[Title 10 CFR ]
[Code of Federal Regulations (annual edition) - January 1, 2018 Edition]
[From the U.S. Government Publishing Office]



[[Page i]]

          

          Title 10

Energy


________________________

Parts 51 to 199

                         Revised as of January 1, 2018

          Containing a codification of documents of general 
          applicability and future effect

          As of January 1, 2018
                    Published by the Office of the Federal Register 
                    National Archives and Records Administration as a 
                    Special Edition of the Federal Register

[[Page ii]]

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                            Table of Contents



                                                                    Page
  Explanation.................................................       v

  Title 10:
          Chapter I--Nuclear Regulatory Commission (Continued)       3
  Finding Aids:
      Table of CFR Titles and Chapters........................     871
      Alphabetical List of Agencies Appearing in the CFR......     891
      List of CFR Sections Affected...........................     901

[[Page iv]]





                     ----------------------------

                     Cite this Code: CFR
                     To cite the regulations in 
                       this volume use title, 
                       part and section number. 
                       Thus, 10 CFR 51.1 refers 
                       to title 10, part 51, 
                       section 1.

                     ----------------------------

[[Page v]]



                               EXPLANATION

    The Code of Federal Regulations is a codification of the general and 
permanent rules published in the Federal Register by the Executive 
departments and agencies of the Federal Government. The Code is divided 
into 50 titles which represent broad areas subject to Federal 
regulation. Each title is divided into chapters which usually bear the 
name of the issuing agency. Each chapter is further subdivided into 
parts covering specific regulatory areas.
    Each volume of the Code is revised at least once each calendar year 
and issued on a quarterly basis approximately as follows:

Title 1 through Title 16.................................as of January 1
Title 17 through Title 27..................................as of April 1
Title 28 through Title 41...................................as of July 1
Title 42 through Title 50................................as of October 1

    The appropriate revision date is printed on the cover of each 
volume.

LEGAL STATUS

    The contents of the Federal Register are required to be judicially 
noticed (44 U.S.C. 1507). The Code of Federal Regulations is prima facie 
evidence of the text of the original documents (44 U.S.C. 1510).

HOW TO USE THE CODE OF FEDERAL REGULATIONS

    The Code of Federal Regulations is kept up to date by the individual 
issues of the Federal Register. These two publications must be used 
together to determine the latest version of any given rule.
    To determine whether a Code volume has been amended since its 
revision date (in this case, January 1, 2018), consult the ``List of CFR 
Sections Affected (LSA),'' which is issued monthly, and the ``Cumulative 
List of Parts Affected,'' which appears in the Reader Aids section of 
the daily Federal Register. These two lists will identify the Federal 
Register page number of the latest amendment of any given rule.

EFFECTIVE AND EXPIRATION DATES

    Each volume of the Code contains amendments published in the Federal 
Register since the last revision of that volume of the Code. Source 
citations for the regulations are referred to by volume number and page 
number of the Federal Register and date of publication. Publication 
dates and effective dates are usually not the same and care must be 
exercised by the user in determining the actual effective date. In 
instances where the effective date is beyond the cut-off date for the 
Code a note has been inserted to reflect the future effective date. In 
those instances where a regulation published in the Federal Register 
states a date certain for expiration, an appropriate note will be 
inserted following the text.

OMB CONTROL NUMBERS

    The Paperwork Reduction Act of 1980 (Pub. L. 96-511) requires 
Federal agencies to display an OMB control number with their information 
collection request.

[[Page vi]]

Many agencies have begun publishing numerous OMB control numbers as 
amendments to existing regulations in the CFR. These OMB numbers are 
placed as close as possible to the applicable recordkeeping or reporting 
requirements.

PAST PROVISIONS OF THE CODE

    Provisions of the Code that are no longer in force and effect as of 
the revision date stated on the cover of each volume are not carried. 
Code users may find the text of provisions in effect on any given date 
in the past by using the appropriate List of CFR Sections Affected 
(LSA). For the convenience of the reader, a ``List of CFR Sections 
Affected'' is published at the end of each CFR volume. For changes to 
the Code prior to the LSA listings at the end of the volume, consult 
previous annual editions of the LSA. For changes to the Code prior to 
2001, consult the List of CFR Sections Affected compilations, published 
for 1949-1963, 1964-1972, 1973-1985, and 1986-2000.

``[RESERVED]'' TERMINOLOGY

    The term ``[Reserved]'' is used as a place holder within the Code of 
Federal Regulations. An agency may add regulatory information at a 
``[Reserved]'' location at any time. Occasionally ``[Reserved]'' is used 
editorially to indicate that a portion of the CFR was left vacant and 
not accidentally dropped due to a printing or computer error.

INCORPORATION BY REFERENCE

    What is incorporation by reference? Incorporation by reference was 
established by statute and allows Federal agencies to meet the 
requirement to publish regulations in the Federal Register by referring 
to materials already published elsewhere. For an incorporation to be 
valid, the Director of the Federal Register must approve it. The legal 
effect of incorporation by reference is that the material is treated as 
if it were published in full in the Federal Register (5 U.S.C. 552(a)). 
This material, like any other properly issued regulation, has the force 
of law.
    What is a proper incorporation by reference? The Director of the 
Federal Register will approve an incorporation by reference only when 
the requirements of 1 CFR part 51 are met. Some of the elements on which 
approval is based are:
    (a) The incorporation will substantially reduce the volume of 
material published in the Federal Register.
    (b) The matter incorporated is in fact available to the extent 
necessary to afford fairness and uniformity in the administrative 
process.
    (c) The incorporating document is drafted and submitted for 
publication in accordance with 1 CFR part 51.
    What if the material incorporated by reference cannot be found? If 
you have any problem locating or obtaining a copy of material listed as 
an approved incorporation by reference, please contact the agency that 
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contacting the agency, you find the material is not available, please 
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or call 202-741-6010.

CFR INDEXES AND TABULAR GUIDES

    A subject index to the Code of Federal Regulations is contained in a 
separate volume, revised annually as of January 1, entitled CFR Index 
and Finding Aids. This volume contains the Parallel Table of Authorities 
and Rules. A list of CFR titles, chapters, subchapters, and parts and an 
alphabetical list of agencies publishing in the CFR are also included in 
this volume.

[[Page vii]]

    An index to the text of ``Title 3--The President'' is carried within 
that volume.
    The Federal Register Index is issued monthly in cumulative form. 
This index is based on a consolidation of the ``Contents'' entries in 
the daily Federal Register.
    A List of CFR Sections Affected (LSA) is published monthly, keyed to 
the revision dates of the 50 CFR titles.

REPUBLICATION OF MATERIAL

    There are no restrictions on the republication of material appearing 
in the Code of Federal Regulations.

INQUIRIES

    For a legal interpretation or explanation of any regulation in this 
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the top of odd-numbered pages.
    For inquiries concerning CFR reference assistance, call 202-741-6000 
or write to the Director, Office of the Federal Register, National 
Archives and Records Administration, 8601 Adelphi Road, College Park, MD 
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ELECTRONIC SERVICES

    The full text of the Code of Federal Regulations, the LSA (List of 
CFR Sections Affected), The United States Government Manual, the Federal 
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information. Connect to NARA's web site at www.archives.gov/federal-
register.
    The e-CFR is a regularly updated, unofficial editorial compilation 
of CFR material and Federal Register amendments, produced by the Office 
of the Federal Register and the Government Publishing Office. It is 
available at www.ecfr.gov.

    Oliver A. Potts,
    Director,
    Office of the Federal Register
    January 1, 2018







[[Page ix]]



                               THIS TITLE

    Title 10--Energy is composed of four volumes. The parts in these 
volumes are arranged in the following order: Parts 1-50, 51-199, 200-499 
and part 500-end. The first and second volumes containing parts 1-199 
are comprised of chapter I--Nuclear Regulatory Commission. The third and 
fourth volumes containing part 200-end are comprised of chapters II, III 
and X--Department of Energy, chapter XIII--Nuclear Waste Technical 
Review Board, and chapter XVII--Defense Nuclear Facilities Safety Board. 
The contents of these volumes represent all current regulations codified 
under this title of the CFR as of January 1, 2018.

    For this volume, Cheryl E. Sirofchuck was Chief Editor. The Code of 
Federal Regulations publication program is under the direction of John 
Hyrum Martinez, assisted by Stephen J. Frattini.

[[Page 1]]



                            TITLE 10--ENERGY




                  (This book contains parts 51 to 199)

  --------------------------------------------------------------------
                                                                    Part

chapter i--Nuclear Regulatory Commission (Continued)........          51

[[Page 3]]



          CHAPTER I--NUCLEAR REGULATORY COMMISSION (CONTINUED)




  --------------------------------------------------------------------


  Editorial Note: Nomenclature changes to chapter I appear at 70 FR 
69421, Nov. 16, 2005, and at 72 FR 33386, June 18, 2007.
Part                                                                Page
51              Environmental protection regulations for 
                    domestic licensing and related 
                    regulatory functions....................           5
52              Licenses, certifications, and approvals for 
                    nuclear power plants....................          67
53              [Reserved]

54              Requirements for renewal of operating 
                    licenses for nuclear power plants.......         151
55              Operators' licenses.........................         158
60              Disposal of high-level radioactive wastes in 
                    geologic repositories...................         174
61              Licensing requirements for land disposal of 
                    radioactive waste.......................         210
62              Criteria and procedures for emergency access 
                    to non-federal and regional low-level 
                    waste disposal facilities...............         237
63              Disposal of high-level radioactive wastes in 
                    a geologic repository at Yucca Mountain, 
                    Nevada..................................         245
70              Domestic licensing of special nuclear 
                    material................................         288
71              Packaging and transportation of radioactive 
                    material................................         338
72              Licensing requirements for the independent 
                    storage of spent nuclear fuel, high-
                    level radioactive waste, and reactor-
                    related greater than Class C waste......         395
73              Physical protection of plants and materials.         461
74              Material control and accounting of special 
                    nuclear material........................         589
75              Safeguards on nuclear material--
                    implementation of US/IAEA agreement.....         612
76              Certification of gaseous diffusion plants...         628
81              Standard specifications for the granting of 
                    patent licenses.........................         654

[[Page 4]]

95              Facility security clearance and safeguarding 
                    of national security information and 
                    restricted data.........................         661
100             Reactor site criteria.......................         679
110             Export and import of nuclear equipment and 
                    material................................         694
140             Financial protection requirements and 
                    indemnity agreements....................         750
150             Exemptions and continued regulatory 
                    authority in Agreement States and in 
                    offshore waters under section 274.......         822
160             Trespassing on Commission property..........         836
170             Fees for facilities, materials, import and 
                    export licenses, and other regulatory 
                    services under the Atomic Energy Act of 
                    1954, as amended........................         837
171             Annual fees for reactor licenses and fuel 
                    cycle licenses and materials licenses, 
                    including holders of certificates of 
                    compliance, registrations, and quality 
                    assurance program approvals and 
                    government agencies licensed by the NRC.         852
172-199         [Reserved]

[[Page 5]]



PART 51_ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING
AND RELATED REGULATORY FUNCTIONS--Table of Contents



Sec.
51.1 Scope.
51.2 Subparts.
51.3 Resolution of conflict.
51.4 Definitions.
51.5 Interpretations.
51.6 Specific exemptions.

  Subpart A_National Environmental Policy Act_Regulations Implementing 
                             Section 102(2)

51.10 Purpose and scope of subpart; application of regulations of 
          Council on Environmental Quality.
51.11 Relationship to other subparts. [Reserved]
51.12 Application of subpart to ongoing environmental work.
51.13 Emergencies.
51.14 Definitions.
51.15 Time schedules.
51.16 Proprietary information.
51.17 Information collection requirements; OMB approval.

                         Preliminary Procedures

           classification of licensing and regulatory actions

51.20 Criteria for and identification of licensing and regulatory 
          actions requiring environmental impact statements.
51.21 Criteria for and identification of licensing and regulatory 
          actions requiring environmental assessments.
51.22 Criterion for categorical exclusion; identification of licensing 
          and regulatory actions eligible for categorical exclusion or 
          otherwise not requiring environmental review.
51.23 Environmental impacts of continued storage of spent nuclear fuel 
          beyond the licensed life for operation of a reactor.

determinations to prepare environmental impact statements, environmental 
assessments or findings of no significant impact, and related procedures

51.25 Determination to prepare environmental impact statement or 
          environmental assessment; eligibility for categorical 
          exclusion.
51.26 Requirement to publish notice of intent and conduct scoping 
          process.
51.27 Notice of intent.

                                 scoping

51.28 Scoping--participants.
51.29 Scoping-environmental impact statement and supplement to 
          environmental impact statement.

                        environmental assessment

51.30 Environmental assessment.
51.31 Determinations based on environmental assessment.

                    finding of no significant impact

51.32 Finding of no significant impact.
51.33 Draft finding of no significant impact; distribution.
51.34 Preparation of finding of no significant impact.
51.35 Requirement to publish finding of no significant impact; 
          limitation on Commission action.

   Environmental Reports and Information--Requirements Applicable to 
                Applicants and Petitioners for Rulemaking

                                 general

51.40 Consultation with NRC staff.
51.41 Requirement to submit environmental information.

               environmental reports--general requirements

51.45 Environmental report.

      environmental reports--production and utilization facilities

51.49 Environmental report--limited work authorization.
51.50 Environmental report--construction permit, early site permit, or 
          combined license stage.
51.51 Uranium fuel cycle environmental data--Table S-3.
51.52 Environmental effects of transportation of fuel and waste--Table 
          S-4.
51.53 Postconstruction environmental reports.
51.54 Environmental report--manufacturing license.
51.55 Environmental report--standard design certification.
51.58 Environmental report--number of copies; distribution.

                environmental reports--materials licenses

51.60 Environmental report--materials licenses.
51.61 Environmental report--independent spent fuel storage installation 
          (ISFSI) or monitored retrievable storage installation (MRS) 
          license.
51.62 Environmental report--land disposal of radioactive waste licensed 
          under 10 CFR part 61.
51.66 Environmental report--number of copies; distribution.

[[Page 6]]

51.67 Environmental information concerning geologic repositories.

                    environmental reports--rulemaking

51.68 Environmental report--rulemaking.

                     Environmental Impact Statements

       draft environmental impact statements--general requirements

51.70 Draft environmental impact statement--general.
51.71 Draft environmental impact statement--contents.
51.72 Supplement to draft environmental impact statement.
51.73 Request for comments on draft environmental impact statement.
51.74 Distribution of draft environmental impact statement and 
          supplement to draft environmental impact statement; news 
          releases.

   draft environmental impact statements--production and utilization 
                               facilities

51.75 Draft environmental impact statement--construction permit, early 
          site permit, or combined license.
51.76 Draft environmental impact statement--limited work authorization.
51.77 Distribution of draft environmental impact statement.

        draft environmental impact statements--materials licenses

51.80 Draft environmental impact statement--materials license.
51.81 Distribution of draft environmental impact statement.

            draft environmental impact statements--rulemaking

51.85 Draft environmental impact statement--rulemaking.
51.86 Distribution of draft environmental impact statement.

 legislative environmental impact statements--proposals for legislation

51.88 Proposals for legislation.

       final environmental impact statements--general requirements

51.90 Final environmental impact statement--general.
51.91 Final environmental impact statement--contents.
51.92 Supplement to the final environmental impact statement.
51.93 Distribution of final environmental impact statement and 
          supplement to final environmental impact statement; news 
          releases.
51.94 Requirement to consider final environmental impact statement.

   final environmental impact statements--production and utilization 
                               facilities

51.95 Postconstruction environmental impact statements.

        final environmental impact statements--materials licenses

51.97 Final environmental impact statement--materials license.

            final environmental impact statements--rulemaking

51.99 [Reserved]

                NEPA Procedure and Administrative Action

                                 general

51.100 Timing of Commission action.
51.101 Limitations on actions.
51.102 Requirement to provide a record of decision; preparation.
51.103 Record of decision--general.
51.104 NRC proceeding using public hearings; consideration of 
          environmental impact statement.

                  production and utilization facilities

51.105 Public hearings in proceedings for issuance of construction 
          permits or early site permits; limited work authorizations.
51.105a Public hearings in proceedings for issuance of manufacturing 
          licenses.
51.106 Public hearings in proceedings for issuance of operating 
          licenses.
51.107 Public hearings in proceedings for issuance of combined licenses; 
          limited work authorizations.
51.108 Public hearings on Commission findings that inspections, tests, 
          analyses, and acceptance criteria of combined licenses are 
          met.

                           materials licenses

51.109 Public hearings in proceedings for issuance of materials license 
          with respect to a geologic repository.

                               rulemaking

51.110 [Reserved]

         Public Notice of and Access to Environmental Documents

51.116 Notice of intent.
51.117 Draft environmental impact statement--notice of availability.
51.118 Final environmental impact statement--notice of availability.
51.119 Publication of finding of no significant impact; distribution.
51.120 Availability of environmental documents for public inspection.
51.121 Status of NEPA actions.

[[Page 7]]

51.122 List of interested organizations and groups.
51.123 Charges for environmental documents; distribution to public; 
          distribution to governmental agencies.

                               Commenting

51.124 Commission duty to comment.

                          Responsible Official

51.125 Responsible official.

Appendix A to Subpart A of Part 51--Format for Presentation of Material 
          in Environmental Impact Statements
Appendix B to Subpart A of Part 51--Environmental Effect of Renewing the 
          Operating License of a Nuclear Power Plant

Subpart B [Reserved]

    Authority: Atomic Energy Act of 1954, secs. 161, 193 (42 U.S.C. 
2201, 2243); Energy Reorganization Act of 1974, secs. 201, 202 (42 
U.S.C. 5841, 5842); National Environmental Policy Act of 1969 (42 U.S.C. 
4332, 4334, 4335); Nuclear Waste Policy Act of 1982, secs. 144(f), 121, 
135, 141, 148 (42 U.S.C. 10134(f), 10141, 10155, 10161, 10168); 44 
U.S.C. 3504 note.
    Sections 51.20, 51.30, 51.60, 51.80, and 51.97 also issued under 
Nuclear Waste Policy Act secs. 135, 141, 148 (42 U.S.C. 10155, 10161, 
10168).
    Section 51.22 also issued under Atomic Energy Act sec. 274 (42 
U.S.C. 2021) and under Nuclear Waste Policy Act sec. 121 (42 U.S.C. 
10141).
    Sections 51.43, 51.67, and 51.109 also issued under Nuclear Waste 
Policy Act sec. 114(f) (42 U.S.C. 10134(f)).

    Source: 49 FR 9381, Mar. 12, 1984, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 51 appear at 80 FR 
74980, Dec. 1, 2015.



Sec. 51.1  Scope.

    This part contains environmental protection regulations applicable 
to NRC's domestic licensing and related regulatory functions. These 
regulations do not apply to export licensing matters within the scope of 
part 110 of this chapter or to any environmental effects which NRC's 
domestic licensing and related regulatory functions may have upon the 
environment of foreign nations. Subject to these limitations, the 
regulations in this part implement:
    (a) Section 102(2) of the National Environmental Policy Act of 1969, 
as amended.



Sec. 51.2  Subparts.

    (a) The regulations in subpart A of this part implement section 
102(2) of the National Environmental Policy Act of 1969, as amended.



Sec. 51.3  Resolution of conflict.

    In any conflict between a general rule in subpart A of this part and 
a special rule in another subpart of this part or another part of this 
chapter applicable to a particular type of proceeding, the special rule 
governs.



Sec. 51.4  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954 (Pub. L. 83-703, 68 Stat. 
919) including any amendments thereto.
    Commission means the Nuclear Regulatory Commission or its authorized 
representatives.
    Construction means:
    (1) For production and utilization facilities, the activities in 
paragraph (1)(i) of this definition, and does not mean the activities in 
paragraph (1)(ii) of this definition.
    (i) Activities constituting construction are the driving of piles, 
subsurface preparation, placement of backfill, concrete, or permanent 
retaining walls within an excavation, installation of foundations, or 
in-place assembly, erection, fabrication, or testing, which are for:
    (A) Safety-related structures, systems, or components (SSCs) of a 
facility, as defined in 10 CFR 50.2;
    (B) SSCs relied upon to mitigate accidents or transients or used in 
plant emergency operating procedures;
    (C) SSCs whose failure could prevent safety-related SSCs from 
fulfilling their safety-related function;
    (D) SSCs whose failure could cause a reactor scram or actuation of a 
safety-related system;
    (E) SSCs necessary to comply with 10 CFR part 73;
    (F) SSCs necessary to comply with 10 CFR 50.48 and criterion 3 of 10 
CFR part 50, appendix A; and
    (G) Onsite emergency facilities (i.e., technical support and 
operations support centers), necessary to comply with 10 CFR 50.47 and 
10 CFR part 50, appendix E.
    (ii) Construction does not include:

[[Page 8]]

    (A) Changes for temporary use of the land for public recreational 
purposes;
    (B) Site exploration, including necessary borings to determine 
foundation conditions or other preconstruction monitoring to establish 
background information related to the suitability of the site, the 
environmental impacts of construction or operation, or the protection of 
environmental values;
    (C) Preparation of a site for construction of a facility, including 
clearing of the site, grading, installation of drainage, erosion and 
other environmental mitigation measures, and construction of temporary 
roads and borrow areas;
    (D) Erection of fences and other access control measures that are 
not safety or security related, and do not pertain to radiological 
controls;
    (E) Excavation;
    (F) Erection of support buildings (e.g., construction equipment 
storage sheds, warehouse and shop facilities, utilities, concrete mixing 
plants, docking and unloading facilities, and office buildings) for use 
in connection with the construction of the facility;
    (G) Building of service facilities (e.g., paved roads, parking lots, 
railroad spurs, exterior utility and lighting systems, potable water 
systems, sanitary sewerage treatment facilities, and transmission 
lines);
    (H) Procurement or fabrication of components or portions of the 
proposed facility occurring at other than the final, in-place location 
at the facility;
    (I) Manufacture of a nuclear power reactor under a manufacturing 
license under subpart F of part 52 of this chapter to be installed at 
the proposed site and to be part of the proposed facility; or
    (J) With respect to production or utilization facilities, other than 
testing facilities and nuclear power plants, required to be licensed 
under section 104.a or section 104.c of the Act, the erection of 
buildings which will be used for activities other than operation of a 
facility and which may also be used to house a facility (e.g., the 
construction of a college laboratory building with space for 
installation of a training reactor).
    (2) For materials licenses, taking any site-preparation activity at 
the site of a facility subject to the regulations in 10 CFR parts 30, 
36, 40, and 70 that has a reasonable nexus to radiological health and 
safety or the common defense and security; provided, however, that 
construction does not mean:
    (i) Those actions or activities listed in paragraphs (1)(ii)(A)-(H) 
of this definition; or
    (ii) Taking any other action that has no reasonable nexus to 
radiological health and safety or the common defense and security.
    NRC means the Nuclear Regulatory Commission, the agency established 
by Title II of the Energy Reorganization Act of 1974, as amended.
    NRC staff means any NRC officer or employee or his/her authorized 
representative, except a Commissioner, a member of a Commissioner's 
immediate staff, an Atomic Safety and Licensing Board, a presiding 
officer, an administrative judge, an administrative law judge, or any 
other officer or employee of the Commission who performs adjudicatory 
functions.
    NRC Staff Director means:

Executive Director for Operations;
Director, Office of Nuclear Reactor Regulation;
Director, Office of New Reactors;
Director, Office of Nuclear Material Safety and Safeguards;
Director, Office of Nuclear Regulatory Research;
Director, Office of Governmental and Public Affairs; and
The designee of any NRC staff director.

[49 FR 9381, Mar. 12, 1984, as amended at 51 FR 35999, Oct. 8, 1986; 52 
FR 31612, Aug. 21, 1987; 72 FR 57443, Oct. 9, 2007; 73 FR 5723, Jan. 31, 
2008; 76 FR 56964, Sept. 15, 2011; 77 FR 46599, Aug. 3, 2012; 79 FR 
75740, Dec. 19, 2014]



Sec. 51.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the regulations in this part by any officer or 
employee of the Commission other than a written interpretation by the 
General Counsel will be recognized to be binding upon the Commission.



Sec. 51.6  Specific exemptions.

    The Commission may, upon application of any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines

[[Page 9]]

are authorized by law and are otherwise in the public interest.



  Subpart A_National Environmental Policy Act_Regulations Implementing 
                             Section 102(2)



Sec. 51.10  Purpose and scope of subpart; application of regulations 
of Council on Environmental Quality.

    (a) The National Environmental Policy Act of 1969, as amended (NEPA) 
directs that, to the fullest extent possible: (1) The policies, 
regulations, and public laws of the United States shall be interpreted 
and administered in accordance with the policies set forth in NEPA, and 
(2) all agencies of the Federal Government shall comply with the 
procedures in section 102(2) of NEPA except where compliance would be 
inconsistent with other statutory requirements. The regulations in this 
subpart implement section 102(2) of NEPA in a manner which is consistent 
with the NRC's domestic licensing and related regulatory authority under 
the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act 
of 1974, as amended, and the Uranium Mill Tailings Radiation Control Act 
of 1978, and which reflects the Commission's announced policy to take 
account of the regulations of the Council on Environmental Quality 
published November 29, 1978 (43 FR 55978-56007) voluntarily, subject to 
certain conditions. This subpart does not apply to export licensing 
matters within the scope of part 110 of this chapter nor does it apply 
to any environmental effects which NRC's domestic licensing and related 
regulatory functions may have upon the environment of foreign nations.
    (b) The Commission recognizes a continuing obligation to conduct its 
domestic licensing and related regulatory functions in a manner which is 
both receptive to environmental concerns and consistent with the 
Commission's responsibility as an independent regulatory agency for 
protecting the radiological health and safety of the public. 
Accordingly, the Commission will:
    (1) Examine any future interpretation or change to the Council's 
NEPA regulations;
    (2) Follow the provisions of 40 CFR 1501.5 and 1501.6 relating to 
lead agencies and cooperating agencies, except that the Commission 
reserves the right to prepare an independent environmental impact 
statement whenever the NRC has regulatory jurisdiction over an acitivity 
even though the NRC has not been designated as lead agency for 
preparation of the statement; and
    (3) Reserve the right to make a final decision on any matter within 
the NRC's regulatory authority even though another agency has made a 
predecisional referral of an NRC action to the Council under the 
procedures of 40 CFR part 1504.
    (c) The regulations in this subpart \1\ also address the limitations 
imposed on NRC's authority and responsibility under the National 
Environmental Policy Act of 1969, as amended, by the Federal Water 
Pollution Control Act Amendments of 1972, Pub. L. 92-500, 86 Stat. 816 
et seq. (33 U.S.C. 1251 et seq.) In accordance with section 511(c)(2) of 
the Federal Water Pollution Control Act (86 Stat. 893, 33 U.S.C 
1371(c)(2)) the NRC recognizes that responsibility for Federal 
regulation of nonradiological pollutant discharges \2\ into receiving 
waters rests by statute with the Environmental Protection Agency.
---------------------------------------------------------------------------

    \1\ See also Second Memorandum of Understanding Regarding 
Implementation of Certain NRC and EPA Responsibilities and Policy 
Statement on Implementation of Section 511 of the Federal Water 
Pollution Control Act (FWPCA) attached as Appendix A thereto, which were 
published in the Federal Register on December 31, 1975 (40 FR 60115) and 
became effective January 30, 1976.
    \2\ On June 1, 1976, the U.S. Supreme Court held that `` 
`pollutants' subject to regulation under the FWPCA [Federal Water 
Pollution Control Act] do not include source, byproduct, and special 
nuclear materials, . . .'' Train v. Colorado PIRG, 426 U.S. 1 at 25.
---------------------------------------------------------------------------

    (d) Commission actions initiating or relating to administrative or 
judicial civil or criminal enforcement actions or proceedings are not 
subject to Section 102(2) of NEPA. These actions include issuance of 
notices of violation, orders, and denials of requests for action 
pursuant to subpart B of part 2 of this chapter; matters covered by part 
15 and part 160 of this chapter; and issuance of confirmatory action 
letters, bulletins, generic letters, notices

[[Page 10]]

---------------------------------------------------------------------------
of deviation, and notices of nonconformance.

[49 FR 9381, Mar. 12, 1984, as amended at 54 FR 43578, Oct. 26, 1989; 61 
FR 43408, Aug. 22, 1996]



Sec. 51.11  Relationship to other subparts. [Reserved]



Sec. 51.12  Application of subpart to ongoing environmental work.

    (a) Except as otherwise provided in this section, the regulations in 
this subpart shall apply to the fullest extent practicable to NRC's 
ongoing environmental work.
    (b) No environmental report or any supplement to an environmental 
report filed with the NRC and no environmental assessment, environmental 
impact statement or finding of no significant impact or any supplement 
to any of the foregoing issued by the NRC before June 7, 1984, need be 
redone and no notice of intent to prepare an environmental impact 
statement or notice of availability of these environmental documents 
need be republished solely by reason of the promulgation on March 12, 
1984, of this revision of part 51.

[49 FR 9381, Mar. 12, 1984, as amended at 49 FR 24513, June 14, 1984]



Sec. 51.13  Emergencies.

    Whenever emergency circumstances make it necessary and whenever, in 
other situations, the health and safety of the public may be adversely 
affected if mitigative or remedial actions are delayed, the Commission 
may take an action with significant environmental impact without 
observing the provisions of these regulations. In taking an action 
covered by this section, the Commission will consult with the Council as 
soon as feasible concerning appropriate alternative NEPA arrangements.



Sec. 51.14  Definitions.

    (a) As used in this subpart:
    Categorical Exclusion means a category of actions which do not 
individually or cumulatively have a significant effect on the human 
environment and which the Commission has found to have no such effect in 
accordance with procedures set out in Sec. 51.22, and for which, 
therefore, neither an environmental assessment nor an environmental 
impact statement is required.
    Cooperating Agency means any Federal agency other than the NRC which 
has jurisdiction by law or special expertise with respect to any 
environmental impact involved in a proposal (or a reasonable 
alternative) for legislation or other major Federal action significantly 
affecting the quality of the human environment. By agreement with the 
Commission, a State or local agency of similar qualifications or, when 
the effects are on a reservation, an Indian Tribe, may become a 
cooperating agency.
    Council means the Council on Environmental Quality (CEQ) established 
by Title II of NEPA.
    DOE means the U.S. Department of Energy or its duly authorized 
representatives.
    Environmental Assessment means a concise public document for which 
the Commission is responsible that serves to:
    (1) Briefly provide sufficient evidence and analysis for determining 
whether to prepare an environmental impact statement or a finding of no 
significant impact.
    (2) Aid the Commission's compliance with NEPA when no environmental 
impact statement is necessary.
    (3) Facilitate preparation of an environmental impact statement when 
one is necessary.
    Environmental document includes an environmental assessment, an 
environmental impact statement, a finding of no significant impact, an 
environmental report and any supplements to or comments upon those 
documents, and a notice of intent.
    Environmental Impact Statement means a detailed written statement as 
required by section 102(2)(C) of NEPA.
    Environmental report means a document submitted to the Commission by 
an applicant for a permit, license, or other form of permission, or an 
amendment to or renewal of a permit, license or other form of 
permission, or by a petitioner for rulemaking, in order to aid the 
Commission in complying with section 102(2) of NEPA.
    Finding of No Significant Impact means a concise public document for

[[Page 11]]

which the Commission is responsible that briefly states the reasons why 
an action, not otherwise excluded, will not have a significant effect on 
the human environment and for which therefore an environmental impact 
statement will not be prepared.
    NEPA means the National Environmental Policy Act of 1969, as amended 
(Pub. L. 91-190, 83 Stat. 852, 856, as amended by Pub. L. 94-83, 89 
Stat. 424, 42 U.S.C. 4321, et seq.).
    Notice of Intent means a notice that an environmental impact 
statement will be prepared and considered.
    Uranium enrichment facility means:
    (1) Any facility used for separating the isotopes for uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or
    (2) Any equipment or device, or important component part especially 
designed for such equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.
    (b) The definitions in 40 CFR 1508.3, 1508.7, 1508.8, 1508.14, 
1508.15, 1508.16, 1508.17, 1508.18, 1508.20, 1508.23, 1508.25, 1508.26, 
and 1508.27, will also be used in implementing section 102(2) of NEPA.

[49 FR 9381, Mar. 12, 1984, as amended at 57 FR 18391, Apr. 30, 1992]



Sec. 51.15  Time schedules.

    Consistent with the purposes of NEPA, the Administrative Procedure 
Act, the Commission's rules of practice in part 2 of this chapter, 
Sec. Sec. 51.100 and 51.101, and with other essential considerations of 
national policy:
    (a) The appropriate NRC staff director may, and upon the request of 
an applicant for a proposed action or a petitioner for rulemaking shall, 
establish a time schedule for all or any constituent part of the NRC 
staff NEPA process. To the maximum extent practicable, the NRC staff 
will conduct its NEPA review in accordance with any time schedule 
established under this section.
    (b) As specified in 10 CFR part 2, the presiding officer, the Atomic 
Safety and Licensing Board or the Commissioners acting as a collegial 
body may establish a time schedule for all or any part of an 
adjudicatory or rulemaking proceeding to the extent that each has 
jurisdiction.

[49 FR 9381, Mar. 12, 1984, as amended at 69 FR 2276, Jan. 14, 2004]



Sec. 51.16  Proprietary information.

    (a) Proprietary information, such as trade secrets or privileged or 
confidential commercial or financial information, will be treated in 
accordance with the procedures provided in Sec. 2.390 of this chapter.
    (b) Any proprietary information which a person seeks to have 
withheld from public disclosure shall be submitted in accordance with 
Sec. 2.390 of this chapter. When submitted, the proprietary information 
should be clearly identified and accompanied by a request, containing 
detailed reasons and justifications, that the proprietary information be 
withheld from public disclosure. A non-proprietary summary describing 
the general content of the proprietary information should also be 
provided.

[69 FR 2276, Jan. 14, 2004]



Sec. 51.17  Information collection requirements; OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0021.
    (b) The approved information collection requirements in this part 
appear in Sec. Sec. 51.6, 51.16, 51.41, 51.45, 51.49, 51.50, 51.51, 
51.52, 51.53, 51.54, 51.55, 51.58, 51.60, 51.61, 51.62, 51.66, 51.68, 
and 51.69.

[49 FR 24513, June 14, 1984, as amended at 62 FR 52188, Oct. 6, 1997; 67 
FR 67100, Nov. 4, 2002; 72 FR 57443, Oct. 9, 2007]

[[Page 12]]

                         Preliminary Procedures

           classification of licensing and regulatory actions



Sec. 51.20  Criteria for and identification of licensing and 
regulatory actions requiring environmental impact statements.

    (a) Licensing and regulatory actions requiring an environmental 
impact statement shall meet at least one of the following criteria:
    (1) The proposed action is a major Federal action significantly 
affecting the quality of the human environment.
    (2) The proposed action involves a matter which the Commission, in 
the exercise of its discretion, has determined should be covered by an 
environmental impact statement.
    (b) The following types of actions require an environmental impact 
statement or a supplement to an environmental impact statement:
    (1) Issuance of a limited work authorization or a permit to 
construct a nuclear power reactor, testing facility, or fuel 
reprocessing plant under part 50 of this chapter, or issuance of an 
early site permit under part 52 of this chapter.
    (2) Issuance or renewal of a full power or design capacity license 
to operate a nuclear power reactor, testing facility, or fuel 
reprocessing plant under part 50 of this chapter, or a combined license 
under part 52 of this chapter.
    (3) Issuance of a permit to construct or a design capacity license 
to operate or renewal of a design capacity license to operate an 
isotopic enrichment plant pursuant to part 50 of this chapter.
    (4) Conversion of a provisional operating license for a nuclear 
power reactor, testing facility or fuel reprocessing plant to a full 
term or design capacity license pursuant to part 50 of this chapter if a 
final environmental impact statement covering full term or design 
capacity operation has not been previously prepared.
    (5)-(6) [Reserved]
    (7) Issuance of a license to possess and use special nuclear 
material for processing and fuel fabrication, scrap recovery, or 
conversion of uranium hexafluoride pursuant to part 70 of this chapter.
    (8) Issuance of a license to possess and use source material for 
uranium milling or production of uranium hexafluoride pursuant to part 
40 of this chapter.
    (9) Issuance of a license pursuant to part 72 of this chapter for 
the storage of spent fuel in an independent spent fuel storage 
installation (ISFSI) at a site not occupied by a nuclear power reactor, 
or for the storage of spent fuel or high-level radioactive waste in a 
monitored retrievable storage installation (MRS).
    (10) Issuance of a license for a uranium enrichment facility.
    (11) Issuance of renewal of a license authorizing receipt and 
disposal of radioactive waste from other persons pursuant to part 61 of 
this chapter.
    (12) Issuance of a license amendment pursuant to part 61 of this 
chapter authorizing (i) closure of a land disposal site, (ii) transfer 
of the license to the disposal site owner for the purpose of 
institutional control, or (iii) termination of the license at the end of 
the institutional control period.
    (13) Issuance of a construction authorization and license pursuant 
to part 60 or part 63 of this chapter.
    (14) Any other action which the Commission determines is a major 
Commission action significantly affecting the quality of the human 
environment. As provided in Sec. 51.22(b), the Commission may, in 
special circumstances, prepare an environmental impact statement on an 
action covered by a categorical exclusion.

[49 FR 9381, Mar. 12, 1984, as amended at 53 FR 31681, Aug. 19, 1988; 53 
FR 24052, June 27, 1988; 54 FR 15398, Apr. 18, 1989; 54 FR 27870, July 
3, 1989; 57 FR 18392, Apr. 30, 1992; 66 FR 55790, Nov. 2, 2001; 72 FR 
49509, Aug. 28, 2007]



Sec. 51.21  Criteria for and identification of licensing and
regulatory actions requiring environmental assessments.

    All licensing and regulatory actions subject to this subpart require 
an environmental assessment except those identified in Sec. 51.20(b) as 
requiring an environmental impact statement, those identified in Sec. 
51.22(c) as categorical exclusions, and those identified in Sec. 
51.22(d) as other actions not requiring environmental review. As 
provided in

[[Page 13]]

Sec. 51.22(b), the Commission may, in special circumstances, prepare an 
environmental assessment on an action covered by a categorical 
exclusion.

[54 FR 27870, July 3, 1989]



Sec. 51.22  Criterion for categorical exclusion; identification of
licensing and regulatory actions eligible for categorical exclusion
or otherwise not requiring environmental review.

    (a) Licensing, regulatory, and administrative actions eligible for 
categorical exclusion shall meet the following criterion: The action 
belongs to a category of actions which the Commission, by rule or 
regulation, has declared to be a categorical exclusion, after first 
finding that the category of actions does not individually or 
cumulatively have a significant effect on the human environment.
    (b) Except in special circumstances, as determined by the Commission 
upon its own initiative or upon request of any interested person, an 
environmental assessment or an environmental impact statement is not 
required for any action within a category of actions included in the 
list of categorical exclusions set out in paragraph (c) of this section. 
Special circumstances include the circumstance where the proposed action 
involves unresolved conflicts concerning alternative uses of available 
resources within the meaning of section 102(2)(E) of NEPA.
    (c) The following categories of actions are categorical exclusions:
    (1) Amendments to parts 1, 2, 4, 5, 7, 8, 9, 10, 11, 12, 13, 15, 16, 
19, 21, 25, 26, 55, 75, 95, 110, 140, 150, 160, 170, or 171 of this 
chapter, and actions on petitions for rulemaking relating to parts 1, 2, 
4, 5, 7, 9, 10, 11, 12, 13, 14, 15, 16, 19, 21, 25, 26, 55, 75, 95, 110, 
140, 150, 160, 170, or 171 of this chapter.
    (2) Amendments to the regulations in this chapter which are 
corrective or of a minor or nonpolicy nature and do not substantially 
modify existing regulations, and actions on petitions for rulemaking 
relating to these amendments.
    (3) Amendments to parts 20, 30, 31, 32, 33, 34, 35, 37, 39, 40, 50, 
51, 52, 54, 60, 61, 63, 70, 71, 72, 73, 74, 81, and 100 of this chapter 
which relate to--
    (i) Procedures for filing and reviewing applications for licenses or 
construction permits or early site permits or other forms of permission 
or for amendments to or renewals of licenses or construction permits or 
early site permits or other forms of permission;
    (ii) Recordkeeping requirements;
    (iii) Reporting requirements;
    (iv) Education, training, experience, qualification or other 
employment suitability requirements or
    (v) Actions on petitions for rulemaking relating to these 
amendments.
    (4) Entrance into or amendment, suspension, or termination of all or 
part of an agreement with a State pursuant to section 274 of the Atomic 
Energy Act of 1954, as amended, providing for assumption by the State 
and discontinuance by the Commission of certain regulatory authority of 
the Commission.
    (5) Procurement of general equipment and supplies.
    (6) Procurement of technical assistance, confirmatory research 
provided that the confirmatory research does not involve any significant 
construction impacts, and personal services relating to the safe 
operation and protection of commercial reactors, other facilities, and 
materials subject to NRC licensing and regulation.
    (7) Personnel actions.
    (8) Issuance, amendment, or renewal of operators' licenses pursuant 
to part 55 of this chapter.
    (9) Issuance of an amendment to a permit or license for a reactor 
under part 50 or part 52 of this chapter that changes a requirement or 
issuance of an exemption from a requirement, with respect to 
installation or use of a facility component located within the 
restricted area, as defined in part 20 of this chapter; or the issuance 
of an amendment to a permit or license for a reactor under part 50 or 
part 52 of this chapter that changes an inspection or a surveillance 
requirement; provided that:
    (i) The amendment or exemption involves no significant hazards 
consideration;
    (ii) There is no significant change in the types or significant 
increase in the amounts of any effluents that may be released offsite; 
and

[[Page 14]]

    (iii) There is no significant increase in individual or cumulative 
occupational radiation exposure.
    (10) Issuance of an amendment to a permit or license issued under 
this chapter which--
    (i) Changes surety, insurance and/or indemnity requirements;
    (ii) Changes recordkeeping, reporting, or administrative procedures 
or requirements;
    (iii) Changes the licensee's or permit holder's name, phone number, 
business or e-mail address;
    (iv) Changes the name, position, or title of an officer of the 
licensee or permit holder, including but not limited to, the radiation 
safety officer or quality assurance manager; or
    (v) Changes the format of the license or permit or otherwise makes 
editorial, corrective or other minor revisions, including the updating 
of NRC approved references.
    (11) Issuance of amendments to licenses for fuel cycle plants and 
radioactive waste disposal sites and amendments to materials licenses 
identified in Sec. 51.60(b)(1) which are administrative, 
organizational, or procedural in nature, or which result in a change in 
process operations or equipment, provided that (i) there is no 
significant change in the types or significant increase in the amounts 
of any effluents that may be released offsite, (ii) there is no 
significant increase in individual or cumulative occupational radiation 
exposure, (iii) there is no significant construction impact, and (iv) 
there is no significant increase in the potential for or consequences 
from radiological accidents.
    (12) Issuance of an amendment to a license under parts 50, 52, 60, 
61, 63, 70, 72, or 75 of this chapter relating solely to safeguards 
matters (i.e., protection against sabotage or loss or diversion of 
special nuclear material) or issuance of an approval of a safeguards 
plan submitted under parts 50, 52, 70, 72, and 73 of this chapter, 
provided that the amendment or approval does not involve any significant 
construction impacts. These amendments and approvals are confined to--
    (i) Organizational and procedural matters;
    (ii) Modifications to systems used for security and/or materials 
accountability;
    (iii) Administrative changes; and
    (iv) Review and approval of transportation routes pursuant to 10 CFR 
73.37.
    (13) Approval of package designs for packages to be used for the 
transportation of licensed materials.
    (14) Issuance, amendment, or renewal of materials licenses issued 
pursuant to 10 CFR parts 30, 31, 32, 33, 34, 35, 36, 39, 40 or part 70 
authorizing the following types of activities:
    (i) Distribution of radioactive material and devices or products 
containing radioactive material to general licensees and to persons 
exempt from licensing.
    (ii) Distribution of radiopharmaceuticals, generators, reagent kits 
and/or sealed sources to persons licensed pursuant to 10 CFR 35.18.
    (iii) Nuclear pharmacies.
    (iv) Medical and veterinary.
    (v) Use of radioactive materials for research and development and 
for educational purposes.
    (vi) Industrial radiography.
    (vii) Irradiators.
    (viii) Use of sealed sources and use of gauging devices, analytical 
instruments and other devices containing sealed sources.
    (ix) Use of uranium as shielding material in containers or devices.
    (x) Possession of radioactive material incident to performing 
services such as installation, maintenance, leak tests and calibration.
    (xi) Use of sealed sources and/or radioactive tracers in well-
logging procedures.
    (xii) Acceptance of packaged radioactive wastes from others for 
transfer to licensed land burial facilities provided the interim storage 
period for any package does not exceed 180 days and the total possession 
limit for all packages held in interim storage at the same time does not 
exceed 50 curies.
    (xiii) Manufacturing or processing of source, byproduct, or special 
nuclear materials for distribution to other licensees, except processing 
of source material for extraction of rare earth and other metals.
    (xiv) Nuclear laundries.

[[Page 15]]

    (xv) Possession, manufacturing, processing, shipment, testing, or 
other use of depleted uranium military munitions.
    (xvi) Any use of source, byproduct, or special nuclear material not 
listed above which involves quantities and forms of source, byproduct, 
or special nuclear material similar to those listed in paragraphs 
(c)(14) (i) through (xv) of this section (Category 14).
    (15) Issuance, amendment or renewal of licenses for import of 
nuclear facilities and materials pursuant to part 110 of this chapter, 
except for import of spent power reactor fuel.
    (16) Issuance or amendment of guides for the implementation of 
regulations in this chapter, and issuance or amendment of other 
informational and procedural documents that do not impose any legal 
requirements.
    (17) Issuance of an amendment to a permit or license under parts 30, 
40, 50, 52, or part 70 of this chapter which deletes any limiting 
condition of operation or monitoring requirement based on or applicable 
to any matter subject to the provisions of the Federal Water Pollution 
Control Act.
    (18) Issuance of amendments or orders authorizing licensees of 
production or utilization facilities to resume operation, provided the 
basis for the authorization rests solely on a determination or 
redetermination by the Commission that applicable emergency planning 
requirements are met.
    (19) Issuance, amendment, modification, or renewal of a certificate 
of compliance of gaseous diffusion enrichment facilities pursuant to 10 
CFR part 76.
    (20) Decommissioning of sites where licensed operations have been 
limited to the use of--
    (i) Small quantities of short-lived radioactive materials;
    (ii) Radioactive materials in sealed sources, provided there is no 
evidence of leakage of radioactive material from these sealed sources; 
or
    (iii) Radioactive materials in such a manner that a decommissioning 
plan is not required by 10 CFR 30.36(g)(1), 40.42(g)(1), or 70.38(g)(1), 
and the NRC has determined that the facility meets the radiological 
criteria for unrestricted use in 10 CFR 20.1402 without further 
remediation or analysis.
    (21) Approvals of direct or indirect transfers of any license issued 
by NRC and any associated amendments of license required to reflect the 
approval of a direct or indirect transfer of an NRC license.
    (22) Issuance of a standard design approval under part 52 of this 
chapter.
    (23) The Commission finding for a combined license under Sec. 
52.103(g) of this chapter.
    (24) Grants to institutions of higher education in the United 
States, to fund scholarships, fellowships, and stipends for the study of 
science, engineering, or another field of study that the NRC determines 
is in a critical skill area related to its regulatory mission, to 
support faculty and curricular development in such fields, and to 
support other domestic educational, technical assistance, or training 
programs (including those of trade schools) in such fields, except to 
the extent that such grants or programs include activities directly 
affecting the environment, such as:
    (i) The construction of facilities;
    (ii) A major disturbance brought about by blasting, drilling, 
excavating or other means;
    (iii) Field work, except that which only involves noninvasive or 
non-harmful techniques such as taking water or soil samples or 
collecting non-protected species of flora and fauna; or
    (iv) The release of radioactive material.
    (25) Granting of an exemption from the requirements of any 
regulation of this chapter, provided that--
    (i) There is no significant hazards consideration;
    (ii) There is no significant change in the types or significant 
increase in the amounts of any effluents that may be released offsite;
    (iii) There is no significant increase in individual or cumulative 
public or occupational radiation exposure;
    (iv) There is no significant construction impact;
    (v) There is no significant increase in the potential for or 
consequences from radiological accidents; and
    (vi) The requirements from which an exemption is sought involve:
    (A) Recordkeeping requirements;
    (B) Reporting requirements;

[[Page 16]]

    (C) Inspection or surveillance requirements;
    (D) Equipment servicing or maintenance scheduling requirements;
    (E) Education, training, experience, qualification, requalification 
or other employment suitability requirements;
    (F) Safeguard plans, and materials control and accounting inventory 
scheduling requirements;
    (G) Scheduling requirements;
    (H) Surety, insurance or indemnity requirements; or
    (I) Other requirements of an administrative, managerial, or 
organizational nature.
    (d) In accordance with section 121 of the Nuclear Waste Policy Act 
of 1982 (42 U.S.C. 10141), the promulgation of technical requirements 
and criteria that the Commission will apply in approving or disapproving 
applications under part 60 or 63 of this chapter shall not require an 
environmental impact statement, an environmental assessment, or any 
environmental review under subparagraph (E) or (F) of section 102(2) of 
NEPA.

[49 FR 9381, Mar. 12, 1984]

    Editorial Note: For Federal Register citations affecting Sec. 
51.22, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 51.23  Environmental impacts of continued storage of spent 
nuclear fuel beyond the licensed life for operation of a reactor.

    (a) The Commission has generically determined that the environmental 
impacts of continued storage of spent nuclear fuel beyond the licensed 
life for operation of a reactor are those impacts identified in NUREG-
2157, ``Generic Environmental Impact Statement for Continued Storage of 
Spent Nuclear Fuel.''
    (b) The environmental reports described in Sec. Sec. 51.50, 51.53, 
and 51.61 are not required to discuss the environmental impacts of spent 
nuclear fuel storage in a reactor facility storage pool or an ISFSI for 
the period following the term of the reactor operating license, reactor 
combined license, or ISFSI license. The impact determinations in NUREG-
2157 regarding continued storage shall be deemed incorporated into the 
environmental impact statements described in Sec. Sec. 51.75, 51.80(b), 
51.95, and 51.97(a). The impact determinations in NUREG-2157 regarding 
continued storage shall be considered in the environmental assessments 
described in Sec. Sec. 51.30(b) and 51.95(d), if the impacts of 
continued storage of spent fuel are relevant to the proposed action.
    (c) This section does not alter any requirements to consider the 
environmental impacts of spent fuel storage during the term of a reactor 
operating license or combined license, or a license for an ISFSI in a 
licensing proceeding.

[49 FR 34694, Aug. 31, 1984, as amended at 55 FR 38474, Sept. 18, 1990; 
72 FR 49509, Aug. 28, 2007; 75 FR 81037, Dec. 23, 2010; 79 FR 56260, 
Sept. 19, 2014]

determinations to prepare environmental impact statements, environmental 
assessments or findings of no significant impact, and related procedures



Sec. 51.25  Determination to prepare environmental impact statement
or environmental assessment; eligibility for categorical exclusion.

    Before taking a proposed action subject to the provisions of this 
subpart, the appropriate NRC staff director will determine on the basis 
of the criteria and classifications of types of actions in Sec. Sec. 
51.20, 51.21 and 51.22 of this subpart whether the proposed action is of 
the type listed in Sec. 51.22(c) as a categorical exclusion or whether 
an environmental impact statement or an environmental assessment should 
be prepared. An environmental assessment is not necessary if it is 
determined that an environmental impact statement will be prepared.



Sec. 51.26  Requirement to publish notice of intent and conduct 
scoping process.

    (a) Whenever the appropriate NRC staff director determines that an 
environmental impact statement will be prepared by NRC in connection 
with a proposed action, a notice of intent will be prepared as provided 
in Sec. 51.27, and

[[Page 17]]

will be published in the Federal Register as provided in Sec. 51.116, 
and an appropriate scoping process (see Sec. Sec. 51.27, 51.28, and 
51.29) will be conducted.
    (b) The scoping process may include a public scoping meeting.
    (c) Upon receipt of an application and accompanying environmental 
impact statement under Sec. 60.22 or Sec. 63.22 of this chapter 
(pertaining to geologic repositories for high-level radioactive waste), 
the appropriate NRC staff director will include in the notice of 
docketing required to be published by Sec. 2.101(f)(8) of this chapter 
a statement of Commission intention to adopt the environmental impact 
statement to the extent practicable. However, if the appropriate NRC 
staff director determines, at the time of such publication or at any 
time thereafter, that NRC should prepare a supplemental environmental 
impact statement in connection with the Commission's action on the 
license application, the NRC shall follow the procedures set out in 
paragraph (a) of this section.
    (d) Whenever the appropriate NRC staff director determines that a 
supplement to an environmental impact statement will be prepared by the 
NRC, a notice of intent will be prepared as provided in Sec. 51.27, and 
will be published in the Federal Register as provided in Sec. 51.116. 
The NRC staff need not conduct a scoping process (see Sec. Sec. 51.27, 
51.28, and 51.29), provided, however, that if scoping is conducted, then 
the scoping must be directed at matters to be addressed in the 
supplement. If scoping is conducted in a proceeding for a combined 
license referencing an early site permit under part 52, then the scoping 
must be directed at matters to be addressed in the supplement as 
described in Sec. 51.92(e).

[49 FR 9381, Mar. 12, 1984, as amended at 54 FR 27870, July 3, 1989; 66 
FR 55791, Nov. 2, 2001; 72 FR 49510, Aug. 28, 2007]



Sec. 51.27  Notice of intent.

    (a) The notice of intent required by Sec. 51.26(a) shall:
    (1) State that an environmental impact statement will be prepared;
    (2) Describe the proposed action and, to the extent sufficient 
information is available, possible alternatives;
    (3) State whether the applicant or petitioner for rulemaking has 
filed an environmental report, and, if so, where copies are available 
for public inspection;
    (4) Describe the proposed scoping process, including the role of 
participants, whether written comments will be accepted, the last date 
for submitting comments and where comments should be sent, whether a 
public scoping meeting will be held, the time and place of any scoping 
meeting or when the time and place of the meeting will be announced; and
    (5) State the name, address and telephone number of an individual in 
NRC who can provide information about the proposed action, the scoping 
process, and the environmental impact statement.
    (b) The notice of intent required by Sec. 51.26(d) shall:
    (1) State that a supplement to a final environmental impact 
statement will be prepared in accordance with Sec. 51.72 or Sec. 
51.92. For a combined license application that references an early site 
permit, the supplement to the early site permit environmental impact 
statement will be prepared in accordance with Sec. 51.92(e);
    (2) Describe the proposed action and, to the extent required, 
possible alternatives. For the case of a combined license referencing an 
early site permit, identify the proposed action as the issuance of a 
combined license for the construction and operation of a nuclear power 
plant as described in the combined license application at the site 
described in the early site permit referenced in the combined license 
application;
    (3) Identify the environmental report prepared by the applicant and 
information on where copies are available for public inspection;
    (4) Describe the matters to be addressed in the supplement to the 
final environmental impact statement;
    (5) Describe any proposed scoping process that the NRC staff may 
conduct, including the role of participants, whether written comments 
will be accepted, the last date for submitting comments and where 
comments should be sent, whether a public scoping meeting will be held, 
the time and place of

[[Page 18]]

any scoping meeting or when the time and place of the meeting will be 
announced; and
    (6) State the name, address, and telephone number of an individual 
in NRC who can provide information about the proposed action, the 
scoping process, and the supplement to the environmental impact 
statement.

[49 FR 9381, Mar. 12, 1984, as amended at 72 FR 49510, Aug. 28, 2007]

                                 scoping



Sec. 51.28  Scoping--participants.

    (a) The appropriate NRC staff director shall invite the following 
persons to participate in the scoping process:
    (1) The applicant or the petitioner for rulemaking;
    (2) Any person who has petitioned for leave to intervene in the 
proceeding or who has been admitted as a party to the proceeding;
    (3) Any other Federal agency which has jurisdiction by law or 
special expertise with respect to any environmental impact involved or 
which is authorized to develop and enforce relevant environmental 
standards;
    (4) Affected State and local agencies, including those authorized to 
develop and enforce relevant environmental standards;
    (5) Any affected Indian Tribe; and
    (6) Any person who has requested an opportunity to participate in 
the scoping process.
    (b) The appropriate NRC staff director may also invite any other 
appropriate person to participate in the scoping process.
    (c) Participation in the scoping process for an environmental impact 
statement does not entitle the participant to become a party to the 
proceeding to which the environmental impact statement relates. 
Participation in an adjudicatory proceeding is governed by the 
procedures in Sec. Sec. 2.309 and 2.315 of this chapter. Participation 
in a rulemaking proceeding in which the Commission has decided to have a 
hearing is governed by the provisions in the notice of hearing.

[49 FR 9381, Mar. 12, 1984, as amended at 74 FR 62682, Dec. 1, 2009]



Sec. 51.29  Scoping-environmental impact statement and supplement
to environmental impact statement.

    (a) The scoping process for an environmental impact statement shall 
begin as soon as practicable after publication of the notice of intent 
as provided in Sec. 51.116, and shall be used to:
    (1) Define the proposed action which is to be the subject of the 
statement or supplement. For environmental impact statements other than 
a supplement to an early site permit final environmental impact 
statement prepared for a combined license application, the provisions of 
40 CFR 1502.4 will be used for this purpose. For a supplement to an 
early site permit final environmental impact statement prepared for a 
combined license application, the proposed action shall be as set forth 
in the relevant provisions of Sec. 51.92(e).
    (2) Determine the scope of the statement and identify the 
significant issues to be analyzed in depth.
    (3) Identify and eliminate from detailed study issues which are 
peripheral or are not significant or which have been covered by prior 
environmental review. Discussion of these issues in the statement will 
be limited to a brief presentation of why they are peripheral or will 
not have a significant effect on the quality of the human environment or 
a reference to their coverage elsewhere.
    (4) Identify any environmental assessments and other environmental 
impact statements which are being or will be prepared that are related 
to but are not part of the scope of the statement under consideration.
    (5) Identify other environmental review and consultation 
requirements related to the proposed action so that other required 
analyses and studies may be prepared concurrently and integrated with 
the environmental impact statement.
    (6) Indicate the relationship between the timing of the preparation 
of environmental analyses and the Commission's tentative planning and 
decision-making schedule.
    (7) Identify any cooperating agencies, and as appropriate, allocate 
assignments for preparation and schedules for completion of the 
statement to the NRC and any cooperating agencies.

[[Page 19]]

    (8) Describe the means by which the environmental impact statement 
will be prepared, including any contractor assistance to be used.
    (b) At the conclusion of the scoping process, the appropriate NRC 
staff director will prepare a concise summary of the determinations and 
conclusions reached, including the significant issues identified, and 
will send a copy of the summary to each participant in the scoping 
process.
    (c) At any time prior to issuance of the draft environmental impact 
statement, the appropriate NRC staff director may revise the 
determinations made under paragraph (b) of this section, as appropriate, 
if substantial changes are made in the proposed action, or if 
significant new circumstances or information arise which bear on the 
proposed action or its impacts.

[49 FR 9381, Mar. 12, 1984, as amended at 72 FR 49510, Aug. 28, 2007]

                        environmental assessment



Sec. 51.30  Environmental assessment.

    (a) An environmental assessment for proposed actions, other than 
those for a standard design certification under 10 CFR part 52 or a 
manufacturing license under part 52, shall identify the proposed action 
and include:
    (1) A brief discussion of:
    (i) The need for the proposed action;
    (ii) Alternatives as required by section 102(2)(E) of NEPA;
    (iii) The environmental impacts of the proposed action and 
alternatives as appropriate; and
    (2) A list of agencies and persons consulted, and identification of 
sources used.
    (b) As stated in Sec. 51.23, the generic impact determinations 
regarding the continued storage of spent fuel in NUREG-2157 shall be 
considered in the environmental assessment, if the impacts of continued 
storage of spent fuel are relevant to the proposed action.
    (c) An environmental assessment for a proposed action regarding a 
monitored retrievable storage installation (MRS) will not address the 
need for the MRS or any alternative to the design criteria for an MRS 
set forth in section 141(b)(1) of the Nuclear Waste Policy Act of 1982 
(96 Stat. 2242, 42 U.S.C. 10161(b)(1)).
    (d) An environmental assessment for a standard design certification 
under subpart B of part 52 of this chapter must identify the proposed 
action, and will be limited to the consideration of the costs and 
benefits of severe accident mitigation design alternatives and the bases 
for not incorporating severe accident mitigation design alternatives in 
the design certification. An environmental assessment for an amendment 
to a design certification will be limited to the consideration of 
whether the design change which is the subject of the proposed amendment 
renders a severe accident mitigation design alternative previously 
rejected in the earlier environmental assessment to become cost 
beneficial, or results in the identification of new severe accident 
mitigation design alternatives, in which case the costs and benefits of 
new severe accident mitigation design alternatives and the bases for not 
incorporating new severe accident mitigation design alternatives in the 
design certification must be addressed.
    (e) An environmental assessment for a manufacturing license under 
subpart F of part 52 of this chapter must identify the proposed action, 
and will be limited to the consideration of the costs and benefits of 
severe accident mitigation design alternatives and the bases for not 
incorporating severe accident mitigation design alternatives in the 
manufacturing license. An environmental assessment for an amendment to a 
manufacturing license will be limited to consideration of whether the 
design change which is the subject of the proposed amendment either 
renders a severe accident mitigation design alternative previously 
rejected in an environmental assessment to become cost beneficial, or 
results in the identification of new severe accident mitigation design 
alternatives, in which case the costs and benefits of new severe 
accident mitigation design alternatives and the bases for not 
incorporating new severe accident mitigation design alternatives in the 
manufacturing license must be addressed. In either case, the 
environmental assessment will not

[[Page 20]]

address the environmental impacts associated with manufacturing the 
reactor under the manufacturing license.

[49 FR 9381, Mar. 12, 1984, as amended at 49 FR 34694, Aug. 31, 1984; 53 
FR 31681, Aug. 19, 1988; 72 FR 49510, Aug. 28, 2007; 79 FR 56260, Sept. 
19, 2014]



Sec. 51.31  Determinations based on environmental assessment.

    (a) General. Upon completion of an environmental assessment for 
proposed actions other than those involving a standard design 
certification or a manufacturing license under part 52 of this chapter, 
the appropriate NRC staff director will determine whether to prepare an 
environmental impact statement or a finding of no significant impact on 
the proposed action. As provided in Sec. 51.33, a determination to 
prepare a draft finding of no significant impact may be made.
    (b) Standard design certification. (1) For actions involving the 
issuance or amendment of a standard design certification, the Commission 
shall prepare a draft environmental assessment for public comment as 
part of the proposed rule. The proposed rule must state that:
    (i) The Commission has determined in Sec. 51.32 that there is no 
significant environmental impact associated with the issuance of the 
standard design certification or its amendment, as applicable; and
    (ii) Comments on the environmental assessment will be limited to the 
consideration of SAMDAs as required by Sec. 51.30(d).
    (2) The Commission will prepare a final environmental assessment 
following the close of the public comment period for the proposed 
standard design certification.
    (c) Manufacturing license. (1) Upon completion of the environmental 
assessment for actions involving issuance or amendment of a 
manufacturing license (manufacturing license environmental assessment), 
the appropriate NRC staff director will determine the costs and benefits 
of severe accident mitigation design alternatives and the bases for not 
incorporating severe accident mitigation design alternatives in the 
design of the reactor to be manufactured under the manufacturing 
license. The NRC staff director may determine to prepare a draft 
environmental assessment.
    (2) The manufacturing license environmental assessment must state 
that:
    (i) The Commission has determined in Sec. 51.32 that there is no 
significant environmental impact associated with the issuance of a 
manufacturing license or an amendment to a manufacturing license, as 
applicable;
    (ii) The environmental assessment will not address the environmental 
impacts associated with manufacturing the reactor under the 
manufacturing license; and
    (iii) Comments on the environmental assessment will be limited to 
the consideration of severe accident mitigation design alternatives as 
required by Sec. 51.30(e).
    (3) If the NRC staff director makes a determination to prepare and 
issue a draft environmental assessment for public review and comment 
before making a final determination on the manufacturing license 
application, the assessment will be marked, ``Draft.'' The NRC notice of 
availability on the draft environmental assessment will include a 
request for comments which specifies where comments should be submitted 
and when the comment period expires. The notice will state that copies 
of the environmental assessment and any related environmental documents 
are available for public inspection and where inspections can be made. A 
copy of the final environmental assessment will be sent to the U.S. 
Environmental Protection Agency, the applicant, any party to a 
proceeding, each commenter, and any other Federal, State, and local 
agencies, and Indian Tribes, State, regional, and metropolitan 
clearinghouses expressing an interest in the action. Additional copies 
will be made available in accordance with Sec. 51.123.
    (4) When a hearing is held under the regulations in part 2 of this 
chapter on the proposed issuance of the manufacturing license or 
amendment, the NRC staff director will prepare a final environmental 
assessment which may be subject to modification as a result of review 
and decision as appropriate to the nature and scope of the proceeding.

[[Page 21]]

    (5) Only a party admitted into the proceeding with respect to a 
contention on the environmental assessment, or an entity participating 
in the proceeding pursuant to Sec. 2.315(c) of this chapter, may take a 
position and offer evidence on the matters within the scope of the 
environmental assessment.

[72 FR 49510, Aug. 28, 2007]

                    finding of no significant impact



Sec. 51.32  Finding of no significant impact.

    (a) A finding of no significant impact will:
    (1) Identify the proposed action;
    (2) State that the Commission has determined not to prepare an 
environmental impact statement for the proposed action;
    (3) Briefly present the reasons why the proposed action will not 
have a significant effect on the quality of the human environment;
    (4) Include the environmental assessment or a summary of the 
environmental assessment. If the assessment is included, the finding 
need not repeat any of the discussion in the assessment but may 
incorporate it by reference;
    (5) Note any other related environmental documents; and
    (6) State that the finding and any related environmental documents 
are available for public inspection and where the documents may be 
inspected.
    (b) The Commission finds that there is no significant environmental 
impact associated with the issuance of:
    (1) A standard design certification under subpart B of part 52 of 
this chapter;
    (2) An amendment to a design certification;
    (3) A manufacturing license under subpart F of part 52 of this 
chapter; or
    (4) An amendment to a manufacturing license.

[49 FR 9381, Mar. 12, 1984, as amended at 72 FR 49511, Aug. 28, 2007]



Sec. 51.33  Draft finding of no significant impact; distribution.

    (a) As provided in paragraph (b) of this section, the appropriate 
NRC staff director may make a determination to prepare and issue a draft 
finding of no significant impact for public review and comment before 
making a final determination whether to prepare an environmental impact 
statement or a final finding of no significant impact on the proposed 
action.
    (b) Circumstances in which a draft finding of no significant impact 
may be prepared will ordinarily include the following:
    (1) A finding of no significant impact appears warranted for the 
proposed action but the proposed action is (i) closely similar to one 
which normally requires the preparation of an environmental impact 
statement, or (ii) without precedent; and
    (2) The appropriate NRC staff director determines that preparation 
of a draft finding of no significant impact will further the purposes of 
NEPA.
    (c) A draft finding of no significant impact will (1) be marked 
``Draft'', (2) contain the information specified in Sec. 51.32, (3) be 
accompanied by or include a request for comments on the proposed action 
and on the draft finding within thirty (30) days, or such longer period 
as may be specified in the notice of the draft finding, and (4) be 
published in the Federal Register as required by Sec. Sec. 51.35 and 
51.119.
    (d) A draft finding will be distributed as provided in Sec. 
51.74(a). Additional copies will be made available in accordance with 
Sec. 51.123.
    (e) When a draft finding of no significant impact is issued for a 
proposed action, a final determination to prepare an environmental 
impact statement or a final finding of no significant impact for that 
action shall not be made until the last day of the public comment period 
has expired.



Sec. 51.34  Preparation of finding of no significant impact.

    (a) Except as provided in paragraph (b) of this section, the finding 
of no significant impact will be prepared by the NRC staff director 
authorized to take the action.
    (b) When a hearing is held on the proposed action under the 
regulations in subpart G of part 2 of this chapter or when the action 
can only be taken by the Commissioners acting as a collegial body, the 
appropriate NRC staff director will prepare a proposed finding of no 
significant impact, which may be

[[Page 22]]

subject to modification as a result of review and decision as 
appropriate to the nature and scope of the proceeding. In such cases, 
the presiding officer, or the Commission acting as a collegial body, as 
appropriate, will issue the final finding of no significant impact.

[49 FR 9381, Mar. 12, 1984, as amended at 77 FR 46600, Aug. 3, 2012; 79 
FR 66604, Nov. 10, 2014]



Sec. 51.35  Requirement to publish finding of no significant impact;
limitation on Commission action.

    (a) Whenever the Commission makes a draft or final finding of no 
significant impact on a proposed action, the finding will be published 
in the Federal Register as provided in Sec. 51.119.
    (b) Except as provided in Sec. 51.13, the Commission shall not take 
the proposed action until after the final finding has been published in 
the Federal Register.

   Environmental Reports and Information--Requirements Applicable to 
                Applicants and Petitioners for Rulemaking

                                 general



Sec. 51.40  Consultation with NRC staff.

    (a) A prospective applicant or petitioner for rulemaking is 
encouraged to confer with NRC staff as early as possible in its planning 
process before submitting environmental information or filing an 
environmental report.
    (b) Requests for guidance or information on environmental matters 
may include inquiries relating to:
    (1) Applicable NRC rules and regulations;
    (2) Format, content and procedures for filing environmental reports 
and other environmental information, including the type and quantity of 
environmental information likely to be needed to address issues and 
concerns identified in the scoping process described in Sec. 51.29 in a 
manner appropriate to their relative significance;
    (3) Availability of relevant environmental studies and environmental 
information;
    (4) Need for, appropriate level and scope of any environmental 
studies or information which the Commission may require to be submitted 
in connection with an application or petition for rulemaking;
    (5) Public meetings with NRC staff.
    (c) Questions concerning environmental matters should be addressed 
to the following NRC staff offices as appropriate:
    (1) Utilization facilities: ATTN: Document Control Desk, Director, 
Office of Nuclear Reactor Regulation or Director, Office of New 
Reactors, as appropriate, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, telephone (301) 415-1270, e-mail 
[email protected].
    (2) Production facilities: ATTN: Document Control Desk, Director, 
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
7800, e-mail [email protected].
    (3) Materials licenses: ATTN: Document Control Desk, Director, 
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
7800, e-mail [email protected].
    (4) Rulemaking: ATTN: Chief, Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone (800) 368-5642, e-mail [email protected].
    (5) General Environmental Matters: Executive Director for 
Operations, U.S. Nuclear Regulatory Commission, Washington, DC 20555, 
Telephone: (301) 415-1700.

[49 FR 9381, Mar. 12, 1984, as amended at 53 FR 13399, Apr. 25, 1988; 60 
FR 24552, May 9, 1995; 68 FR 58810, Oct. 10, 2003; 73 FR 5724, Jan. 31, 
2008]



Sec. 51.41  Requirement to submit environmental information.

    The Commission may require an applicant for a permit, license, or 
other form of permission, or amendment to or renewal of a permit, 
license or other form of permission, or a petitioner for rulemaking to 
submit such information to the Commission as may be useful in aiding the 
Commission in complying with section 102(2) of NEPA. The

[[Page 23]]

Commission will independently evaluate and be responsible for the 
reliability of any information which it uses.

               environmental reports--general requirements



Sec. 51.45  Environmental report.

    (a) General. As required by Sec. Sec. 51.50, 51.53, 51.54, 51.55, 
51.60, 51.61, 51.62, or 51.68, as appropriate, each applicant or 
petitioner for rulemaking shall submit with its application or petition 
for rulemaking one signed original of a separate document entitled 
``Applicant's'' or ``Petitioner's Environmental Report,'' as 
appropriate. An applicant or petitioner for rulemaking may submit a 
supplement to an environmental report at any time.
    (b) Environmental considerations. The environmental report shall 
contain a description of the proposed action, a statement of its 
purposes, a description of the environment affected, and discuss the 
following considerations:
    (1) The impact of the proposed action on the environment. Impacts 
shall be discussed in proportion to their significance;
    (2) Any adverse environmental effects which cannot be avoided should 
the proposal be implemented;
    (3) Alternatives to the proposed action. The discussion of 
alternatives shall be sufficiently complete to aid the Commission in 
developing and exploring, pursuant to section 102(2)(E) of NEPA, 
``appropriate alternatives to recommended courses of action in any 
proposal which involves unresolved conflicts concerning alternative uses 
of available resources.'' To the extent practicable, the environmental 
impacts of the proposal and the alternatives should be presented in 
comparative form;
    (4) The relationship between local short-term uses of man's 
environment and the maintenance and enhancement of long-term 
productivity; and
    (5) Any irreversible and irretrievable commitments of resources 
which would be involved in the proposed action should it be implemented.
    (c) Analysis. The environmental report must include an analysis that 
considers and balances the environmental effects of the proposed action, 
the environmental impacts of alternatives to the proposed action, and 
alternatives available for reducing or avoiding adverse environmental 
effects. An environmental report required for materials licenses under 
Sec. 51.60 must also include a description of those site preparation 
activities excluded from the definition of construction under Sec. 51.4 
which have been or will be undertaken at the proposed site (i.e., those 
activities listed in paragraphs (2)(i) and (2)(ii) in the definition of 
construction contained in Sec. 51.4); a description of the impacts of 
such excluded site preparation activities; and an analysis of the 
cumulative impacts of the proposed action when added to the impacts of 
such excluded site preparation activities on the human environment. An 
environmental report prepared at the early site permit stage under Sec. 
51.50(b), limited work authorization stage under Sec. 51.49, 
construction permit stage under Sec. 51.50(a), or combined license 
stage under Sec. 51.50(c) must include a description of impacts of the 
preconstruction activities performed by the applicant at the proposed 
site (i.e., those activities listed in paragraph (1)(ii) in the 
definition of ``construction'' contained in Sec. 51.4), necessary to 
support the construction and operation of the facility which is the 
subject of the early site permit, limited work authorization, 
construction permit, or combined license application. The environmental 
report must also contain an analysis of the cumulative impacts of the 
activities to be authorized by the limited work authorization, 
construction permit, or combined license in light of the preconstruction 
impacts described in the environmental report. Except for an 
environmental report prepared at the early site permit stage, or an 
environmental report prepared at the license renewal stage under Sec. 
51.53(c), the analysis in the environmental report should also include 
consideration of the economic, technical, and other benefits and costs 
of the proposed action and its alternatives. Environmental reports 
prepared at the license renewal stage under Sec. 51.53(c) need not 
discuss the economic or technical benefits and costs of either the 
proposed action or alternatives except if these benefits

[[Page 24]]

and costs are either essential for a determination regarding the 
inclusion of an alternative in the range of alternatives considered or 
relevant to mitigation. In addition, environmental reports prepared 
under Sec. 51.53(c) need not discuss issues not related to the 
environmental effects of the proposed action and its alternatives. The 
analyses for environmental reports shall, to the fullest extent 
practicable, quantify the various factors considered. To the extent that 
there are important qualitative considerations or factors that cannot be 
quantified, those considerations or factors shall be discussed in 
qualitative terms. The environmental report should contain sufficient 
data to aid the Commission in its development of an independent 
analysis.
    (d) Status of compliance. The environmental report shall list all 
Federal permits, licenses, approvals and other entitlements which must 
be obtained in connection with the proposed action and shall describe 
the status of compliance with these requirements. The environmental 
report shall also include a discussion of the status of compliance with 
applicable environmental quality standards and requirements including, 
but not limited to, applicable zoning and land-use regulations, and 
thermal and other water pollution limitations or requirements which have 
been imposed by Federal, State, regional, and local agencies having 
responsibility for environmental protection. The discussion of 
alternatives in the report shall include a discussion of whether the 
alternatives will comply with such applicable environmental quality 
standards and requirements.
    (e) Adverse information. The information submitted pursuant to 
paragraphs (b) through (d) of this section should not be confined to 
information supporting the proposed action but should also include 
adverse information.

[49 FR 9381, Mar. 12, 1984, as amended at 61 FR 28486, June 5, 1996; 61 
FR 66542, Dec. 18, 1996; 68 FR 58810, Oct. 10, 2003; 72 FR 49511, Aug. 
28, 2007; 72 FR 57443, Oct. 9, 2007; 73 FR 22787, Apr. 28, 2008; 76 FR 
56965, Sept. 15, 2011]

      environmental reports--production and utilization facilities



Sec. 51.49  Environmental report--limited work authorization.

    (a) Limited work authorization submitted as part of complete 
construction permit or combined license application. Each applicant for 
a construction permit or combined license applying for a limited work 
authorization under Sec. 50.10(d) of this chapter in a complete 
application under 10 CFR 2.101(a)(1) through (a)(4), shall submit with 
its application a separate document, entitled, ``Applicant's 
Environmental Report--Limited Work Authorization Stage,'' which is in 
addition to the environmental report required by Sec. 51.50 of this 
part. Each environmental report must also contain the following 
information:
    (1) A description of the activities proposed to be conducted under 
the limited work authorization;
    (2) A statement of the need for the activities; and
    (3) A description of the environmental impacts that may reasonably 
be expected to result from the activities, the mitigation measures that 
the applicant proposes to implement to achieve the level of 
environmental impacts described, and a discussion of the reasons for 
rejecting mitigation measures that could be employed by the applicant to 
further reduce environmental impacts.
    (b) Phased application for limited work authorization and 
construction permit or combined license. If the construction permit or 
combined license application is filed in accordance with Sec. 
2.101(a)(9) of this chapter, then the environmental report for part one 
of the application may be limited to a discussion of the activities 
proposed to be conducted under the limited work authorization. If the 
scope of the environmental report for part one is so limited, then part 
two of the application must include the information required by Sec. 
51.50, as applicable.
    (c) Limited work authorization submitted as part of an early site 
permit application. Each applicant for an early site permit under 
subpart A of part 52 of this chapter requesting a limited work 
authorization shall submit with

[[Page 25]]

its application the environmental report required by Sec. 51.50(b). 
Each environmental report must contain the following information:
    (1) A description of the activities proposed to be conducted under 
the limited work authorization;
    (2) A statement of the need for the activities; and
    (3) A description of the environmental impacts that may reasonably 
be expected to result from the activities, the mitigation measures that 
the applicant proposes to implement to achieve the level of 
environmental impacts described, and a discussion of the reasons for 
rejecting mitigation measures that could be employed by the applicant to 
further reduce environmental impacts.
    (d) Limited work authorization request submitted by early site 
permit holder. Each holder of an early site permit requesting a limited 
work authorization shall submit with its application a document 
entitled, ``Applicant's Environmental Report--Limited Work Authorization 
under Early Site Permit,'' containing the following information:
    (1) A description of the activities proposed to be conducted under 
the limited work authorization;
    (2) A statement of the need for the activities;
    (3) A description of the environmental impacts that may reasonably 
be expected to result from the activities, the mitigation measures that 
the applicant proposes to implement to achieve the level of 
environmental impacts described, and a discussion of the reasons for 
rejecting mitigation measures that could be employed by the applicant to 
further reduce environmental impacts; and
    (4) Any new and significant information for issues related to the 
impacts of construction of the facility that were resolved in the early 
site permit proceeding with respect to the environmental impacts of the 
activities to be conducted under the limited work authorization.
    (5) A description of the process used to identify new and 
significant information regarding NRC's conclusions in the early site 
permit environmental impact statement. The process must be a reasonable 
methodology for identifying this new and significant information.
    (e) Limited work authorization for a site where an environmental 
impact statement was prepared, but the facility construction was not 
completed. If the limited work authorization is for activities to be 
conducted at a site for which the Commission has previously prepared an 
environmental impact statement for the construction and operation of a 
nuclear power plant, and a construction permit was issued but 
construction of the plant was never completed, then the applicant's 
environmental report may incorporate by reference the earlier 
environmental impact statement. In the event of such referencing, the 
environmental report must identify:
    (1) Any new and significant information material to issues related 
to the impacts of construction of the facility that were resolved in the 
construction permit proceeding for the matters required to be addressed 
in paragraph (a) of this section; and
    (2) A description of the process used to identify new and 
significant information regarding the NRC's conclusions in the 
construction permit environmental impact statement. The process must use 
a reasonable methodology for identifying this new and significant 
information.
    (f) Environmental report. An environmental report submitted in 
accordance with this section must separately evaluate the environmental 
impacts and proposed alternatives attributable to the activities 
proposed to be conducted under the limited work authorization. At the 
option of the applicant, the ``Applicant's Environmental Report--Limited 
Work Authorization Stage,'' may contain the information required to be 
submitted in the environmental report required under Sec. 51.50, which 
addresses the impacts of construction and operation for the proposed 
facility (including the environmental impacts attributable to the 
limited work authorization), and discusses the overall costs and 
benefits balancing for the proposed action.

[72 FR 57444, Oct. 9, 2007]

[[Page 26]]



Sec. 51.50  Environmental report--construction permit, early site
permit, or combined license stage.

    (a) Construction permit stage. Each applicant for a permit to 
construct a production or utilization facility covered by Sec. 51.20 
shall submit with its application a separate document, entitled 
``Applicant's Environmental Report--Construction Permit Stage,'' which 
shall contain the information specified in Sec. Sec. 51.45, 51.51, and 
51.52. Each environmental report shall identify procedures for reporting 
and keeping records of environmental data, and any conditions and 
monitoring requirements for protecting the non-aquatic environment, 
proposed for possible inclusion in the license as environmental 
conditions in accordance with Sec. 50.36b of this chapter. As stated in 
Sec. 51.23, no discussion of the environmental impacts of the continued 
storage of spent fuel is required in this report.
    (b) Early site permit stage. Each applicant for an early site permit 
shall submit with its application a separate document, entitled 
``Applicant's Environmental Report--Early Site Permit Stage,'' which 
shall contain the information specified in Sec. Sec. 51.45, 51.51, and 
51.52, as modified in this paragraph.
    (1) The environmental report must include an evaluation of 
alternative sites to determine whether there is any obviously superior 
alternative to the site proposed.
    (2) The environmental report may address one or more of the 
environmental effects of construction and operation of a reactor, or 
reactors, which have design characteristics that fall within the site 
characteristics and design parameters for the early site permit 
application, provided however, that the environmental report must 
address all environmental effects of construction and operation 
necessary to determine whether there is any obviously superior 
alternative to the site proposed. The environmental report need not 
include an assessment of the economic, technical, or other benefits (for 
example, need for power) and costs of the proposed action or an 
evaluation of alternative energy sources. As stated in Sec. 51.23, no 
discussion of the environmental impacts of the continued storage of 
spent fuel is required in this report.
    (3) For other than light-water-cooled nuclear power reactors, the 
environmental report must contain the basis for evaluating the 
contribution of the environmental effects of fuel cycle activities for 
the nuclear power reactor.
    (4) Each environmental report must identify the procedures for 
reporting and keeping records of environmental data, and any conditions 
and monitoring requirements for protecting the non-aquatic environment, 
proposed for possible inclusion in the license as environmental 
conditions in accordance with Sec. 50.36b of this chapter.
    (c) Combined license stage. Each applicant for a combined license 
shall submit with its application a separate document, entitled 
``Applicant's Environmental Report--Combined License Stage.'' Each 
environmental report shall contain the information specified in 
Sec. Sec. 51.45, 51.51, and 51.52, as modified in this paragraph. For 
other than light-water-cooled nuclear power reactors, the environmental 
report shall contain the basis for evaluating the contribution of the 
environmental effects of fuel cycle activities for the nuclear power 
reactor. Each environmental report shall identify procedures for 
reporting and keeping records of environmental data, and any conditions 
and monitoring requirements for protecting the non-aquatic environment, 
proposed for possible inclusion in the license as environmental 
conditions in accordance with Sec. 50.36b of this chapter. The combined 
license environmental report may reference information contained in a 
final environmental document previously prepared by the NRC staff. As 
stated in Sec. 51.23, no discussion of the environmental impacts of the 
continued storage of spent fuel is required in this report.
    (1) Application referencing an early site permit. If the combined 
license application references an early site permit, then the 
``Applicant's Environmental Report--Combined License Stage'' need not 
contain information or analyses submitted to the Commission in 
``Applicant's Environmental Report--Early Site Permit Stage,'' or 
resolved in the Commission's early site permit environmental impact 
statement, but must

[[Page 27]]

contain, in addition to the environmental information and analyses 
otherwise required:
    (i) Information to demonstrate that the design of the facility falls 
within the site characteristics and design parameters specified in the 
early site permit;
    (ii) Information to resolve any significant environmental issue that 
was not resolved in the early site permit proceeding;
    (iii) Any new and significant information for issues related to the 
impacts of construction and operation of the facility that were resolved 
in the early site permit proceeding;
    (iv) A description of the process used to identify new and 
significant information regarding the NRC's conclusions in the early 
site permit environmental impact statement. The process must use a 
reasonable methodology for identifying such new and significant 
information; and
    (v) A demonstration that all environmental terms and conditions that 
have been included in the early site permit will be satisfied by the 
date of issuance of the combined license. Any terms or conditions of the 
early site permit that could not be met by the time of issuance of the 
combined license, must be set forth as terms or conditions of the 
combined license.
    (2) Application referencing standard design certification. If the 
combined license references a standard design certification, then the 
combined license environmental report may incorporate by reference the 
environmental assessment previously prepared by the NRC for the 
referenced design certification. If the design certification 
environmental assessment is referenced, then the combined license 
environmental report must contain information to demonstrate that the 
site characteristics for the combined license site fall within the site 
parameters in the design certification environmental assessment.
    (3) Application referencing a manufactured reactor. If the combined 
license application proposes to use a manufactured reactor, then the 
combined license environmental report may incorporate by reference the 
environmental assessment previously prepared by the NRC for the 
underlying manufacturing license. If the manufacturing license 
environmental assessment is referenced, then the combined license 
environmental report must contain information to demonstrate that the 
site characteristics for the combined license site fall within the site 
parameters in the manufacturing license environmental assessment. The 
environmental report need not address the environmental impacts 
associated with manufacturing the reactor under the manufacturing 
license.

[72 FR 49511, Aug. 28, 2007, as amended at 79 FR 56260, Sept. 19, 2014]



Sec. 51.51  Uranium fuel cycle environmental data--Table S-3.

    (a) Under Sec. 51.50, every environmental report prepared for the 
construction permit stage or early site permit stage or combined license 
stage of a light-water-cooled nuclear power reactor, and submitted on or 
after September 4, 1979, shall take Table S-3, Table of Uranium Fuel 
Cycle Environmental Data, as the basis for evaluating the contribution 
of the environmental effects of uranium mining and milling, the 
production of uranium hexafluoride, isotopic enrichment, fuel 
fabrication, reprocessing of irradiated fuel, transportation of 
radioactive materials and management of low-level wastes and high-level 
wastes related to uranium fuel cycle activities to the environmental 
costs of licensing the nuclear power reactor. Table S-3 shall be 
included in the environmental report and may be supplemented by a 
discussion of the environmental significance of the data set forth in 
the table as weighed in the analysis for the proposed facility.
    (b) Table S-3.

[[Page 28]]



      Table S-3--Table of Uranium Fuel Cycle Environmental Data \1\
     [Normalized to model LWR annual fuel requirement [WASH-1248] or
                  reference reactor year [NUREG-0116]]
                  [See footnotes at end of this table]
------------------------------------------------------------------------
                                                    Maximum effect per
                                                 annual fuel requirement
    Environmental considerations        Total      or reference reactor
                                                 year of model 1,000 MWe
                                                           LWR
------------------------------------------------------------------------
        Natural Resource Use
Land (acres):
  Temporarily committed \2\.........        100
    Undisturbed area................         79
    Disturbed area..................         22  Equivalent to a 110 MWe
                                                  coal-fired power
                                                  plant.
  Permanently committed.............         13
  Overburden moved (millions of MT).        2.8  Equivalent to 95 MWe
                                                  coal-fired power
                                                  plant.
                                     -----------
Water (millions of gallons):
  Discharged to air.................        160   = 2 percent of model
                                                  1,000 MWe LWR with
                                                  cooling tower.
  Discharged to water bodies........     11,090
  Discharged to ground..............        127
                                     -----------
      Total.........................     11,377  <4 percent of model
                                                  1,000 MWe LWR with
                                                  once-through cooling.
                                     -----------
Fossil fuel:
  Electrical energy (thousands of MW-       323  <5 percent of model
   hour).                                         1,000 MWe LWR output.
  Equivalent coal (thousands of MT).        118  Equivalent to the
                                                  consumption of a 45
                                                  MWe coal-fired power
                                                  plant.
  Natural gas (millions of scf).....        135  <0.4 percent of model
                                                  1,000 MWe energy
                                                  output.
 
      Effluents--Chemical (MT)
 
Gases (including entrainment): \3\
  SOX...............................      4,400
  NOX\4\............................      1,190  Equivalent to emissions
                                                  from 45 MWe coal-fired
                                                  plant for a year.
  Hydrocarbons......................         14
  CO................................       29.6
  Particulates......................      1,154
Other gases:
  F.................................        .67  Principally from UF6
                                                  production,
                                                  enrichment, and
                                                  reprocessing.
                                                  Concentration within
                                                  range of state
                                                  standards--below level
                                                  that has effects on
                                                  human health.
  HCl...............................       .014
 
Liquids:
SO -4...............................        9.9  From enrichment, fuel
NO -3...............................       25.8   fabrication, and
Fluoride............................       12.9   reprocessing steps.
Ca \ + \............................        5.4   Components that
C1 -................................        8.5   constitute a potential
Na \ + \............................       12.1   for adverse
NH 3................................       10.0   environmental effect
Fe..................................         .4   are present in dilute
                                                  concentrations and
                                                  receive additional
                                                  dilution by receiving
                                                  bodies of water to
                                                  levels below
                                                  permissible standards.
                                                  The constituents that
                                                  require dilution and
                                                  the flow of dilution
                                                  water are: NH 3--600
                                                  cfs., NO 3--20 cfs.,
                                                  Fluoride--70 cfs.
Tailings solutions (thousands of MT)        240  From mills only--no
                                                  significant effluents
                                                  to environment.
Solids..............................     91,000  Principally from mills--
                                                  no significant
                                                  effluents to
                                                  environment.
  Effluents--Radiological (curies)
 
Gases (including entrainment):
  Rn-222............................  .........  Presently under
                                                  reconsideration by the
                                                  Commission.
  Ra-226............................        .02
  Th-230............................        .02
  Uranium...........................       .034
  Tritium (thousands)...............       18.1
  C-14..............................         24
  Kr-85 (thousands).................        400
  Ru-106............................        .14  Principally from fuel
                                                  reprocessing plants.
  I-129.............................        1.3
  I-131.............................        .83
  Tc-99.............................  .........  Presently under
                                                  consideration by the
                                                  Commission.
  Fission products and transuranics.       .203
 
Liquids:
  Uranium and daughters.............        2.1  Principally from
                                                  milling--included
                                                  tailings liquor and
                                                  returned to ground--no
                                                  effluents; therefore,
                                                  no effect on
                                                  environment.
  Ra-226............................      .0034  From UF6 production.
  Th-230............................      .0015

[[Page 29]]

 
  Th-234............................        .01  From fuel fabrication
                                                  plants--concentration
                                                  10 percent of 10 CFR
                                                  20 for total
                                                  processing 26 annual
                                                  fuel requirements for
                                                  model LWR.
  Fission and activation products...  5.9 x 10-
                                              6
Solids (buried on site):
  Other than high level (shallow)...     11,300  9,100 Ci comes from low
                                                  level reactor wastes
                                                  and 1,500 Ci comes
                                                  from reactor
                                                  decontamination and
                                                  decommissioning--burie
                                                  d at land burial
                                                  facilities. 600 Ci
                                                  comes from mills--
                                                  included in tailings
                                                  returned to ground.
                                                  Approximately 60 Ci
                                                  comes from conversion
                                                  and spent fuel
                                                  storage. No
                                                  significant effluent
                                                  to the environment.
  TRU and HLW (deep)................      1.1 x  Buried at Federal
                                          10\7\   Repository.
Effluents--thermal (billions of           4,063  <5 percent of model
 British thermal units).                          1,000 MWe LWR.
Transportation (person-rem):
  Exposure of workers and general           2.5
   public.
  Occupational exposure (person-rem)       22.6  From reprocessing and
                                                  waste management.
------------------------------------------------------------------------
\1\ In some cases where no entry appears it is clear from the background
  documents that the matter was addressed and that, in effect, the Table
  should be read as if a specific zero entry had been made. However,
  there are other areas that are not addressed at all in the Table.
  Table S-3 does not include health effects from the effluents described
  in the Table, or estimates of releases of Radon-222 from the uranium
  fuel cycle or estimates of Technetium-99 released from waste
  management or reprocessing activities. These issues may be the subject
  of litigation in the individual licensing proceedings.
Data supporting this table are given in the ``Environmental Survey of
  the Uranium Fuel Cycle,'' WASH-1248, April 1974; the ``Environmental
  Survey of the Reprocessing and Waste Management Portion of the LWR
  Fuel Cycle,'' NUREG-0116 (Supp.1 to WASH-1248); the ``Public Comments
  and Task Force Responses Regarding the Environmental Survey of the
  Reprocessing and Waste Management Portions of the LWR Fuel Cycle,''
  NUREG-0216 (Supp. 2 to WASH-1248); and in the record of the final
  rulemaking pertaining to Uranium Fuel Cycle Impacts from Spent Fuel
  Reprocessing and Radioactive Waste Management, Docket RM-50-3. The
  contributions from reprocessing, waste management and transportation
  of wastes are maximized for either of the two fuel cycles (uranium
  only and no recycle). The contribution from transportation excludes
  transportation of cold fuel to a reactor and of irradiated fuel and
  radioactive wastes from a reactor which are considered in Table S-4 of
  Sec. 51.20(g). The contributions from the other steps of the fuel
  cycle are given in columns A-E of Table S-3A of WASH-1248.
\2\ The contributions to temporarily committed land from reprocessing
  are not prorated over 30 years, since the complete temporary impact
  accrues regardless of whether the plant services one reactor for one
  year or 57 reactors for 30 years.
\3\ Estimated effluents based upon combustion of equivalent coal for
  power generation.
\4\ 1.2 percent from natural gas use and process.


[49 FR 9381, Mar. 12, 1984; 49 FR 10922, Mar. 23, 1984, as amended at 67 
FR 77652, Dec. 19, 2002; 72 FR 49512, Aug. 28, 2007]



Sec. 51.52  Environmental effects of transportation of fuel and waste
--Table S-4.

    Under Sec. 51.50, every environmental report prepared for the 
construction permit stage or early site permit stage or combined license 
stage of a light-water-cooled nuclear power reactor, and submitted after 
February 4, 1975, shall contain a statement concerning transportation of 
fuel and radioactive wastes to and from the reactor. That statement 
shall indicate that the reactor and this transportation either meet all 
of the conditions in paragraph (a) of this section or all of the 
conditions of paragraph (b) of this section.
    (a)(1) The reactor has a core thermal power level not exceeding 
3,800 megawatts;
    (2) The reactor fuel is in the form of sintered uranium dioxide 
pellets having a uranium-235 enrichment not exceeding 4% by weight, and 
the pellets are encapsulated in zircaloy rods;
    (3) The average level of irradiation of the irradiated fuel from the 
reactor does not exceed 33,000 megawatt-days per metric ton, and no 
irradiated fuel assembly is shipped until at least 90 days after it is 
discharged from the reactor;
    (4) With the exception of irradiated fuel, all radioactive waste 
shipped from the reactor is packaged and in a solid form;
    (5) Unirradiated fuel is shipped to the reactor by truck; irradiated 
fuel is shipped from the reactor by truck, rail, or barge; and 
radioactive waste other than irradiated fuel is shipped from the reactor 
by truck or rail; and
    (6) The environmental impacts of transportation of fuel and waste to 
and

[[Page 30]]

from the reactor, with respect to normal conditions of transport and 
possible accidents in transport, are as set forth in Summary Table S-4 
in paragraph (c) of this section; and the values in the table represent 
the contribution of the transportation to the environmental costs of 
licensing the reactor.
    (b) For reactors not meeting the conditions of paragraph (a) of this 
section, the statement shall contain a full description and detailed 
analysis of the environmental effects of transportation of fuel and 
wastes to and from the reactor, including values for the environmental 
impact under normal conditions of transport and for the environmental 
risk from accidents in transport. The statement shall indicate that the 
values determined by the analysis represent the contribution of such 
effects to the environmental costs of licensing the reactor.
    (c)

  Summary Table S-4--Environmental Impact of Transportation of Fuel and
   Waste to and From One Light-Water-Cooled Nuclear Power Reactor \1\
                     Normal Conditions of Transport
------------------------------------------------------------------------
                                               Environmental impact
------------------------------------------------------------------------
Heat (per irradiated fuel cask in        250,000 Btu/hr.
 transit).
Weight (governed by Federal or State     73,000 lbs. per truck; 100 tons
 restrictions).                           per cask per rail car.
Traffic density:
  Truck................................  Less than 1 per day.
  Rail.................................  Less than 3 per month
------------------------------------------------------------------------


----------------------------------------------------------------------------------------------------------------
                                            Estimated
                                            number of   Range of doses to exposed    Cumulative dose to exposed
            Exposed population               persons       individuals \2\ (per        population (per reactor
                                             exposed          reactor year)                   year) \3\
----------------------------------------------------------------------------------------------------------------
Transportation workers...................         200  0.01 to 300 millirem.......  4 man-rem.
General public:
  Onlookers..............................       1,100  0.003 to 1.3 millirem......  3 man-rem.
  Along Route............................     600,000  0.0001 to 0.06 millirem....  ............................
----------------------------------------------------------------------------------------------------------------


                         Accidents in Transport
------------------------------------------------------------------------
                                                Environmental risk
------------------------------------------------------------------------
Radiological effects...................  Small \4\
Common (nonradiological) causes........  1 fatal injury in 100 reactor
                                          years; 1 nonfatal injury in 10
                                          reactor years; $475 property
                                          damage per reactor year.
------------------------------------------------------------------------
\1\ Data supporting this table are given in the Commission's
  ``Environmental Survey of Transportation of Radioactive Materials to
  and from Nuclear Power Plants,'' WASH-1238, December 1972; and Supp. 1
  of NUREG-75/038, April 1975. Both documents are available for
  inspection and copying at the Commission's Public Document Room, One
  White Flint North, 11555 Rockville Pike (first floor), Rockville,
  Maryland 20852 and may be obtained from National Technical Information
  Service, Springfield, VA 22161. The WASH-1238 is available from NTIS
  at a cost of $5.45 (microfiche, $2.25) and NUREG-75/038 is available
  at a cost of $3.25 (microfiche, $2.25).
\2\ The Federal Radiation Council has recommended that the radiation
  doses from all sources of radiation other than natural background and
  medical exposures should be limited to 5,000 millirem per year for
  individuals as a result of occupational exposure and should be limited
  to 500 millirem per year for individuals in the general population.
  The dose to individuals due to average natural background radiation is
  about 130 millirem per year.
\3\ Man-rem is an expression for the summation of whole body doses to
  individuals in a group. Thus, if each member of a population group of
  1,000 people were to receive a dose of 0.001 rem (1 millirem), or if 2
  people were to receive a dose of 0.5 rem (500 millirem) each, the
  total man-rem dose in each case would be 1 man-rem.
\4\ Athough the environmental risk of radiological effects stemming from
  transportation accidents is currently incapable of being numerically
  quantified, the risk remains small regardless of whether it is being
  appiled to a single reactor or a multireactor site.


[49 FR 9381, Mar. 12, 1984; 49 FR 10922, Mar. 23, 1984, as amended at 53 
FR 43420, Oct. 27, 1988; 72 FR 49512, Aug. 28, 2007; 79 FR 66604, Nov. 
10, 2014]



Sec. 51.53  Postconstruction environmental reports.

    (a) General. Any environmental report prepared under the provisions 
of this section may incorporate by reference any information contained 
in a prior environmental report or supplement thereto that relates to 
the production or utilization facility or site, or any information 
contained in a final environmental document previously prepared by the 
NRC staff that relates to the production or utilization facility or 
site. Documents that may be referenced include, but are not limited to,

[[Page 31]]

the final environmental impact statement; supplements to the final 
environmental impact statement, including supplements prepared at the 
license renewal stage; NRC staff-prepared final generic environmental 
impact statements; and environmental assessments and records of 
decisions prepared in connection with the construction permit, operating 
license, early site permit, combined license and any license amendment 
for that facility.
    (b) Operating license stage. Each applicant for a license to operate 
a production or utilization facility covered by Sec. 51.20 shall submit 
with its application a separate document entitled ``Supplement to 
Applicant's Environmental Report--Operating License Stage,'' which will 
update ``Applicant's Environmental Report--Construction Permit Stage.'' 
Unless otherwise required by the Commission, the applicant for an 
operating license for a nuclear power reactor shall submit this report 
only in connection with the first licensing action authorizing full-
power operation. In this report, the applicant shall discuss the same 
matters described in Sec. Sec. 51.45, 51.51, and 51.52, but only to the 
extent that they differ from those discussed or reflect new information 
in addition to that discussed in the final environmental impact 
statement prepared by the Commission in connection with the construction 
permit. No discussion of need for power, or of alternative energy 
sources, or of alternative sites for the facility, is required in this 
report. As stated in Sec. 51.23, no discussion of the environmental 
impacts of the continued storage of spent fuel is required in this 
report.
    (c) Operating license renewal stage. (1) Each applicant for renewal 
of a license to operate a nuclear power plant under part 54 of this 
chapter shall submit with its application a separate document entitled 
``Applicant's Environmental Report--Operating License Renewal Stage.''
    (2) The report must contain a description of the proposed action, 
including the applicant's plans to modify the facility or its 
administrative control procedures as described in accordance with Sec. 
54.21 of this chapter. This report must describe in detail the affected 
environment around the plant, the modifications directly affecting the 
environment or any plant effluents, and any planned refurbishment 
activities. In addition, the applicant shall discuss in this report the 
environmental impacts of alternatives and any other matters described in 
Sec. 51.45. The report is not required to include discussion of need 
for power or the economic costs and economic benefits of the proposed 
action or of alternatives to the proposed action except insofar as such 
costs and benefits are either essential for a determination regarding 
the inclusion of an alternative in the range of alternatives considered 
or relevant to mitigation. The environmental report need not discuss 
other issues not related to the environmental effects of the proposed 
action and the alternatives. As stated in Sec. 51.23, no discussion of 
the environmental impacts of the continued storage of spent fuel is 
required in this report.
    (3) For those applicants seeking an initial renewed license and 
holding an operating license, construction permit, or combined license 
as of June 30, 1995, the environmental report shall include the 
information required in paragraph (c)(2) of this section subject to the 
following conditions and considerations:
    (i) The environmental report for the operating license renewal stage 
is not required to contain analyses of the environmental impacts of the 
license renewal issues identified as Category 1 issues in appendix B to 
subpart A of this part.
    (ii) The environmental report must contain analyses of the 
environmental impacts of the proposed action, including the impacts of 
refurbishment activities, if any, associated with license renewal and 
the impacts of operation during the renewal term, for those issues 
identified as Category 2 issues in appendix B to subpart A of this part. 
The required analyses are as follows:
    (A) If the applicant's plant utilizes cooling towers or cooling 
ponds and withdraws makeup water from a river, an assessment of the 
impact of the proposed action on water availability and competing water 
demands, the flow of the river, and related impacts on stream (aquatic) 
and riparian (terrestrial) ecological communities must be

[[Page 32]]

provided. The applicant shall also provide an assessment of the impacts 
of the withdrawal of water from the river on alluvial aquifers during 
low flow.
    (B) If the applicant's plant utilizes once-through cooling or 
cooling pond heat dissipation systems, the applicant shall provide a 
copy of current Clean Water Act 316(b) determinations and, if necessary, 
a 316(a) variance in accordance with 40 CFR part 125, or equivalent 
State permits and supporting documentation. If the applicant cannot 
provide these documents, it shall assess the impact of the proposed 
action on fish and shellfish resources resulting from thermal changes 
and impingement and entrainment.
    (C) If the applicant's plant pumps more than 100 gallons (total 
onsite) of groundwater per minute, an assessment of the impact of the 
proposed action on groundwater must be provided.
    (D) If the applicant's plant is located at an inland site and 
utilizes cooling ponds, an assessment of the impact of the proposed 
action on groundwater quality must be provided.
    (E) All license renewal applicants shall assess the impact of 
refurbishment, continued operations, and other license-renewal-related 
construction activities on important plant and animal habitats. 
Additionally, the applicant shall assess the impact of the proposed 
action on threatened or endangered species in accordance with Federal 
laws protecting wildlife, including but not limited to, the Endangered 
Species Act, and essential fish habitat in accordance with the Magnuson-
Stevens Fishery Conservation and Management Act.
    (F) [Reserved]
    (G) If the applicant's plant uses a cooling pond, lake, or canal or 
discharges into a river, an assessment of the impact of the proposed 
action on public health from thermophilic organisms in the affected 
water must be provided.
    (H) If the applicant's transmission lines that were constructed for 
the specific purpose of connecting the plant to the transmission system 
do not meet the recommendations of the National Electric Safety Code for 
preventing electric shock from induced currents, an assessment of the 
impact of the proposed action on the potential shock hazard from the 
transmission lines must be provided.
    (I)-(J) [Reserved]
    (K) All applicants shall identify any potentially affected historic 
or archaeological properties and assess whether any of these properties 
will be affected by future plant operations and any planned 
refurbishment activities in accordance with the National Historic 
Preservation Act.
    (L) If the staff has not previously considered severe accident 
mitigation alternatives for the applicant's plant in an environmental 
impact statement or related supplement or in an environmental 
assessment, a consideration of alternatives to mitigate severe accidents 
must be provided.
    (M) [Reserved]
    (N) Applicants shall provide information on the general demographic 
composition of minority and low-income populations and communities (by 
race and ethnicity) residing in the immediate vicinity of the plant that 
could be affected by the renewal of the plant's operating license, 
including any planned refurbishment activities, and ongoing and future 
plant operations.
    (O) Applicants shall provide information about other past, present, 
and reasonably foreseeable future actions occurring in the vicinity of 
the nuclear plant that may result in a cumulative effect.
    (P) An applicant shall assess the impact of any documented 
inadvertent releases of radionuclides into groundwater. The applicant 
shall include in its assessment a description of any groundwater 
protection program used for the surveillance of piping and components 
containing radioactive liquids for which a pathway to groundwater may 
exist. The assessment must also include a description of any past 
inadvertent releases and the projected impact to the environment (e.g., 
aquifers, rivers, lakes, ponds, ocean) during the license renewal term.
    (iii) The report must contain a consideration of alternatives for 
reducing adverse impacts, as required by Sec. 51.45(c), for all 
Category 2 license renewal issues in appendix B to subpart A of this 
part. No such consideration is

[[Page 33]]

required for Category 1 issues in appendix B to subpart A of this part.
    (iv) The environmental report must contain any new and significant 
information regarding the environmental impacts of license renewal of 
which the applicant is aware.
    (d) Postoperating license stage. Each applicant for a license 
amendment authorizing decommissioning activities for a production or 
utilization facility either for unrestricted use or based on continuing 
use restrictions applicable to the site; and each applicant for a 
license amendment approving a license termination plan or 
decommissioning plan under Sec. 50.82 of this chapter either for 
unrestricted use or based on continuing use restrictions applicable to 
the site; and each applicant for a license or license amendment to store 
spent fuel at a nuclear power reactor after expiration of the operating 
license for the nuclear power reactor shall submit with its application 
a separate document, entitled ``Supplement to Applicant's Environmental 
Report--Post Operating License Stage,'' which will update ``Applicant's 
Environmental Report--Operating License Stage,'' as appropriate, to 
reflect any new information or significant environmental change 
associated with the applicant's proposed decommissioning activities or 
with the applicant's proposed activities with respect to the planned 
storage of spent fuel. As stated in Sec. 51.23, no discussion of the 
environmental impacts of the continued storage of spent fuel is required 
in this report. The ``Supplement to Applicant's Environmental Report--
Post Operating License Stage'' may incorporate by reference any 
information contained in ``Applicant's Environmental Report--
Construction Permit Stage.''

[61 FR 66543, Dec. 18, 1996, as amended at 64 FR 48506, Sept. 3, 1999; 
68 FR 58810, Oct. 10, 2003; 72 FR 49513, Aug. 28, 2007; 78 FR 37316, 
June 20, 2013; 79 FR 56260, Sept. 19, 2014; 79 FR 66604, Nov. 10, 2014]



Sec. 51.54  Environmental report--manufacturing license.

    (a) Each applicant for a manufacturing license under subpart F of 
part 52 of this chapter shall submit with its application a separate 
document entitled, ``Applicant's Environmental Report--Manufacturing 
License.'' The environmental report must address the costs and benefits 
of severe accident mitigation design alternatives, and the bases for not 
incorporating severe accident mitigation design alternatives into the 
design of the reactor to be manufactured. The environmental report need 
not address the environmental impacts associated with manufacturing the 
reactor under the manufacturing license, the benefits and impacts of 
utilizing the reactor in a nuclear power plant, or an evaluation of 
alternative energy sources.
    (b) Each applicant for an amendment to a manufacturing license shall 
submit with its application a separate document entitled, ``Applicant's 
Supplemental Environmental Report--Amendment to Manufacturing License.'' 
The environmental report must address whether the design change which is 
the subject of the proposed amendment either renders a severe accident 
mitigation design alternative previously rejected in an environmental 
assessment to become cost beneficial, or results in the identification 
of new severe accident mitigation design alternatives that may be 
reasonably incorporated into the design of the manufactured reactor. The 
environmental report need not address the environmental impacts 
associated with manufacturing the reactor under the manufacturing 
license.

[72 FR 49513, Aug. 28, 2007]



Sec. 51.55  Environmental report--standard design certification.

    (a) Each applicant for a standard design certification under subpart 
B of part 52 of this chapter shall submit with its application a 
separate document entitled, ``Applicant's Environmental Report--Standard 
Design Certification.'' The environmental report must address the costs 
and benefits of severe accident mitigation design alternatives, and the 
bases for not incorporating severe accident mitigation design 
alternatives in the design to be certified.
    (b) Each applicant for an amendment to a design certification shall 
submit with its application a separate document entitled, ``Applicant's 
Supplemental Environmental Report--

[[Page 34]]

Amendment to Standard Design Certification.'' The environmental report 
must address whether the design change which is the subject of the 
proposed amendment either renders a severe accident mitigation design 
alternative previously rejected in an environmental assessment to become 
cost beneficial, or results in the identification of new severe accident 
mitigation design alternatives that may be reasonably incorporated into 
the design certification.

[72 FR 49513, Aug. 28, 2007]



Sec. 51.58  Environmental report--number of copies; distribution.

    (a) Each applicant for a license or permit to site, construct, 
manufacture, or operate a production or utilization facility covered by 
Sec. Sec. 51.20(b)(1), (b)(2), (b)(3), or (b)(4), each applicant for 
renewal of an operating or combined license for a nuclear power plant, 
each applicant for a license amendment authorizing the decommissioning 
of a production or utilization facility covered by Sec. 51.20, and each 
applicant for a license or license amendment to store spent fuel at a 
nuclear power plant after expiration of the operating license or 
combined license for the nuclear power plant shall submit a copy to the 
Director of the Office of Nuclear Reactor Regulation, the Director of 
the Office of New Reactors, the Director of the Office of Nuclear 
Material Safety and Safeguards, as appropriate, of an environmental 
report or any supplement to an environmental report. These reports must 
be sent either by mail addressed: ATTN: Document Control Desk; U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand 
delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland, between the hours of 7:30 a.m. and 4:15 p.m. eastern time; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, or CD-ROM. Electronic submissions must be made in 
a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information. If the communication is on paper, the signed original must 
be sent. If a submission due date falls on a Saturday, Sunday, or 
Federal holiday, the next Federal working day becomes the official due 
date. The applicant shall maintain the capability to generate additional 
copies of the environmental report or any supplement to the 
environmental report for subsequent distribution to parties and Boards 
in the NRC proceedings; Federal, State, and local officials; and any 
affected Indian Tribes, in accordance with written instructions issued 
by the Director of the Office of New Reactors, the Director of the 
Office of Nuclear Reactor Regulation, or the Director of the Office of 
Nuclear Material Safety and Safeguards, as appropriate.
    (b) Each applicant for a license to manufacture a nuclear power 
reactor, or for an amendment to a license to manufacture, seeking 
approval of the final design of the nuclear power reactor under subpart 
F of part 52 of this chapter, shall submit to the Commission an 
environmental report or any supplement to an environmental report in the 
manner specified in Sec. 50.3 of this chapter. The applicant shall 
maintain the capability to generate additional copies of the 
environmental report or any supplement to the environmental report for 
subsequent distribution to parties and Boards in the NRC proceeding; 
Federal, State, and local officials; and any affected Indian Tribes, in 
accordance with written instructions issued by the Director of the 
Office of New Reactors or the Director of the Office of Nuclear Reactor 
Regulation.

[72 FR 49513, Aug. 28, 2007, as amended at 74 FR 62682, Dec. 1, 2009]

[[Page 35]]

                environmental reports--materials licenses



Sec. 51.60  Environmental report--materials licenses.

    (a) Each applicant for a license or other form of permission, or an 
amendment to or renewal of a license or other form of permission issued 
pursuant to parts 30, 32, 33, 34, 35, 36, 39, 40, 61, 70 and/or 72 of 
this chapter, and covered by paragraphs (b)(1) through (b)(5) of this 
section, shall submit with its application to: ATTN: Document Control 
Desk, Director, Nuclear Material Safety and Safeguards, a separate 
document, entitled ``Applicant's Environmental Report'' or ``Supplement 
to Applicant's Environmental Report,'' as appropriate. The ``Applicant's 
Environmental Report'' shall contain the information specified in Sec. 
51.45. If the application is for an amendment to or a renewal of a 
license or other form of permission for which the applicant has 
previously submitted an environmental report, the supplement to 
applicant's environmental report may be limited to incorporating by 
reference, updating or supplementing the information previously 
submitted to reflect any significant environmental change, including any 
significant environmental change resulting from operational experience 
or a change in operations or proposed decommissioning activities. If the 
applicant is the U.S. Department of Energy, the environmental report may 
be in the form of either an environmental impact statement or an 
environmental assessment, as appropriate.
    (b) As required by paragraph (a) of this section, each applicant 
shall prepare an environmental report for the following types of 
actions:
    (1) Issuance or renewal of a license or other form of permission 
for:
    (i) Possession and use of special nuclear material for processing 
and fuel fabrication, scrap recovery, or conversion of uranium 
hexafluoride pursuant to part 70 of this chapter.
    (ii) Possession and use of source material for uranium milling or 
production of uranium hexafluoride pursuant to part 40 of this chapter.
    (iii) Storage of spent fuel in an independent spent fuel storage 
installation (ISFSI) or the storage of spent fuel or high-level radio-
active waste in a monitored retrievable storage installation (MRS) 
pursuant to part 72 of this chapter.
    (iv) Receipt and disposal of radioactive waste from other persons 
pursuant to part 61 of this chapter.
    (v) Processing of source material for extraction of rare earth and 
other metals.
    (vi) Use of radioactive tracers in field flood studies involving 
secondary and tertiary oil and gas recovery.
    (vii) Construction and operation of a uranium enrichment facility.
    (2) Issuance of an amendment that would authorize or result in (i) a 
significant expansion of a site, (ii) a significant change in the types 
of effluents, (iii) a significant increase in the amounts of effluents, 
(iv) a significant increase in individual or cumulative occupational 
radiation exposure, (v) a significant increase in the potential for or 
consequences from radiological accidents, or (vi) a significant increase 
in spent fuel storage capacity, in a license or other form of permission 
to conduct an activity listed in paragraph (b)(1) of this section.
    (3) Amendment of a license to authorize the decommissioning of an 
independent spent fuel storage installation (ISFSI) or a monitored 
retrievable storage installation (MRS) pursuant to part 72 of this 
chapter.
    (4) Issuance of a license amendment pursuant to part 61 of this 
chapter authorizing (i) closure of a land disposal site, (ii) transfer 
of the license to the disposal site owner for the purpose of 
institutional control, or (iii) termination of the license at the end of 
the institutional control period.
    (5) Any other licensing action for which the Commission determines 
an Environmental Report is necessary.

[49 FR 9381, Mar. 12, 1984, as amended at 53 FR 31681, Aug. 19, 1988; 57 
FR 18392, Apr. 30, 1992; 58 FR 7737, Feb. 9, 1993; 62 FR 26732, May 14, 
1997; 68 FR 58811, Oct. 10, 2003]



Sec. 51.61  Environmental report--independent spent fuel storage 
installation (ISFSI) or monitored retrievable storage installation
(MRS) license.

    Each applicant for issuance of a license for storage of spent fuel 
in an

[[Page 36]]

independent spent fuel storage installation (ISFSI) or for the storage 
of spent fuel and high-level radioactive waste in a monitored 
retrievable storage installation (MRS) pursuant to part 72 of this 
chapter shall submit with its application to: ATTN: Document Control 
Desk, Director, Office of Nuclear Material Safety and Safeguards, a 
separate document entitled ``Applicant's Environmental Report--ISFSI 
License'' or ``Applicant's Environmental Report--MRS License,'' as 
appropriate. If the applicant is the U.S. Department of Energy, the 
environmental report may be in the form of either an environmental 
impact statement or an environmental assessment, as appropriate. The 
environmental report shall contain the information specified in Sec. 
51.45 and shall address the siting evaluation factors contained in 
subpart E of part 72 of this chapter. As stated in Sec. 51.23, no 
discussion of the environmental impacts of the continued storage of 
spent fuel in an ISFSI is required in this report.

[79 FR 56261, Sept. 19, 2014]



Sec. 51.62  Environmental report--land disposal of radioactive waste
licensed under 10 CFR part 61.

    (a) Each applicant for issuance of a license for land disposal of 
radioactive waste pursuant to part 61 of this chapter shall submit with 
its application to: ATTN: Document Control Desk, Director of Nuclear 
Material Safety and Safeguards, a separate document, entitled 
``Applicant's Environmental Report--License for Land Disposal of 
Radioactive Waste.'' The environmental report and any supplement to the 
environmental report may incorporate by reference information contained 
in the application or in any previous application, statement or report 
filed with the Commission provided that such references are clear and 
specific and that copies of the information so incorporated are 
available at the NRC Web site, http://www.nrc.gov, and/or at the NRC 
Public Document Room.
    (b) The environmental report shall contain the information specified 
in Sec. 51.45, shall address the applicant's environmental monitoring 
program required by Sec. Sec. 61.12(l), 61.53 and 61.59(b) of this 
chapter, and shall be as complete as possible in the light of 
information that is available at the time the environmental report is 
submitted.
    (c) The applicant shall supplement the environmental report in a 
timely manner as necessary to permit the Commission to review, prior to 
issuance, amendment or renewal of a license, new information regarding 
the environmental impact of previously proposed activities, information 
regarding the environmental impact of any changes in previously proposed 
activities, or any significant new information regarding the 
environmental impact of closure activities and long-term performance of 
the disposal site.

[49 FR 9381, Mar. 12, 1984, as amended at 53 FR 43420, Oct. 27, 1988; 64 
FR 48952, Sept. 9, 1999; 68 FR 58811, Oct. 10, 2003]



Sec. 51.66  Environmental report--number of copies; distribution.

    Each applicant for a license or other form of permission, or an 
amendment to or renewal of a license or other form of permission issued 
under parts 30, 32, 33, 34, 35, 36, 39, 40, 61, 70, and/or 72 of this 
chapter, and covered by Sec. Sec. 51.60(b)(1) through (6); or by 
Sec. Sec. 51.61 or 51.62 shall submit to the Director of Nuclear 
Material Safety and Safeguards an environmental report or any supplement 
to an environmental report in the manner specified in Sec. 51.58(a). 
The applicant shall maintain the capability to generate additional 
copies of the environmental report or any supplement to the 
environmental report for subsequent distribution to Federal, State, and 
local officials, and any affected Indian Tribes in accordance with 
written instructions issued by the Director of Nuclear Material Safety 
and Safeguards.

[72 FR 49514, Aug. 28, 2007]



Sec. 51.67  Environmental information concerning geologic repositories.

    (a) In lieu of an environmental report, the Department of Energy, as 
an applicant for a license or license amendment pursuant to part 60 or 
63 of this chapter, shall submit to the Commission any final 
environmental impact statement which the Department prepares in 
connection with any geologic repository developed under Subtitle A of 
Title I, or under Title IV, of

[[Page 37]]

the Nuclear Waste Policy Act of 1982, as amended. (See Sec. 60.22 or 
Sec. 63.22 of this chapter as to the required time and manner of 
submission.) The statement shall include, among the alternatives under 
consideration, denial of a license or construction authorization by the 
Commission.
    (b) Under applicable provisions of law, the Department of Energy may 
be required to supplement its final environmental impact statement if it 
makes a substantial change in its proposed action that is relevant to 
environmental concerns or determines that there are significant new 
circumstances or information relevant to environmental concerns and 
bearing on the proposed action or its impacts. The Department shall 
submit any supplement to its final environmental impact statement to the 
Commission. (See Sec. 60.22 or Sec. 63.22 of this chapter as to the 
required time and manner of submission.)
    (c) Whenever the Department of Energy submits a final environmental 
impact statement, or a final supplement to an environmental impact 
statement, to the Commission pursuant to this section, it shall also 
inform the Commission of the status of any civil action for judicial 
review initiated pursuant to section 119 of the Nuclear Waste Policy Act 
of 1982. This status report, which the Department shall update from time 
to time to reflect changes in status, shall:
    (1) State whether the environmental impact statement has been found 
by the courts of the United States to be adequate or inadequate; and
    (2) Identify any issues relating to the adequacy of the 
environmental impact statement that may remain subject to judicial 
review.

[54 FR 27870, July 3, 1989, as amended at 66 FR 55791, Nov. 2, 2001]

                    environmental reports--rulemaking



Sec. 51.68  Environmental report--rulemaking.

    Petitioners for rulemaking requesting amendments of parts 30, 31, 
32, 33, 34, 35, 36, 39, 40 or part 70 of this chapter concerning the 
exemption from licensing and regulatory requirements of or authorizing 
general licenses for any equipment, device, commodity or other product 
containing byproduct material, source material or special nuclear 
material shall submit with the petition a separate document entitled 
``Petitioner's Environmental Report,'' which shall contain the 
information specified in Sec. 51.45.

[68 FR 58811, Oct. 10, 2003]

                     Environmental Impact Statements

       draft environmental impact statements--general requirements



Sec. 51.70  Draft environmental impact statement--general.

    (a) The NRC staff will prepare a draft environmental impact 
statement as soon as practicable after publication of the notice of 
intent to prepare an environmental impact statement and completion of 
the scoping process. To the fullest extent practicable, environmental 
impact statements will be prepared concurrently or integrated with 
environmental impact analyses and related surveys and studies required 
by other Federal law.
    (b) The draft environmental impact statement will be concise, clear 
and analytic, will be written in plain language with appropriate 
graphics, will state how alternatives considered in it and decisions 
based on it will or will not achieve the requirements of sections 101 
and 102(1) of NEPA and of any other relevant and applicable 
environmental laws and policies, will identify any methodologies used 
and sources relied upon, and will be supported by evidence that the 
necessary environmental analyses have been made. The format provided in 
section 1(a) of appendix A of this subpart should be used. The NRC staff 
will independently evaluate and be responsible for the reliability of 
all information used in the draft environmental impact statement.
    (c) The Commission will cooperate with State and local agencies to 
the fullest extent possible to reduce duplication between NEPA and State 
and local requirements, in accordance with 40 CFR 1506.2 (b) and (c).

[[Page 38]]



Sec. 51.71  Draft environmental impact statement--contents.

    (a) Scope. The draft environmental impact statement will be prepared 
in accordance with the scope decided upon in the scoping process 
required by Sec. Sec. 51.26 and 51.29. As appropriate and to the extent 
required by the scope, the draft statement will address the topics in 
paragraphs (b), (c), (d) and (e) of this section and the matters 
specified in Sec. Sec. 51.45, 51.50, 51.51, 51.52, 51.53, 51.54, 51.61 
and 51.62.
    (b) Analysis of major points of view. To the extent sufficient 
information is available, the draft environmental impact statement will 
include consideration of major points of view concerning the 
environmental impacts of the proposed action and the alternatives, and 
contain an analysis of significant problems and objections raised by 
other Federal, State, and local agencies, by any affected Indian Tribes, 
and by other interested persons.
    (c) Status of compliance. The draft environmental impact statement 
will list all Federal permits, licenses, approvals, and other 
entitlements which must be obtained in implementing the proposed action 
and will describe the status of compliance with those requirements. If 
it is uncertain whether a Federal permit, license, approval, or other 
entitlement is necessary, the draft environmental impact statement will 
so indicate.
    (d) Analysis. Unless excepted in this paragraph or Sec. 51.75, the 
draft environmental impact statement will include a preliminary analysis 
that considers and weighs the environmental effects, including any 
cumulative effects, of the proposed action; the environmental impacts of 
alternatives to the proposed action; and alternatives available for 
reducing or avoiding adverse environmental effects. Additionally, the 
draft environmental impact statement will include a consideration of the 
economic, technical, and other benefits and costs of the proposed action 
and alternatives. The draft environmental impact statement will indicate 
what other interests and considerations of Federal policy, including 
factors not related to environmental quality, if applicable, are 
relevant to the consideration of environmental effects of the proposed 
action identified under paragraph (a) of this section. The draft 
supplemental environmental impact statement prepared at the license 
renewal stage under Sec. 51.95(c) need not discuss the economic or 
technical benefits and costs of either the proposed action or 
alternatives except if benefits and costs are either essential for a 
determination regarding the inclusion of an alternative in the range of 
alternatives considered or relevant to mitigation. In addition, the 
supplemental environmental impact statement prepared at the license 
renewal stage need not discuss other issues not related to the 
environmental effects of the proposed action and associated 
alternatives. The draft supplemental environmental impact statement for 
license renewal prepared under Sec. 51.95(c) will rely on conclusions 
as amplified by the supporting information in the GEIS for issues 
designated as Category 1 in appendix B to subpart A of this part. The 
draft supplemental environmental impact statement must contain an 
analysis of those issues identified as Category 2 in appendix B to 
subpart A of this part that are open for the proposed action. The 
analysis for all draft environmental impact statements will, to the 
fullest extent practicable, quantify the various factors considered. To 
the extent that there are important qualitative considerations or 
factors that cannot be quantified, these considerations or factors will 
be discussed in qualitative terms. Consideration will be given to 
compliance with environmental quality standards and requirements that 
have been imposed by Federal, State, regional, and local agencies having 
responsibility for environmental protection, including applicable zoning 
and land-use regulations and water pollution limitations or requirements 
issued or imposed under the Federal Water Pollution Control Act. The 
environmental impact of the proposed action will be considered in the 
analysis with respect to matters covered by environmental quality 
standards and requirements irrespective of whether a certification or 
license from the appropriate

[[Page 39]]

authority has been obtained. \3\ While satisfaction of Commission 
standards and criteria pertaining to radiological effects will be 
necessary to meet the licensing requirements of the Atomic Energy Act, 
the analysis will, for the purposes of NEPA, consider the radiological 
effects of the proposed action and alternatives.
---------------------------------------------------------------------------

    \3\ Compliance with the environmental quality standards and 
requirements of the Federal Water Pollution Control Act (imposed by EPA 
or designated permitting states) is not a substitute for, and does not 
negate the requirement for NRC to weigh all environmental effects of the 
proposed action, including the degradation, if any, of water quality, 
and to consider alternatives to the proposed action that are available 
for reducing adverse effects. Where an environmental assessment of 
aquatic impact from plant discharges is available from the permitting 
authority, the NRC will consider the assessment in its determination of 
the magnitude of environmental impacts for striking an overall cost-
benefit balance at the construction permit and operating license and 
early site permit and combined license stages, and in its determination 
of whether the adverse environmental impacts of license renewal are so 
great that preserving the option of license renewal for energy planning 
decision-makers would be unreasonable at the license renewal stage. When 
no such assessment of aquatic impacts is available from the permitting 
authority, NRC will establish on its own, or in conjunction with the 
permitting authority and other agencies having relevant expertise, the 
magnitude of potential impacts for striking an overall cost-benefit 
balance for the facility at the construction permit and operating 
license and early site permit and combined license stages, and in its 
determination of whether the adverse environmental impacts of license 
renewal are so great that preserving the option of license renewal for 
energy planning decision-makers would be unreasonable at the license 
renewal stage.
---------------------------------------------------------------------------

    (e) Effect of limited work authorization. If a limited work 
authorization was issued either in connection with or subsequent to an 
early site permit, or in connection with a construction permit or 
combined license application, then the environmental impact statement 
for the construction permit or combined license application will not 
address or consider the sunk costs associated with the limited work 
authorization.
    (f) Preliminary recommendation. The draft environmental impact 
statement normally will include a preliminary recommendation by the NRC 
staff respecting the proposed action. This preliminary recommendation 
will be based on the information and analysis described in paragraphs 
(a) through (d) of this section and Sec. Sec. 51.75, 51.76, 51.80, 
51.85, and 51.95, as appropriate, and will be reached after considering 
the environmental effects of the proposed action and reasonable 
alternatives, \4\ and, except for supplemental environmental impact 
statements for the operating license renewal stage prepared pursuant to 
Sec. 51.95(c), after weighing the costs and benefits of the proposed 
action. In lieu of a recommendation, the NRC staff may indicate in the 
draft statement that two or more alternatives remain under 
consideration.
---------------------------------------------------------------------------

    \4\ The consideration of reasonable alternatives to a proposed 
action involving nuclear power reactors (e.g., alternative energy 
sources) is intended to assist the NRC in meeting its NEPA obligations 
and does not preclude any State authority from making separate 
determinations with respect to these alternatives and in no way 
preempts, displaces, or affects the authority of States or other Federal 
agencies to address these issues.

[49 FR 9381, Mar. 12, 1984, as amended at 61 FR 28488, June 5, 1996; 61 
FR 66544, Dec. 18, 1996; 72 FR 49514, Aug. 28, 2007; 72 FR 57445, Oct. 
9, 2007; 78 FR 37317, June 20, 2013]



Sec. 51.72  Supplement to draft environmental impact statement.

    (a) The NRC staff will prepare a supplement to a draft environmental 
impact statement for which a notice of availability has been published 
in the Federal Register as provided in Sec. 51.117, if:
    (1) There are substantial changes in the proposed action that are 
relevant to environmental concerns; or
    (2) There are significant new circumstances or information relevant 
to environmental concerns and bearing on the proposed action or its 
impacts.
    (b) The NRC staff may prepare a supplement to a draft environmental 
impact statement when, in its opinion, preparation of a supplement will 
further the purposes of NEPA.

[[Page 40]]

    (c) The supplement to a draft environmental impact statement will be 
prepared and noticed in the same manner as the draft environmental 
impact statement except that a scoping process need not be used.



Sec. 51.73  Request for comments on draft environmental impact statement.

    Each draft environmental impact statement and each supplement to a 
draft environmental impact statement distributed in accordance with 
Sec. 51.74, and each news release provided pursuant to Sec. 51.74(d) 
will be accompanied by or include a request for comments on the proposed 
action and on the draft environmental impact statement or any supplement 
to the draft environmental impact statement and will state where 
comments should be submitted and the date on which the comment period 
closes. A minimum comment period of 45 days will be provided. The 
comment period will be calculated from the date on which the 
Environmental Protection Agency notice stating that the draft statement 
or the supplement to the draft statement has been filed with EPA is 
published in the Federal Register. If no comments are provided within 
the time specified, it will be presumed, unless the agency or person 
requests an extension of time, that the agency or person has no comment 
to make. To the extent practicable, NRC staff will grant reasonable 
requests for extensions of time of up to fifteen (15) days.



Sec. 51.74  Distribution of draft environmental impact statement
and supplement to draft environmental impact statement; news releases.

    (a) A copy of the draft environmental impact statement will be 
distributed to:
    (1) The Environmental Protection Agency.
    (2) Any other Federal agency which has special expertise or 
jurisdiction by law with respect to any environmental impact involved or 
which is authorized to develop and enforce relevant environmental 
standards.
    (3) The applicant or petitioner for rulemaking and any other party 
to the proceeding.
    (4) Appropriate State and local agencies authorized to develop and 
enforce relevant environmental standards.
    (5) Appropriate State, regional and metropolitan clearinghouses.
    (6) Appropriate Indian Tribes when the proposed action may have an 
environmental impact on a reservation.
    (7) Upon written request, any organization or group included in the 
master list of interested organizations and groups maintained under 
Sec. 51.122.
    (8) Upon written request, any other person to the extent available.
    (b) Additional copies will be made available in accordance with 
Sec. 51.123.
    (c) A supplement to a draft environmental impact statement will be 
distributed in the same manner as the draft environmental impact 
statement to which it relates.
    (d) News releases stating the availability for comment and place for 
obtaining or inspecting a draft environmental statement or supplement 
will be provided to local newspapers and other appropriate media.
    (e) A notice of availability will be published in the Federal 
Register in accordance with Sec. 51.117.

   draft environmental impact statements--production and utilization 
                               facilities



Sec. 51.75  Draft environmental impact statement--construction permit,
early site permit, or combined license.

    (a) Construction permit stage. A draft environmental impact 
statement relating to issuance of a construction permit for a production 
or utilization facility will be prepared in accordance with the 
procedures and measures described in Sec. Sec. 51.70, 51.71, 51.72, and 
51.73. The contribution of the environmental effects of the uranium fuel 
cycle activities specified in Sec. 51.51 shall be evaluated on the 
basis of impact values set forth in Table S-3, Table of Uranium Fuel 
Cycle Environmental Data, which shall be set out in the draft 
environmental impact statement. With the exception of radon-222 and 
technetium-99 releases, no further discussion of fuel cycle release 
values and other numerical data that appear explicitly in the

[[Page 41]]

table shall be required.\5\ The impact statement shall take account of 
dose commitments and health effects from fuel cycle effluents set forth 
in Table S-3 and shall in addition take account of economic, 
socioeconomic, and possible cumulative impacts and other fuel cycle 
impacts as may reasonably appear significant. As stated in Sec. 51.23, 
the generic impact determinations regarding the continued storage of 
spent fuel in NUREG-2157 shall be deemed incorporated into the 
environmental impact statement.
---------------------------------------------------------------------------

    \5\ Values for releases of Rn-222 and Tc-99 are not given in the 
table. The amount and significance of Rn-222 releases from the fuel 
cycle and Tc-99 releases from waste management or reprocessing 
activities shall be considered in the draft environmental impact 
statement and may be the subject of litigation in individual licensing 
proceedings.
---------------------------------------------------------------------------

    (b) Early site permit stage. A draft environmental impact statement 
relating to issuance of an early site permit for a production or 
utilization facility will be prepared in accordance with the procedures 
and measures described in Sec. Sec. 51.70, 51.71, 51.72, 51.73, and 
this section. The contribution of the environmental effects of the 
uranium fuel cycle activities specified in Sec. 51.51 shall be 
evaluated on the basis of impact values set forth in Table S-3, Table of 
Uranium Fuel Cycle Environmental Data, which shall be set out in the 
draft environmental impact statement. With the exception of radon-222 
and technetium-99 releases, no further discussion of fuel cycle release 
values and other numerical data that appear explicitly in the table 
shall be required.\5\ The impact statement shall take account of dose 
commitments and health effects from fuel cycle effluents set forth in 
Table S-3 and shall in addition take account of economic, socioeconomic, 
and possible cumulative impacts and other fuel cycle impacts as may 
reasonably appear significant. As stated in Sec. 51.23, the generic 
impact determinations regarding the continued storage of spent fuel in 
NUREG-2157 shall be deemed incorporated into the environmental impact 
statement. The draft environmental impact statement must include an 
evaluation of alternative sites to determine whether there is any 
obviously superior alternative to the site proposed. The draft 
environmental impact statement must also include an evaluation of the 
environmental effects of construction and operation of a reactor, or 
reactors, which have design characteristics that fall within the site 
characteristics and design parameters for the early site permit 
application, but only to the extent addressed in the early site permit 
environmental report or otherwise necessary to determine whether there 
is any obviously superior alternative to the site proposed. The draft 
environmental impact statement must not include an assessment of the 
economic, technical, or other benefits (for example, need for power) and 
costs of the proposed action or an evaluation of alternative energy 
sources, unless these matters are addressed in the early site permit 
environmental report.
    (c) Combined license stage. A draft environmental impact statement 
relating to issuance of a combined license that does not reference an 
early site permit will be prepared in accordance with the procedures and 
measures described in Sec. Sec. 51.70, 51.71, 51.72, and 51.73. The 
contribution of the environmental effects of the uranium fuel cycle 
activities specified in Sec. 51.51 shall be evaluated on the basis of 
impact values set forth in Table S-3, Table of Uranium Fuel Cycle 
Environmental Data, which shall be set out in the draft environmental 
impact statement. With the exception of radon-222 and technetium-99 
releases, no further discussion of fuel cycle release values and other 
numerical data that appear explicitly in the table shall be required.\5\ 
The impact statement shall take account of dose commitments and health 
effects from fuel cycle effluents set forth in Table S-3 and shall in 
addition take account of economic, socioeconomic, and possible 
cumulative impacts and other fuel cycle impacts as may reasonably appear 
significant. As stated in Sec. 51.23, the generic impact determinations 
regarding the continued storage of spent fuel in NUREG-2157 shall be 
deemed incorporated into the environmental impact statement.
    (1) Combined license application referencing an early site permit. 
If the combined license application references an early site permit, 
then the NRC staff

[[Page 42]]

shall prepare a draft supplement to the early site permit environmental 
impact statement. The supplement must be prepared in accordance with 
Sec. 51.92(e).
    (2) Combined license application referencing a standard design 
certification. If the combined license application references a standard 
design certification and the site characteristics of the combined 
license's site fall within the site parameters specified in the design 
certification environmental assessment, then the draft combined license 
environmental impact statement shall incorporate by reference the design 
certification environmental assessment, and summarize the findings and 
conclusions of the environmental assessment with respect to severe 
accident mitigation design alternatives.
    (3) Combined license application referencing a manufactured reactor. 
If the combined license application proposes to use a manufactured 
reactor and the site characteristics of the combined license's site fall 
within the site parameters specified in the manufacturing license 
environmental assessment, then the draft combined license environmental 
impact statement shall incorporate by reference the manufacturing 
license environmental assessment, and summarize the findings and 
conclusions of the environmental assessment with respect to severe 
accident mitigation design alternatives. The combined license 
environmental impact statement report will not address the environmental 
impacts associated with manufacturing the reactor under the 
manufacturing license.

[72 FR 49514, Aug. 28, 2007, as amended at 79 FR 56261, Sept. 19, 2014]



Sec. 51.76  Draft environmental impact statement--limited work
authorization.

    The NRC will prepare a draft environmental impact statement relating 
to issuance of a limited work authorization in accordance with the 
procedures and measures described in Sec. Sec. 51.70, 51.71, and 51.73, 
as further supplemented or modified in the following paragraphs.
    (a) Limited work authorization submitted as part of complete 
construction permit or combined license application. If the application 
for a limited work authorization is submitted as part of a complete 
construction permit or combined license application, then the NRC may 
prepare a partial draft environmental impact statement. The analysis 
called for by Sec. 51.71(d) must be limited to the activities proposed 
to be conducted under the limited work authorization. Alternatively, the 
NRC may prepare a complete draft environmental impact statement prepared 
in accordance with Sec. 51.75(a) or (c), as applicable.
    (b) Phased application for limited work authorization under Sec. 
2.101(a)(9) of this chapter. If the application for a limited work 
authorization is submitted in accordance with Sec. 2.101(a)(9) of this 
chapter, then the draft environmental impact statement for part one of 
the application may be limited to consideration of the activities 
proposed to be conducted under the limited work authorization, and the 
proposed redress plan. However, if the environmental report contains the 
full set of information required to be submitted under Sec. 51.50(a) or 
(c), then a draft environmental impact statement must be prepared in 
accordance with Sec. 51.75(a) or (c), as applicable. Siting issues, 
including whether there is an obviously superior alternative site, or 
issues related to operation of the proposed nuclear power plant at the 
site, including need for power, may not be considered. After part two of 
the application is docketed, the NRC will prepare a draft supplement to 
the final environmental impact statement for part two of the application 
under Sec. 51.72. No updating of the information contained in the final 
environmental impact statement prepared for part one is necessary in 
preparation of the supplemental environmental impact statement. The 
draft supplement must consider all environmental impacts associated with 
the prior issuance of the limited work authorization, but may not 
address or consider the sunk costs associated with the limited work 
authorization.
    (c) Limited work authorization submitted as part of an early site 
permit application. If the application for a limited work authorization 
is submitted as part of an application for an early site permit, then 
the NRC will prepare

[[Page 43]]

an environmental impact statement in accordance with Sec. 51.75(b). 
However, the analysis called for by Sec. 51.71(d) must also address the 
activities proposed to be conducted under the limited work 
authorization.
    (d) Limited work authorization request submitted by an early site 
permit holder. If the application for a limited work authorization is 
submitted by a holder of an early site permit, then the NRC will prepare 
a draft supplement to the environmental impact statement for the early 
site permit. The supplement is limited to consideration of the 
activities proposed to be conducted under the limited work 
authorization, the adequacy of the proposed redress plan, and whether 
there is new and significant information identified with respect to 
issues related to the impacts of construction of the facility that were 
resolved in the early site permit proceeding with respect to the 
environmental impacts of the activities to be conducted under the 
limited work authorization. No other updating of the information 
contained in the final environmental impact statement prepared for the 
early site permit is required.
    (e) Limited work authorization for a site where an environmental 
impact statement was prepared, but the facility construction was not 
completed. If the limited work authorization is for activities to be 
conducted at a site for which the Commission has previously prepared an 
environmental impact statement for the construction and operation of a 
nuclear power plant, and a construction permit was issued but 
construction of the plant was not completed, then the draft 
environmental impact statement shall incorporate by reference the 
earlier environmental impact statement. The draft environmental impact 
statement must be limited to a consideration of whether there is 
significant new information with respect to the environmental impacts of 
construction, relevant to the activities to be conducted under the 
limited work authority, so that the conclusion of the referenced 
environmental impact statement on the impacts of construction would, 
when analyzed in accordance with Sec. 51.71, lead to the conclusion 
that the limited work authorization should not be issued or should be 
issued with appropriate conditions.
    (f) Draft environmental impact statement. A draft environmental 
impact statement prepared under this section must separately evaluate 
the environmental impacts and proposed alternatives attributable to the 
activities proposed to be conducted under the limited work 
authorization. However, if the ``Applicant's Environmental Report--
Limited Work Authorization Stage,'' also contains the information 
required to be submitted in the environmental report required under 
Sec. 51.50, then the environmental impact statement must address the 
impacts of construction and operation for the proposed facility 
(including the environmental impacts attributable to the limited work 
authorization), and discuss the overall costs and benefits balancing for 
the underlying proposed action, in accordance with Sec. 51.71, and 
Sec. 51.75(a) or (c), as applicable.

[72 FR 57445, Oct. 9, 2007]



Sec. 51.77  Distribution of draft environmental impact statement.

    (a) In addition to the distribution authorized by Sec. 51.74, a 
copy of a draft environmental statement for a licensing action for a 
production or utilization facility, except an action authorizing 
issuance, amendment or renewal of a license to manufacture a nuclear 
power reactor pursuant to 10 CFR part 52, appendix M will also be 
distributed to:
    (1) The chief executive of the municipality or county identified in 
the draft environmental impact statement as the preferred site for the 
proposed facility or activity.
    (2) Upon request, the chief executive of each municipality or county 
identified in the draft environmental impact statement as an alternative 
site.
    (b) Additional copies will be made available in accordance with 
Sec. 51.123.

[49 FR 9381, Mar. 12, 1984, as amended at 54 FR 15398, Apr. 18, 1989]

[[Page 44]]

        draft environmental impact statements--materials licenses



Sec. 51.80  Draft environmental impact statement--materials license.

    (a) The NRC staff will either prepare a draft environmental impact 
statement or as provided in Sec. 51.92, a supplement to a final 
environmental impact statement for each type of action identified in 
Sec. 51.20(b) (7) through (12). Except as the context may otherwise 
require, procedures and measures similar to those described in 
Sec. Sec. 51.70, 51.71, 51.72 and 51.73 will be followed.
    (b)(1) Independent spent fuel storage installation (ISFSI). As 
stated in Sec. 51.23, the generic impact determinations regarding the 
continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated in the environmental impact statement.
    (2) Monitored retrievable storage installation (MRS). As provided in 
sections 141 (c), (d), and (e) and 148 (a) and (c) of the Nuclear Waste 
Policy Act of 1982, as amended (NWPA) (96 Stat. 2242, 2243, 42 U.S.C. 
10161 (c), (d), (e); 101 Stat. 1330-235, 1330-236, 42 U.S.C. 10168 (a) 
and (c)), a draft environmental impact statement for the construction of 
a monitored retrievable storage installation (MRS) will not address the 
need for the MRS or any alternative to the design criteria for an MRS 
set forth in section 141(b)(1) of the NWPA (96 Stat. 2242, 42 U.S.C. 
10161(b)(1)) but may consider alternative facility designs which are 
consistent with these design criteria.

[49 FR 34695, Aug. 31, 1984, as amended at 53 FR 31682, Aug. 19, 1988; 
79 FR 56262, Sept. 19, 2014]



Sec. 51.81  Distribution of draft environmental impact statement.

    Copies of the draft environmental impact statement and any 
supplement to the draft environmental impact statement will be 
distributed in accordance with the provisions of Sec. 51.74.

            draft environmental impact statements--rulemaking



Sec. 51.85  Draft environmental impact statement--rulemaking.

    Except as the context may otherwise require, procedures and measures 
similar to those described in Sec. Sec. 51.70, 51.71, 51.72 and 51.73 
will be followed in proceedings for rulemaking for which the Commission 
has determined to prepare an environmental impact statement.



Sec. 51.86  Distribution of draft environmental impact statement.

    Copies of the draft environmental impact statement and any 
supplement to the draft environmental impact statement will be 
distributed in accordance with the provisions of Sec. 51.74.

 legislative environmental impact statements--proposals for legislation



Sec. 51.88  Proposals for legislation.

    The Commission will, as a matter of policy, follow the provisions of 
40 CFR 1506.8 regarding the NEPA process for proposals for legislation.

       final environmental impact statements--general requirements



Sec. 51.90  Final environmental impact statement--general.

    After receipt and consideration of comments requested pursuant to 
Sec. Sec. 51.73 and 51.117, the NRC staff will prepare a final 
environmental impact statement in accordance with the requirements in 
Sec. Sec. 51.70(b) and 51.71 for a draft environmental impact 
statement. The format provided in section 1(a) of appendix A of this 
subpart should be used.



Sec. 51.91  Final environmental impact statement--contents.

    (a)(1) The final environmental impact statement will include 
responses to any comments on the draft environmental impact statement or 
on any supplement to the draft environmental impact statement. Responses 
to comments may include:
    (i) Modification of alternatives, including the proposed action;
    (ii) Development and evaluation of alternatives not previously given 
serious consideration;
    (iii) Supplementation or modification of analyses;
    (iv) Factual corrections;
    (v) Explanation of why comments do not warrant further response, 
citing

[[Page 45]]

sources, authorities or reasons which support this conclusion.
    (2) All substantive comments received on the draft environmental 
impact statement or any supplement to the draft environmental impact 
statement (or summaries thereof where the response has been 
exceptionally voluminous) will be attached to the final statement, 
whether or not each comment is discussed individually in the text of the 
statement.
    (3) If changes in the draft environmental impact statement in 
response to comments are minor and are confined either to factual 
corrections or to explanations of why the comments do not warrant 
further response, the changes may be made by attaching errata sheets to 
the draft statement. The entire document with a new cover may then be 
issued as the final environmental impact statement.
    (b) The final environmental impact statement will discuss any 
relevant responsible opposing view not adequately discussed in the draft 
environmental impact statement or in any supplement to the draft 
environmental impact statement, and respond to the issues raised.
    (c) The final environmental impact statement will state how the 
alternatives considered in it and decisions based on it will or will not 
achieve the requirements of sections 101 and 102(1) of NEPA and of any 
other relevant and applicable environmental laws and policies.
    (d) The final environmental impact statement will include a final 
analysis and a final recommendation on the action to be taken.



Sec. 51.92  Supplement to the final environmental impact statement.

    (a) If the proposed action has not been taken, the NRC staff will 
prepare a supplement to a final environmental impact statement for which 
a notice of availability has been published in the Federal Register as 
provided in Sec. 51.118, if:
    (1) There are substantial changes in the proposed action that are 
relevant to environmental concerns; or
    (2) There are new and significant circumstances or information 
relevant to environmental concerns and bearing on the proposed action or 
its impacts.
    (b) In a proceeding for a combined license application under 10 CFR 
part 52 referencing an early site permit under part 52, the NRC staff 
shall prepare a supplement to the final environmental impact statement 
for the referenced early site permit in accordance with paragraph (e) of 
this section.
    (c) The NRC staff may prepare a supplement to a final environmental 
impact statement when, in its opinion, preparation of a supplement will 
further the purposes of NEPA.
    (d) The supplement to a final environmental impact statement will be 
prepared in the same manner as the final environmental impact statement 
except that a scoping process need not be used.
    (e) The supplement to an early site permit final environmental 
impact statement which is prepared for a combined license application in 
accordance with Sec. 51.75(c)(1) and paragraph (b) of this section 
must:
    (1) Identify the proposed action as the issuance of a combined 
license for the construction and operation of a nuclear power plant as 
described in the combined license application at the site described in 
the early site permit referenced in the combined license application;
    (2) Incorporate by reference the final environmental impact 
statement prepared for the early site permit;
    (3) Contain no separate discussion of alternative sites;
    (4) Include an analysis of the economic, technical, and other 
benefits and costs of the proposed action, to the extent that the final 
environmental impact statement prepared for the early site permit did 
not include an assessment of these benefits and costs;
    (5) Include an analysis of other energy alternatives, to the extent 
that the final environmental impact statement prepared for the early 
site permit did not include an assessment of energy alternatives;
    (6) Include an analysis of any environmental issue related to the 
impacts of construction or operation of the facility that was not 
resolved in the proceeding on the early site permit; and

[[Page 46]]

    (7) Include an analysis of the issues related to the impacts of 
construction and operation of the facility that were resolved in the 
early site permit proceeding for which new and significant information 
has been identified, including, but not limited to, new and significant 
information demonstrating that the design of the facility falls outside 
the site characteristics and design parameters specified in the early 
site permit.
    (f)(1) A supplement to a final environmental impact statement will 
be accompanied by or will include a request for comments as provided in 
Sec. 51.73 and a notice of availability will be published in the 
Federal Register as provided in Sec. 51.117 if paragraphs (a) or (b) of 
this section applies.
    (2) If comments are not requested, a notice of availability of a 
supplement to a final environmental impact statement will be published 
in the Federal Register as provided in Sec. 51.118.

[72 FR 49515, Aug. 28, 2007]



Sec. 51.93  Distribution of final environmental impact statement
and supplement to final environmental impact statement; news releases.

    (a) A copy of the final environmental impact statement will be 
distributed to:
    (1) The Environmental Protection Agency.
    (2) The applicant or petitioner for rulemaking and any other party 
to the proceeding.
    (3) Appropriate State, regional and metropolitan clearinghouses.
    (4) Each commenter.
    (b) Additional copies will be made available in accordance with 
Sec. 51.123.
    (c) If the final environmental impact statement is unusually long or 
there are so many comments on a draft environmental impact statement or 
any supplement to a draft environmental impact statement that 
distribution of the entire final statement to all commenters is 
impracticable, a summary of the final statement and the substantive 
comments will be distributed. When the final environmental impact 
statement has been prepared by adding errata sheets to the draft 
environmental impact statement as provided in Sec. 51.91(a)(3), only 
the comments, the responses to the comments and the changes to the 
environmental impact statement will be distributed.
    (d) A supplement to a final environmental impact statement will be 
distributed in the same manner as the final environmental impact 
statement to which it relates.
    (e) News releases stating the availability and place for obtaining 
or inspecting a final environmental impact statement or supplement will 
be provided to local newspapers and other appropriate media.
    (f) A notice of availability will be published in the Federal 
Register in accordance with Sec. 51.118.



Sec. 51.94  Requirement to consider final environmental impact
statement.

    The final environmental impact statement, together with any comments 
and any supplement, will accompany the application or petition for 
rulemaking through, and be considered in, the Commission's 
decisionmaking process. The final environmental impact statement, 
together with any comments and any supplement, will be made a part of 
the record of the appropriate adjudicatory or rulemaking proceeding.

   final environmental impact statements--production and utilization 
                               facilities



Sec. 51.95  Postconstruction environmental impact statements.

    (a) General. Any supplement to a final environmental impact 
statement or any environmental assessment prepared under the provisions 
of this section may incorporate by reference any information contained 
in a final environmental document previously prepared by the NRC staff 
that relates to the same production or utilization facility. Documents 
that may be referenced include, but are not limited to, the final 
environmental impact statement; supplements to the final environmental 
impact statement, including supplements prepared at the operating 
license stage; NRC staff-prepared final generic environmental impact 
statements; environmental assessments and records of decisions prepared 
in connection with the construction permit,

[[Page 47]]

the operating license, the early site permit, or the combined license 
and any license amendment for that facility. A supplement to a final 
environmental impact statement will include a request for comments as 
provided in Sec. 51.73.
    (b) Initial operating license stage. In connection with the issuance 
of an operating license for a production or utilization facility, the 
NRC staff will prepare a supplement to the final environmental impact 
statement on the construction permit for that facility, which will 
update the prior environmental review. The supplement will only cover 
matters that differ from the final environmental impact statement or 
that reflect significant new information concerning matters discussed in 
the final environmental impact statement. Unless otherwise determined by 
the Commission, a supplement on the operation of a nuclear power plant 
will not include a discussion of need for power, or of alternative 
energy sources, or of alternative sites, and will only be prepared in 
connection with the first licensing action authorizing full-power 
operation. As stated in Sec. 51.23, the generic impact determinations 
regarding the continued storage of spent fuel in NUREG-2157 shall be 
deemed incorporated into the environmental impact statement.
    (c) Operating license renewal stage. In connection with the renewal 
of an operating license or combined license for a nuclear power plant 
under 10 CFR parts 52 or 54 of this chapter, the Commission shall 
prepare an environmental impact statement, which is a supplement to the 
Commission's NUREG-1437, ``Generic Environmental Impact Statement for 
License Renewal of Nuclear Plants'' (June 2013), which is available in 
the NRC's Public Document Room, 11555 Rockville Pike, Rockville, 
Maryland 20852.
    (1) The supplemental environmental impact statement for the 
operating license renewal stage shall address those issues as required 
by Sec. 51.71. In addition, the NRC staff must comply with 40 CFR 
1506.6(b)(3) in conducting the additional scoping process as required by 
Sec. 51.71(a).
    (2) The supplemental environmental impact statement for license 
renewal is not required to include discussion of need for power or the 
economic costs and economic benefits of the proposed action or of 
alternatives to the proposed action except insofar as such benefits and 
costs are either essential for a determination regarding the inclusion 
of an alternative in the range of alternatives considered or relevant to 
mitigation. In addition, the supplemental environmental impact statement 
prepared at the license renewal stage need not discuss other issues not 
related to the environmental effects of the proposed action and the 
alternatives. The analysis of alternatives in the supplemental 
environmental impact statement should be limited to the environmental 
impacts of such alternatives and should otherwise be prepared in 
accordance with Sec. 51.71 and appendix A to subpart A of this part. As 
stated in Sec. 51.23, the generic impact determinations regarding the 
continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated into the supplemental environmental impact statement.
    (3) The supplemental environmental impact statement shall be issued 
as a final impact statement in accordance with Sec. Sec. 51.91 and 
51.93 after considering any significant new information relevant to the 
proposed action contained in the supplement or incorporated by 
reference.
    (4) The supplemental environmental impact statement must contain the 
NRC staff's recommendation regarding the environmental acceptability of 
the license renewal action. In order to make recommendations and reach a 
final decision on the proposed action, the NRC staff, adjudicatory 
officers, and Commission shall integrate the conclusions in the generic 
environmental impact statement for issues designated as Category 1 with 
information developed for those Category 2 issues applicable to the 
plant under Sec. 51.53(c)(3)(ii) and any new and significant 
information. Given this information, the NRC staff, adjudicatory 
officers, and Commission shall determine whether or not the adverse 
environmental impacts of license renewal are so great that preserving 
the option of license renewal for energy planning decisionmakers would 
be unreasonable.

[[Page 48]]

    (d) Postoperating license stage. In connection with the amendment of 
an operating or combined license authorizing decommissioning activities 
at a production or utilization facility covered by Sec. 51.20, either 
for unrestricted use or based on continuing use restrictions applicable 
to the site, or with the issuance, amendment or renewal of a license to 
store spent fuel at a nuclear power reactor after expiration of the 
operating or combined license for the nuclear power reactor, the NRC 
staff will prepare a supplemental environmental impact statement for the 
post operating or post combined license stage or an environmental 
assessment, as appropriate, which will update the prior environmental 
documentation prepared by the NRC for compliance with NEPA under the 
provisions of this part. The supplement or assessment may incorporate by 
reference any information contained in the final environmental impact 
statement--for the operating or combined license stage, as appropriate, 
or in the records of decision prepared in connection with the early site 
permit, construction permit, operating license, or combined license for 
that facility. The supplement will include a request for comments as 
provided in Sec. 51.73. As stated in Sec. 51.23, the generic impact 
determinations regarding the continued storage of spent fuel in NUREG-
2157 shall be deemed incorporated into the supplemental environmental 
impact statement or shall be considered in the environmental assessment, 
if the impacts of continued storage of spent fuel are applicable to the 
proposed action.

[61 FR 66545, Dec. 18, 1996, as amended at 72 FR 49516, Aug. 28, 2007; 
78 FR 37317, June 20, 2013; 79 FR 56262, Sept. 19, 2014]

        final environmental impact statements--materials licenses



Sec. 51.97  Final environmental impact statement--materials license.

    (a) Independent spent fuel storage installation (ISFSI). As stated 
in Sec. 51.23, the generic impact determinations regarding the 
continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated into the environmental impact statement.
    (b) Monitored retrievable storage facility (MRS). As provided in 
sections 141 (c), (d), and (e) and 148 (a) and (c) of the Nuclear Waste 
Policy Act of 1982, as amended (NWPA) (96 Stat. 2242, 2243, 42 U.S.C. 
10161 (c), (d), (e); 101 Stat. 1330-235, 1330-236, 42 U.S.C. 10168 (a), 
(c)) a final environmental impact statement for the construction of a 
monitored retrievable storage installation (MRS) will not address the 
need for the MRS or any alternative to the design criteria for an MRS 
set forth in section 141(b)(1) of the NWPA (96 Stat. 2242, 42 U.S.C. 
10161(b)(1)) but may consider alternative facility designs which are 
consistent with these design criteria.
    (c) Uranium enrichment facility. As provided in section 5(e) of the 
Solar, Wind, Waste, and Geothermal Power Production Incentives Act of 
1990 (104 Stat. 2834 at 2835, 42 U.S.C. 2243), a final environmental 
impact statement must be prepared before the hearing on the issuance of 
a license for a uranium enrichment facility is completed.

[49 FR 34695, Aug. 31, 1984, as amended at 53 FR 31682, Aug. 19, 1988; 
57 FR 18392, Apr. 30, 1992; 79 FR 56262, Sept. 19, 2014]

            final environmental impact statements--rulemaking



Sec. 51.99  [Reserved]

                NEPA Procedure and Administrative Action

                                 general



Sec. 51.100  Timing of Commission action.

    (a)(1) Except as provided in Sec. 51.13 and paragraph (b) of this 
section, no decision on a proposed action, including the issuance of a 
permit, license, or other form of permission, or amendment to or renewal 
of a permit, license, or other form of permission, or the issuance of an 
effective regulation, for which an environmental impact statement is 
required, will be made and no record of decision will be issued until 
the later of the following dates:
    (i) Ninety (90) days after publication by the Environmental 
Protection Agency of a Federal Register notice stating that the draft 
environmental impact statement has been filed with EPA.

[[Page 49]]

    (ii) Thirty (30) days after publication by the Environmental 
Protection Agency of a Federal Register notice stating that the final 
environmental impact statement has been filed with EPA.
    (2) If a notice of filing of a final environmental impact statement 
is published by the Environmental Protection Agency within ninety (90) 
days after a notice of filing of a draft environmental impact statement 
has been published by EPA, the minimum thirty (30) day period and the 
minimum ninety (90) day period may run concurrently to the extent they 
overlap.
    (b) In any rulemaking proceeding for the purpose of protecting the 
public health or safety or the common defense and security, the 
Commission may make and publish the decision on the final rule at the 
same time that the Environmental Protection Agency publishes the Federal 
Register notice of filing of the final environmental impact statement.



Sec. 51.101  Limitations on actions.

    (a) Until a record of decision is issued in connection with a 
proposed licensing or regulatory action for which an environmental 
impact statement is required under Sec. 51.20, or until a final finding 
of no significant impact is issued in connection with a proposed 
licensing or regulatory action for which an environmental assessment is 
required under Sec. 51.21:
    (1) No action concerning the proposal may be taken by the Commission 
which would (i) have an adverse environmental impact, or (ii) limit the 
choice of reasonable alternatives.
    (2) Any action concerning the proposal taken by an applicant which 
would (i) have an adverse environmental impact, or (ii) limit the choice 
of reasonable alternatives may be grounds for denial of the license. In 
the case of an application covered by Sec. Sec. 30.32(f), 40.31(f), 
50.10(c), 70.21(f), or Sec. Sec. 72.16 and 72.34 of this chapter, the 
provisions of this paragraph will be applied in accordance with 
Sec. Sec. 30.33(a)(5), 40.32(e), 50.10 (c) and (e), 70.23(a)(7) or 
Sec. 72.40(b) of this chapter, as appropriate.
    (b) While work on a required program environmental impact statement 
is in progress, the Commission will not undertake in the interim any 
major Federal action covered by the program which may significantly 
affect the quality of the human environment unless such action:
    (1) Is justified independently of the program;
    (2) Is itself accompanied by an adequate environmental impact 
statement; and
    (3) Will not prejudice the ultimate decision on the program. Absent 
any satisfactory explanation to the contrary, interim action which tends 
to determine subsequent development or limit reasonable alternatives, 
will be considered prejudicial.
    (c) This section does not preclude any applicant for an NRC permit, 
license, or other form of permission, or amendment to or renewal of an 
NRC permit, license, or other form of permission, (1) from developing 
any plans or designs necessary to support an application; or (2) after 
prior notice and consultation with NRC staff, (i) from performing any 
physical work necessary to support an application, or (ii) from 
performing any other physical work relating to the proposed action if 
the adverse environmental impact of that work is de minimis.

[49 FR 9381, Mar. 12, 1984, as amended at 53 FR 31682, Aug. 19, 1988]



Sec. 51.102  Requirement to provide a record of decision; preparation.

    (a) A Commission decision on any action for which a final 
environmental impact statement has been prepared shall be accompanied by 
or include a concise public record of decision.
    (b) Except as provided in paragraph (c) of this section, the record 
of decision will be prepared by the NRC staff director authorized to 
take the action.
    (c) When a hearing is held on the proposed action under the 
regulations in subpart G of part 2 of this chapter or when the action 
can only be taken by the Commissioners acting as a collegial body, the 
initial decision of the presiding officer or the final decision of the 
Commissioners acting as a collegial body will constitute the record of 
decision. An initial or final decision

[[Page 50]]

constituting the record of decision will be distributed as provided in 
Sec. 51.93.

[49 FR 9381, Mar. 12, 1984, as amended at 77 FR 46600, Aug. 3, 2012; 79 
FR 66604, Nov. 10, 2014]



Sec. 51.103  Record of decision--general.

    (a) The record of decision required by Sec. 51.102 shall be clearly 
identified and shall:
    (1) State the decision.
    (2) Identify all alternatives considered by the Commission in 
reaching the decision, state that these alternatives were included in 
the range of alternatives discussed in the environmental impact 
statement, and specify the alternative or alternatives which were 
considered to be environmentally preferable.
    (3) Discuss preferences among alternatives based on relevant 
factors, including economic and technical considerations where 
appropriate, the NRC's statutory mission, and any essential 
considerations of national policy, which were balanced by the Commission 
in making the decision and state how these considerations entered into 
the decision.
    (4) State whether the Commission has taken all practicable measures 
within its jurisdiction to avoid or minimize environmental harm from the 
alternative selected, and if not, to explain why those measures were not 
adopted. Summarize any license conditions and monitoring programs 
adopted in connection with mitigation measures.
    (5) In making a final decision on a license renewal action pursuant 
to part 54 of this chapter, the Commission shall determine whether or 
not the adverse environmental impacts of license renewal are so great 
that preserving the option of license renewal for energy planning 
decisionmakers would be unreasonable.
    (6) In a construction permit or a combined license proceeding where 
a limited work authorization under 10 CFR 50.10 was issued, the 
Commission's decision on the construction permit or combined license 
application will not address or consider the sunk costs associated with 
the limited work authorization in determining the proposed action.
    (b) The record of decision may be integrated into any other record 
prepared by the Commission in connection with the action.
    (c) The record of decision may incorporate by reference material 
contained in a final environmental impact statement.

[49 FR 9381, Mar. 12, 1984, as amended at 61 FR 28490, June 5, 1996; 61 
FR 66546, Dec. 18, 1996; 61 FR 68543, Dec. 30, 1996; 72 FR 57445, Oct. 
9, 2007]



Sec. 51.104  NRC proceeding using public hearings; consideration 
of environmental impact statement.

    (a)(1) In any proceeding in which (i) a hearing is held on the 
proposed action, (ii) a final environmental impact statement has been 
prepared in connection with the proposed action, and (iii) matters 
within the scope of NEPA and this subpart are in issue, the NRC staff 
may not offer the final environmental impact statement in evidence or 
present the position of the NRC staff on matters within the scope of 
NEPA and this subpart until the final environmental impact statement is 
filed with the Environmental Protection Agency, furnished to commenting 
agencies and made available to the public.
    (2) Any party to the proceeding may take a position and offer 
evidence on the aspects of the proposed action within the scope of NEPA 
and this subpart in accordance with the provisions of part 2 of this 
chapter applicable to that proceeding or in accordance with the terms of 
the notice of hearing.
    (3) In the proceeding the presiding officer will decide those 
matters in controversy among the parties within the scope of NEPA and 
this subpart.
    (b) In any proceeding in which a hearing is held where the NRC staff 
has determined that no environmental impact statement need be prepared 
for the proposed action, unless the Commission orders otherwise, any 
party to the proceeding may take a position and offer evidence on the 
aspects of the proposed action within the scope of NEPA and this subpart 
in accordance with the provisions of part 2 of this chapter applicable 
to that proceeding or in accordance with the terms of the notice of 
hearing. In the proceeding, the presiding officer will decide any

[[Page 51]]

such matters in controversy among the parties.
    (c) In any proceeding in which a limited work authorization is 
requested, unless the Commission orders otherwise, a party to the 
proceeding may take a position and offer evidence only on the aspects of 
the proposed action within the scope of NEPA and this subpart which are 
within the scope of that party's admitted contention, in accordance with 
the provisions of part 2 of this chapter applicable to the limited work 
authorization or in accordance with the terms of any notice of hearing 
applicable to the limited work authorization. In the proceeding, the 
presiding officer will decide all matters in controversy among the 
parties.

[49 FR 9381, Mar. 12, 1984, as amended at 72 FR 57445, Oct. 9, 2007]

                  production and utilization facilities



Sec. 51.105  Public hearings in proceedings for issuance of 
construction permits or early site permits; limited work 
authorizations.

    (a) In addition to complying with applicable requirements of Sec. 
51.104, in a proceeding for the issuance of a construction permit or 
early site permit for a nuclear power reactor, testing facility, fuel 
reprocessing plant or isotopic enrichment plant, the presiding officer 
will:
    (1) Determine whether the requirements of Sections 102(2) (A), (C), 
and (E) of NEPA and the regulations in this subpart have been met;
    (2) Independently consider the final balance among conflicting 
factors contained in the record of the proceeding with a view to 
determining the appropriate action to be taken;
    (3) Determine, after weighing the environmental, economic, 
technical, and other benefits against environmental and other costs, and 
considering reasonable alternatives, whether the construction permit or 
early site permit should be issued, denied, or appropriately conditioned 
to protect environmental values;
    (4) Determine, in an uncontested proceeding, whether the NEPA review 
conducted by the NRC staff has been adequate; and
    (5) Determine, in a contested proceeding, whether in accordance with 
the regulations in this subpart, the construction permit or early site 
permit should be issued as proposed by the NRC's Director, Office of New 
Reactors or Director, Office of Nuclear Reactor Regulation, as 
appropriate.
    (b) The presiding officer in an early site permit hearing shall not 
admit contentions proffered by any party concerning the benefits 
assessment (e.g., need for power) or alternative energy sources if those 
issues were not addressed by the applicant in the early site permit 
application.
    (c)(1) In addition to complying with the applicable provisions of 
Sec. 51.104, in any proceeding for the issuance of a construction 
permit for a nuclear power plant or an early site permit under part 52 
of this chapter, where the applicant requests a limited work 
authorization under Sec. 50.10(d) of this chapter, the presiding 
officer shall--
    (i) Determine whether the requirements of Section 102(2)(A), (C), 
and (E) of NEPA and the regulations in the subpart have been met, with 
respect to the activities to be conducted under the limited work 
authorization;
    (ii) Independently consider the balance among conflicting factors 
with respect to the limited work authorization which is contained in the 
record of the proceeding, with a view to determining the appropriate 
action to be taken;
    (iii) Determine whether the redress plan will adequately redress the 
activities performed under the limited work authorization, should 
limited work activities be terminated by the holder or the limited work 
authorization be revoked by the NRC, or upon effectiveness of the 
Commission's final decision denying the associated construction permit 
or early site permit, as applicable;
    (iv) In an uncontested proceeding, determine whether the NEPA review 
conducted by the NRC staff for the limited work authorization has been 
adequate; and
    (v) In a contested proceeding, determine whether, in accordance with 
the regulations in this subpart, the limited work authorization should 
be issued as proposed.

[[Page 52]]

    (2) If the limited work authorization is for activities to be 
conducted at a site for which the Commission has previously prepared an 
environmental impact statement for the construction and operation of a 
nuclear power plant, and a construction permit was issued but 
construction of the plant was never completed, then in making the 
determinations in paragraph (c)(1) of this section, the presiding 
officer shall be limited to a consideration whether there is, with 
respect to construction activities encompassed by the environmental 
impact statement which are analogous to the activities to be conducted 
under the limited work authorization, new and significant information on 
the environmental impacts of those activities, such that the limited 
work authorization should not be issued as proposed.
    (3) The presiding officer's determination in this paragraph shall be 
made in a partial initial decision to be issued separately from, and in 
advance of, the presiding officer's decision in paragraph (a) of this 
section.

[72 FR 49516, Aug. 28, 2007, as amended at 72 FR 57446, Oct. 9, 2007; 73 
FR 5724, Jan. 31, 2008]



Sec. 51.105a  Public hearings in proceedings for issuance 
of manufacturing licenses.

    In addition to complying with applicable requirements of Sec. 
51.31(c), in a proceeding for the issuance of a manufacturing license, 
the presiding officer will determine whether, in accordance with the 
regulations in this subpart, the manufacturing license should be issued 
as proposed by the NRC's Director, Office of New Reactors or Director, 
Office of Nuclear Reactor Regulation, as appropriate.

[73 FR 5724, Jan. 31, 2008]



Sec. 51.106  Public hearings in proceedings for issuance of operating
licenses.

    (a) Consistent with the requirements of this section and as 
appropriate, the presiding officer in an operating license hearing shall 
comply with any applicable requirements of Sec. Sec. 51.104 and 51.105.
    (b) During the course of a hearing on an application for issuance of 
an operating license for a nuclear power reactor, or a testing facility, 
the presiding officer may authorize, pursuant to Sec. 50.57(c) of this 
chapter, the loading of nuclear fuel in the reactor core and limited 
operation within the scope of Sec. 50.57(c) of this chapter, upon 
compliance with the procedures described therein. In any such hearing, 
where any party opposes such authorization on the basis of matters 
covered by subpart A of this part, the provisions of Sec. Sec. 51.104 
and 51.105 will apply, as appropriate.
    (c) The presiding officer in an operating license hearing shall not 
admit contentions proffered by any party concerning need for power or 
alternative energy sources or alternative sites for the facility for 
which an operating license is requested.
    (d) The presiding officer in an operating license hearing shall not 
raise issues concerning alternative sites for the facility for which an 
operating license is requested sua sponte.



Sec. 51.107  Public hearings in proceedings for issuance of combined
licenses; limited work authorizations.

    (a) In addition to complying with the applicable requirements of 
Sec. 51.104, in a proceeding for the issuance of a combined license for 
a nuclear power reactor under part 52 of this chapter, the presiding 
officer will:
    (1) Determine whether the requirements of Sections 102(2) (A), (C), 
and (E) of NEPA and the regulations in this subpart have been met;
    (2) Independently consider the final balance among conflicting 
factors contained in the record of the proceeding with a view to 
determining the appropriate action to be taken;
    (3) Determine, after weighing the environmental, economic, 
technical, and other benefits against environmental and other costs, and 
considering reasonable alternatives, whether the combined license should 
be issued, denied, or appropriately conditioned to protect environmental 
values;
    (4) Determine, in an uncontested proceeding, whether the NEPA review 
conducted by the NRC staff has been adequate; and

[[Page 53]]

    (5) Determine, in a contested proceeding, whether in accordance with 
the regulations in this subpart, the combined license should be issued 
as proposed by the NRC's Director, Office of New Reactors or Director, 
Office of Nuclear Reactor Regulation, as appropriate.
    (b) If a combined license application references an early site 
permit, then the presiding officer in the combined license hearing shall 
not admit any contention proffered by any party on environmental issues 
which have been accorded finality under Sec. 52.39 of this chapter, 
unless the contention:
    (1) Demonstrates that the nuclear power reactor proposed to be built 
does not fit within one or more of the site characteristics or design 
parameters included in the early site permit;
    (2) Raises any significant environmental issue that was not resolved 
in the early site permit proceeding; or
    (3) Raises any issue involving the impacts of construction and 
operation of the facility that was resolved in the early site permit 
proceeding for which new and significant information has been 
identified.
    (c) If the combined license application references a standard design 
certification, or proposes to use a manufactured reactor, then the 
presiding officer in a combined license hearing shall not admit 
contentions proffered by any party concerning severe accident mitigation 
design alternatives unless the contention demonstrates that the site 
characteristics fall outside of the site parameters in the standard 
design certification or underlying manufacturing license for the 
manufactured reactor.
    (d)(1) In any proceeding for the issuance of a combined license 
where the applicant requests a limited work authorization under Sec. 
50.10(d) of this chapter, the presiding officer, in addition to 
complying with any applicable provision of Sec. 51.104, shall:
    (i) Determine whether the requirements of Section 102(2)(A), (C), 
and (E) of NEPA and the regulations in this subpart have been met, with 
respect to the activities to be conducted under the limited work 
authorization;
    (ii) Independently consider the balance among conflicting factors 
with respect to the limited work authorization which is contained in the 
record of the proceeding, with a view to determining the appropriate 
action to be taken;
    (iii) Determine whether the redress plan will adequately redress the 
activities performed under the limited work authorization, should 
limited work activities be terminated by the holder or the limited work 
authorization be revoked by the NRC, or upon effectiveness of the 
Commission's final decision denying the combined license application;
    (iv) In an uncontested proceeding, determine whether the NEPA review 
conducted by the NRC staff for the limited work authorization has been 
adequate; and
    (v) In a contested proceeding, determine whether, in accordance with 
the regulations in this subpart, the limited work authorization should 
be issued as proposed by the Director of New Reactors or the Director of 
Nuclear Reactor Regulation, as applicable.
    (2) If the limited work authorization is for activities to be 
conducted at a site for which the Commission has previously prepared an 
environmental impact statement for the construction and operation of a 
nuclear power plant, and a construction permit was issued but 
construction of the plant was never completed, then in making the 
determinations in paragraph (c)(1) of this section, the presiding 
officer shall be limited to a consideration whether there is, with 
respect to construction activities encompassed by the environmental 
impact statement which are analogous to the activities to be conducted 
under the limited work authorization, new and significant information on 
the environmental impacts of those activities, so that the limited work 
authorization should not be issued as proposed by the Director of New 
Reactors or the Director of Nuclear Reactor Regulation, as applicable.
    (3) In making the determination required by this section, the 
presiding officer may not address or consider the sunk costs associated 
with the limited work authorization.
    (4) The presiding officer's determination in this paragraph shall be 
made in

[[Page 54]]

a partial initial decision to be issued separately from, and in advance 
of, the presiding officer's decision in paragraph (a) of this section on 
the combined license.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 57446, Oct. 9, 2007; 73 
FR 5724, Jan. 31, 2008]



Sec. 51.108  Public hearings on Commission findings that inspections,
tests, analyses, and acceptance criteria of combined licenses are met.

    In any public hearing requested under 10 CFR 52.103(b), the 
Commission will not admit any contentions on environmental issues, the 
adequacy of the environmental impact statement for the combined license 
issued under subpart C of part 52, or the adequacy of any other 
environmental impact statement or environmental assessment referenced in 
the combined license application. The Commission will not make any 
environmental findings in connection with the finding under 10 CFR 
52.103(g).

[72 FR 49517, Aug. 28, 2007]

                           materials licenses



Sec. 51.109  Public hearings in proceedings for issuance of materials
license with respect to a geologic repository.

    (a)(1) In a proceeding for issuance of a construction authorization 
for a high-level radioactive waste repository at a geologic repository 
operations area under parts 60 and 63 of this chapter, and in a 
proceeding for issuance of a license to receive and possess source, 
special nuclear, and byproduct material at a geologic repository 
operations area under parts 60 and 63 of this chapter, the NRC staff 
shall, upon the publication of the notice of hearing in the Federal 
Register, present its position on whether it is practicable to adopt, 
without further supplementation, the environmental impact statement 
(including any supplement thereto) prepared by the Secretary of Energy. 
If the position of the staff is that supplementation of the 
environmental impact statement by NRC is required, it shall file its 
final supplemental environmental impact statement with the Environmental 
Protection Agency, furnish that statement to commenting agencies, and 
make it available to the public, before presenting its position, or as 
soon thereafter as may be practicable. In discharging its 
responsibilities under this paragraph, the staff shall be guided by the 
principles set forth in paragraphs (c) and (d) of this section.
    (2) Any other party to the proceeding who contends that it is not 
practicable to adopt the DOE environmental impact statement, as it may 
have been supplemented, shall file a contention to that effect within 
thirty (30) days after the publication of the notice of hearing in the 
Federal Register. Such contention must be accompanied by one or more 
affidavits which set forth factual and/or technical bases for the claim 
that, under the principles set forth in paragraphs (c) and (d) of this 
section, it is not practicable to adopt the DOE environmental impact 
statement, as it may have been supplemented. The presiding officer shall 
resolve disputes concerning adoption of the DOE environmental impact 
statement by using, to the extent possible, the criteria and procedures 
that are followed in ruling on motions to reopen under Sec. 2.326 of 
this chapter.
    (b) In any such proceeding, the presiding officer will determine 
those matters in controversy among the parties within the scope of NEPA 
and this subpart, specifically including whether, and to what extent, it 
is practicable to adopt the environmental impact statement prepared by 
the Secretary of Energy in connection with the issuance of a 
construction authorization and license for such repository.
    (c) The presiding officer will find that it is practicable to adopt 
any environmental impact statement prepared by the Secretary of Energy 
in connection with a geologic repository proposed to be constructed 
under Title I of the Nuclear Waste Policy Act of 1982, as amended, 
unless:
    (1)(i) The action proposed to be taken by the Commission differs 
from the action proposed in the license application submitted by the 
Secretary of Energy; and
    (ii) The difference may significantly affect the quality of the 
human environment; or

[[Page 55]]

    (2) Significant and substantial new information or new 
considerations render such environmental impact statement inadequate.
    (d) To the extent that the presiding officer determines it to be 
practicable, in accordance with paragraph (c) of this section, to adopt 
the environmental impact statement prepared by the Secretary of Energy, 
such adoption shall be deemed to satisfy all responsibilities of the 
Commission under NEPA and no further consideration under NEPA or this 
subpart shall be required.
    (e) To the extent that it is not practicable, in accordance with 
paragraph (c) of this section, to adopt the environmental impact 
statement prepared by the Secretary of Energy, the presiding officer 
will:
    (1) Determine whether the requirements of section 102(2) (A), (C), 
and (E) of NEPA and the regulations in this subpart have been met;
    (2) Independently consider the final balance among conflicting 
factors contained in the record of the proceeding with a view to 
determining the appropriate action to be taken;
    (3) Determine, after weighing the environmental, economic, technical 
and other benefits against environmental and other costs, whether the 
construction authorization or license should be issued, denied, or 
appropriately conditioned to protect environmental values;
    (4) Determine, in an uncontested proceeding, whether the NEPA review 
conducted by the NRC staff has been adequate; and
    (5) Determine, in a contested proceeding, whether in accordance with 
the regulations in this subpart, the construction authorization or 
license should be issued as proposed.
    (f) In making the determinations described in paragraph (e) of this 
section, the environmental impact statement will be deemed modified to 
the extent that findings and conclusions differ from those in the final 
statement prepared by the Secretary of Energy, as it may have been 
supplemented. The initial decision will be distributed to any persons 
not otherwise entitled to receive it who responded to the request in the 
notice of docketing, as described in Sec. 51.26(c). If the Commission 
reaches conclusions different from those of the presiding officer with 
respect to such matters, the final environmental impact statement will 
be deemed modified to that extent and the decision will be similarly 
distributed.
    (g) The provisions of this section shall be followed, in place of 
those set out in Sec. 51.104, in any proceedings for the issuance of a 
license to receive and possess source, special nuclear, and byproduct 
material at a geologic repository operations area.

[54 FR 27870, July 3, 1989, as amended at 69 FR 2276, Jan. 14, 2004; 77 
FR 46600, Aug. 3, 2012]

                               rulemaking



Sec. 51.110  [Reserved]

         Public Notice of and Access to Environmental Documents



Sec. 51.116  Notice of intent.

    (a) In accordance with Sec. 51.26, the appropriate NRC staff 
director will publish in the Federal Register a notice of intent stating 
that an environmental impact statement will be prepared. The notice will 
contain the information specified in Sec. 51.27.
    (b) Copies of the notice will be sent to appropriate Federal, State, 
and local agencies, and Indian Tribes, appropriate State, regional, and 
metropolitan clearinghouses and to interested persons upon request. A 
public announcement of the notice of intent will also be made.



Sec. 51.117  Draft environmental impact statement--notice of availability.

    (a) Upon completion of a draft environmental impact statement or any 
supplement to a draft environmental impact statement, the appropriate 
NRC staff director will publish a notice of availability of the 
statement in the Federal Register.
    (b) The notice will request comments on the proposed action and on 
the draft statement or any supplement to the draft statement and will 
specify where comments should be submitted and when the comment period 
expires.
    (c) The notice will (1) state that copies of the draft statement or 
any supplement to the draft statement are

[[Page 56]]

available for public inspection; (2) state where inspection may be made, 
and (3) state that any comments of Federal, State, and local agencies, 
Indian Tribes or other interested persons will be made available for 
public inspection when received.
    (d) Copies of the notice will be sent to appropriate Federal, State, 
and local agencies, and Indian Tribes, appropriate State, regional, and 
metropolitan clearinghouses, and to interested persons upon request.



Sec. 51.118  Final environmental impact statement--notice of 
availability.

    (a) Upon completion of a final environmental impact statement or any 
supplement to a final environmental impact statement, the appropriate 
NRC staff director will publish a notice of availability of the 
statement in the Federal Register. The notice will state that copies of 
the final statement or any supplement to the final statement are 
available for public inspection and where inspection may be made. Copies 
of the notice will be sent to appropriate Federal, State, and local 
agencies, and Indian Tribes, appropriate State, regional, and 
metropolitan clearinghouses and to interested persons upon request.
    (b) Upon adoption of a final environmental impact statement or any 
supplement to a final environmental impact statement prepared by the 
Department of Energy with respect to a geologic repository that is 
subject to the Nuclear Waste Policy Act of 1982, the appropriate NRC 
staff director shall follow the procedures set out in paragraph (a) of 
this section.

[49 FR 9381, Mar. 12, 1984, as amended at 54 FR 27871, July 3, 1989]



Sec. 51.119  Publication of finding of no significant impact;
distribution.

    (a) As required by Sec. 51.35, the appropriate NRC staff director 
will publish the finding of no significant impact in the Federal 
Register. The finding of no significant impact will be identified as a 
draft or final finding, and will contain the information specified in 
Sec. Sec. 51.32 or 51.33, as appropriate. A draft finding of no 
significant impact will include a request for comments which specifies 
where comments should be submitted and when the comment period expires.
    (b) The finding will state that copies of the finding, the 
environmental assessment setting forth the basis for the finding and any 
related environmental documents are available for public inspection and 
where inspection may be made.
    (c) A copy of a final finding will be sent to appropriate Federal, 
State, and local agencies, and Indian Tribes, appropriate State, 
regional, and metropolitan clearinghouses, the applicant or petitioner 
for rulemaking and any other party to the proceeding, and if a draft 
finding was issued, to each commenter. Additional copies will be made 
available in accordance with Sec. 51.123.



Sec. 51.120  Availability of environmental documents for public
inspection.

    Copies of environmental reports, draft and final environmental 
impact statements, environmental assessments, and findings of no 
significant impact, together with any related comments and environmental 
documents, will be made available at the NRC Web site, http://
www.nrc.gov, and/or at the NRC Public Document Room.

[64 FR 48952, Sept. 9, 1999]



Sec. 51.121  Status of NEPA actions.

    Individuals or organizations desiring information on the NRC's NEPA 
process or on the status of specific NEPA actions should address 
inquiries to:
    (a) Utilization facilities: ATTN: Document Control Desk, Director, 
Office of Nuclear Reactor Regulation or Director, Office of New 
Reactors, as appropriate, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, telephone (301) 415-1270, e-mail 
[email protected].
    (b) Production facilities: ATTN: Document Control Desk, Director, 
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
7800, e-mail [email protected].
    (c) Materials licenses: ATTN: Document Control Desk, Director, 
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001,

[[Page 57]]

telephone (301) 415-7800, e-mail [email protected].
    (d) Rulemaking: ATTN: Rules, Announcements, and Directives Branch, 
Office of Administration, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, telephone (800) 368-5642.
    (e) General environmental matters: Executive Director for 
Operations, U.S. Nuclear Regulatory Commission, Washington, DC 20555, 
Telephone: (301) 415-1700.

[53 FR 13399, Apr. 25, 1988, as amended at 60 FR 24552, May 9, 1995; 68 
FR 58811, Oct. 10, 2003; 73 FR 5724, Jan. 31, 2008; 77 FR 39907, July 6, 
2012]



Sec. 51.122  List of interested organizations and groups.

    The NRC Office of the Chief Information Officer will maintain a 
master list of organizations and groups, including relevant conservation 
commissions, known to be interested in the Commission's licensing and 
regulatory activities. The NRC Office of the Chief Information Officer 
with the assistance of the appropriate NRC staff director will select 
from this master list those organizations and groups that may have an 
interest in a specific NRC NEPA action and will promptly notify such 
organizations and groups of the availability of a draft environmental 
impact statement or a draft finding of no significant impact.

[49 FR 9381, Mar. 12, 1984, as amended at 52 FR 31612, Aug. 21, 1987; 54 
FR 53316, Dec. 28, 1989; 77 FR 39907, July 6, 2012]



Sec. 51.123  Charges for environmental documents; distribution to 
public; distribution to governmental agencies.

    (a) Distribution to public. Upon written request to the Office of 
the Chief Information Officer, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, e-mail [email protected], and to 
the extent available, single copies of draft environmental impact 
statements and draft findings of no significant impact will be made 
available to interested persons without charge. Single copies of final 
environmental impact statements and final findings of no significant 
impact will also be provided without charge to the persons listed in 
Sec. Sec. 51.93(a) and 51.119(c), respectively. When more than one copy 
of an environmental impact statement or a finding of no significant 
impact is requested or when available NRC copies have been exhausted, 
the requestor will be advised that the NRC will provide copies at the 
charges specified in Sec. 9.35 of this chapter.
    (b) Distribution to governmental agencies. Upon written request to 
the Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, e-mail 
[email protected], and to the extent available, copies of 
draft and final environmental impact statements and draft final findings 
of no significant impact will be made available in the number requested 
to Federal, State and local agencies, Indian Tribes, and State, 
regional, and metropolitan clearinghouses. When available NRC copies 
have been exhausted, the requester will be advised that the NRC will 
provide copies at the charges specified in Sec. 9.35 of this chapter.
    (c) Charges. Charges for the reproduction of environmental documents 
by the NRC at locations other than the NRC Public Document Room located 
in Washington, DC vary according to location.

[50 FR 21037, May 22, 1985, as amended at 52 FR 31612, Aug. 21, 1987; 53 
FR 43421, Oct. 27, 1988; 61 FR 9902, Mar. 12, 1996; 64 FR 48952, Sept. 
9, 1999; 68 FR 58812, Oct. 10, 2003; 80 FR 74980, Dec. 1, 2015]

                               Commenting



Sec. 51.124  Commission duty to comment.

    It is the policy of the Commission to comment on draft environmental 
impact statements prepared by other Federal agencies, consistent with 
the provisions of 40 CFR 1503.2 and 1503.3.

                          Responsible Official



Sec. 51.125  Responsible official.

    The Executive Director for Operations shall be responsible for 
overall review of NRC NEPA compliance, except for matters under the 
jurisdiction of a presiding officer, administrative judge, 
administrative law judge, Atomic Safety and Licensing Board, or the 
Commission acting as a collegial body.

[77 FR 46600, Aug. 3, 2012]

[[Page 58]]



  Sec. Appendix A to Subpart A of Part 51--Format for Presentation of 
               Material in Environmental Impact Statements

1. General
2. Cover sheet
3. Summary
4. Purpose of and need for action
5. Alternatives including the proposed action
6. Affected environment
7. Environmental consequences and mitigating actions
8. List of preparers
9. Appendices

                               1. General.

    (a) The Commission will use a format for environmental impact 
statements which will encourage good analysis and clear presentation of 
the alternatives including the proposed action. The following standard 
format for environmental impact statements should be followed unless 
there is a compelling reason to do otherwise:
    (1) Cover sheet*
    (2) Summary*
    (3) Table of Contents
    (4) Purpose of and Need for Action*
    (5) Alternatives including the proposed action*
    (6) Affected Environment*
    (7) Environmental Consequences and Mitigating Actions*
    (8) List of Preparers*
    (9) List of Agencies, Organizations and Persons to Whom Copies of 
the Statement are Sent
    (10) Substantive Comments Received and NRC Staff Responses
    (11) Index
    (12) Appendices (if any)*
    If a different format is used, it shall include paragraphs (1), (2), 
(3), (8), (9), (10), and (11) of this section and shall include the 
substance of paragraphs (4), (5), (6), (7), and (12) of this section, in 
any appropriate format.
    Additional guidance on the presentation of material under the format 
headings identified by an asterisk is set out in sections 2.-9. of this 
appendix.
    (b) The techniques of tiering and incorporation by reference 
described respectively in 40 CFR 1502.20 and 1508.28 and 40 CFR 1502.21 
\1\ of CEQ's NEPA regulations may be used as appropriate to aid in the 
presentation of issues, eliminate repetition or reduce the size of an 
environmental impact statement. In appropriate circumstances, draft or 
final environmental impact statements prepared by other Federal agencies 
may be adopted in whole or in part in accordance with the procedures 
outlined in 40 CFR 1506.3 \2\ of CEQ's NEPA regulations. In final 
environmental impact statements, material under the following format 
headings will normally be presented in less than 150 pages: Purpose of 
and Need for Action, Alternatives Including the Proposed Action, 
Affected Environment, and Environmental Consequences and Mitigating 
Actions. For proposals of unusual scope or complexity, the material 
presented under these format headings may extend to 300 pages.
---------------------------------------------------------------------------

    \1\ Tiering--40 CFR 1502.20, 40 CFR 1508.28; Incorporation by 
reference--40 CFR 1502.21.
    \2\ Adoption--40 CFR 1506.3.
---------------------------------------------------------------------------

                             2. Cover sheet.

    The cover sheet will not exceed one page. It will include:
    (a) The name of the NRC office responsible for preparing the 
statement and a list of any cooperating agencies.
    (b) The title of the proposed action that is the subject of the 
statement with a list of the states, counties or municipalities where 
the facility or other subject of the action is located, as appropriate.
    (c) The name, address, and telephone number of the individual in NRC 
who can supply further information.
    (d) A designation of the statement as a draft or final statement, or 
a draft or final supplement.
    (e) A one paragraph abstract of the statement.
    (f) For draft environmental impact statements, the date by which 
comments must be received. This date may be specified in the form of the 
following or a substantially similar statement:
    ``Comments should be filed no later than \3\ days after the date on 
which the Environmental Protection Agency notice stating that the draft 
environmental impact statement has been filed with EPA is published in 
the Federal Register. Comments received after the expiration of the 
comment period will be considered if it is practical to do so but 
assurance of consideration of late comments cannot be given.''
---------------------------------------------------------------------------

    \3\ The number of days in the comment period should be inserted. The 
minimum comment period is 45 days (see Sec. 51.73.)
---------------------------------------------------------------------------

                               3. Summary.

    Each environmental impact statement will contain a summary which 
adequately and accurately summarizes the statement. The summary will 
stress the major issues considered. The summary will discuss the areas 
of controversy, will identify any remaining issues to be resolved, and 
will present the major conclusions and recommendations. The summary will 
normally not exceed 15 pages.

[[Page 59]]

                   4. Purpose of and need for action.

    The statement will briefly describe and specify the need for the 
proposed action. The alternative of no action will be discussed. In the 
case of nuclear power plant construction or siting, consideration will 
be given to the potential impact of conservation measures in determining 
the demand for power and consequent need for additional generating 
capacity.

             5. Alternatives including the proposed action.

    This section is the heart of the environmental impact statement. It 
will present the environmental impacts of the proposal and the 
alternatives in comparative form. Where important to the comparative 
evaluation of alternatives, appropriate mitigating measures of the 
alternatives will be discussed. All reasonable alternatives will be 
identified. The range of alternatives discussed will encompass those 
proposed to be considered by the ultimate decisionmaker. An otherwise 
reasonable alternative will not be excluded from discussion solely on 
the ground that it is not within the jurisdiction of the NRC. \4\ The 
discussion of alternatives will take into accounts, without duplicating, 
the environmental information and analyses included in sections, 4., 6. 
and 7. of this appendix.
---------------------------------------------------------------------------

    \4\ With respect to limitations on NRC's NEPA authority and 
responsibility imposed by the Federal Water Pollution Control Act 
Amendments of 1972, see Sec. Sec. 51.10(c), 51.22(c)(17) and 51.71(d).
---------------------------------------------------------------------------

    In the draft environmental impact statement, this section will 
either include a preliminary recommendation on the action to be taken, 
or identify the alternatives under consideration.
    In the final environmental impact statement, this section will 
include a final recommendation on the action to be taken.

                        6. Affected environment.

    The environmental impact statement will succinctly describe the 
environment to be affected by the proposed action. Data and analyses in 
the statement will be commensurate with the importance of the impact, 
with less important material summarized, consolidated, or simply 
referenced. Effort and attention will be concentrated on important 
issues; useless bulk will be eliminated.

          7. Environmental consequences and mitigating actions.

    This section discusses the environmental consequences of 
alternatives, including the proposed actions and any mitigating actions 
which may be taken. Alternatives eliminated from detailed study will be 
identified and a discussion of those alternatives will be confined to a 
brief statement of the reasons why the alternatives were eliminated. The 
level of information for each alternative considered in detail will 
reflect the depth of analysis required for sound decisionmaking.
    The discussion will include any adverse environmental effects which 
cannot be avoided should the alternative be implemented, the 
relationship between short-term uses of man's environment and the 
maintenance and enhancement of long-term productivity, and any 
irreversible or irretrievable commitments of resources which would be 
involved in the alternative should it be implemented. This section will 
include discussions of:
    (a) Direct effects and their significance.
    (b) Indirect effects and their significance.
    (c) Possible conflicts between the alternative and the objectives of 
Federal, regional, State, and local (and in the case of a reservation, 
Indian Tribe) land use plans, policies and controls for the area 
concerned.
    (d) Means to mitigate adverse environmental impacts.

                          8. List of preparers.

    The environmental impact statement will list the names and 
qualifications (expertise, experience, professional disciplines), of the 
persons who were primarily responsible for preparing the environmental 
impact statement or significant background papers. Persons responsible 
for making an independent evaluation of information submitted by the 
applicant or petitioner for rulemaking or others will be included in the 
list. Where possible, the persons who are responsible for a particular 
analysis, including analyses in background papers, will be identified.

                             9. Appendices.

    An appendix to an environmental impact statement will:
    (a) Consist of material prepared in connection with an environmental 
impact statement (as distinct from material which is not so prepared and 
which is incorporated by reference (40 CFR 1502.21)).
    (b) Normally consist of material which substantiates any analysis 
fundamental to the impact statement. Discussion of methodology used may 
be placed in an appendix.
    (c) Normally be analytic.
    (d) Be relevant to the decision to be made.
    (e) Be circulated with the environmental impact statement or be 
readily available on request.

                         Discussion of Footnotes

                               1. Tiering.

    40 CFR 1502.20 states:
    ``Agencies are encouraged to tier their environmental impact 
statements to eliminate repetitive discussions of the same issues and to 
focus on the actual issues ripe for decision at each level of 
environmental review

[[Page 60]]

(Sec. 1508.28). Whenever a broad environmental impact statement has 
been prepared (such as a program or policy statement) and a subsequent 
statement or environmental assessment is then prepared on an action 
included within the entire program or policy (such as a site specific 
action) the subsequent statement or environmental assessment need only 
summarize the issues discussed in the broader statement and incorporate 
discussions from the broader statement by reference and shall 
concentrate on the issues specific to the subsequent action. The 
subsequent document shall state where the earlier document is available. 
Tiering may also be appropriate for different stages of actions. (Sec. 
1508.28).''
    40 CFR 1508.28 states:
    `` `Tiering' refers to the coverage of general matters in broader 
environmental impact statements (such as national program or policy 
statements) with subsequent narrower statements or environmental 
analyses (such as regional or basinwide program statements or ultimately 
site-specific statements) incorporating by reference the general 
discussions and concentrating solely on the issues specific to the 
statement subsequently prepared. Tiering is appropriate when the 
sequence of statements or analyses is:
    ``(a) From a program, plan, or policy environmental impact statement 
to a program, plan, or policy statement or analysis of lesser scope or 
to a site-specific statement or analysis.
    ``(b) From an environmental impact statement on a specific action at 
an early stage (such as need and site selection) to a supplement (which 
is preferred) or a subsequent statement or analysis at a later stage 
(such as environmental mitigation). Tiering in such cases is appropriate 
when it helps the lead agency to focus on the issues which are ripe for 
decision and exclude from consideration issues already decided or not 
yet ripe.''
    Incorporation by reference. 40 CFR 1502.21 states:
    ``Agencies shall incorporate material into an environmental impact 
statement by reference when the effect will be to cut down on bulk 
without impeding agency and public review of the action. The 
incorporated material shall be cited in the statement and its content 
briefly described. No material may be incorporated by reference unless 
it is reasonably available for inspection by potentially interested 
persons within the time allowed for comment. Material based on 
proprietary data which is itself not available for review and comment 
shall not be incorporated by reference.''

                              2. Adoption.

    40 CFR 1506.3 states:
    ``(a) An agency may adopt a Federal draft or final environmental 
impact statement or portion thereof provided that the statement or 
portion thereof meets the standards for an adequate statement under 
these regulations.
    ``(b) If the actions covered by the original environmental impact 
statement and the proposed action are substantially the same, the agency 
adopting another agency's statement is not required to recirculate it 
except as a final statement. Otherwise the adopting agency shall treat 
the statement as a draft and recirculate it (except as provided in 
paragraph (c) of this section).
    ``(c) A cooperating agency may adopt without recirculating the 
environmental impact statement of a lead agency when, after an 
independent review of the statement, the cooperating agency concludes 
that its comments and suggestions have been satisfied.
    ``(d) When an agency adopts a statement which is not final within 
the agency that prepared it, or when the action it assesses is the 
subject of a referral under part 1504, or when the statement's adequacy 
is the subject of a judicial action which is not final, the agency shall 
so specify.''

[49 FR 9381, Mar. 12, 1984, as amended at 61 FR 28490, June 5, 1996; 61 
FR 66546, Dec. 18, 1996]



    Sec. Appendix B to Subpart A of Part 51--Environmental Effect of 
         Renewing the Operating License of a Nuclear Power Plant

    The Commission has assessed the environmental impacts associated 
with granting a renewed operating license for a nuclear power plant to a 
licensee who holds either an operating license or construction permit as 
of June 30, 1995. Table B-1 summarizes the Commission's findings on the 
scope and magnitude of environmental impacts of renewing the operating 
license for a nuclear power plant as required by section 102(2) of the 
National Environmental Policy Act of 1969, as amended. Table B-1, 
subject to an evaluation of those issues identified in Category 2 as 
requiring further analysis and possible significant new information, 
represents the analysis of the environmental impacts associated with 
renewal of any operating license and is to be used in accordance with 
Sec. 51.95(c). On a 10-year cycle, the Commission intends to review the 
material in this appendix and update it if necessary. A scoping notice 
must be published in the Federal Register indicating the results of the 
NRC's review and inviting public comments and proposals for other areas 
that should be updated.

[[Page 61]]



          Table B-1--Summary of Findings on NEPA Issues for License Renewal of Nuclear Power Plants \1\
----------------------------------------------------------------------------------------------------------------
                                               Category
                   Issue                         \2\                            Finding \3\
----------------------------------------------------------------------------------------------------------------
                                                    Land Use
----------------------------------------------------------------------------------------------------------------
Onsite land use............................            1  SMALL. Changes in onsite land use from continued
                                                           operations and refurbishment associated with license
                                                           renewal would be a small fraction of the nuclear
                                                           power plant site and would involve only land that is
                                                           controlled by the licensee.
Offsite land use...........................            1  SMALL. Offsite land use would not be affected by
                                                           continued operations and refurbishment associated
                                                           with license renewal.
Offsite land use in transmission line right-           1  SMALL. Use of transmission line ROWs from continued
 of-ways (ROWs) \4\.                                       operations and refurbishment associated with license
                                                           renewal would continue with no change in land use
                                                           restrictions.
----------------------------------------------------------------------------------------------------------------
                                                Visual Resources
----------------------------------------------------------------------------------------------------------------
Aesthetic impacts..........................            1  SMALL. No important changes to the visual appearance
                                                           of plant structures or transmission lines are
                                                           expected from continued operations and refurbishment
                                                           associated with license renewal.
----------------------------------------------------------------------------------------------------------------
                                                   Air Quality
----------------------------------------------------------------------------------------------------------------
Air quality impacts (all plants)...........            1  SMALL. Air quality impacts from continued operations
                                                           and refurbishment associated with license renewal are
                                                           expected to be small at all plants. Emissions
                                                           resulting from refurbishment activities at locations
                                                           in or near air quality nonattainment or maintenance
                                                           areas would be short-lived and would cease after
                                                           these refurbishment activities are completed.
                                                           Operating experience has shown that the scale of
                                                           refurbishment activities has not resulted in
                                                           exceedance of the de minimis thresholds for criteria
                                                           pollutants, and best management practices including
                                                           fugitive dust controls and the imposition of permit
                                                           conditions in State and local air emissions permits
                                                           would ensure conformance with applicable State or
                                                           Tribal Implementation Plans.
                                                          Emissions from emergency diesel generators and fire
                                                           pumps and routine operations of boilers used for
                                                           space heating would not be a concern, even for plants
                                                           located in or adjacent to nonattainment areas.
                                                           Impacts from cooling tower particulate emissions even
                                                           under the worst-case situations have been small.
Air quality effects of transmission lines              1  SMALL. Production of ozone and oxides of nitrogen is
 \4\.                                                      insignificant and does not contribute measurably to
                                                           ambient levels of these gases.
----------------------------------------------------------------------------------------------------------------
                                                      Noise
----------------------------------------------------------------------------------------------------------------
Noise impacts..............................            1  SMALL. Noise levels would remain below regulatory
                                                           guidelines for offsite receptors during continued
                                                           operations and refurbishment associated with license
                                                           renewal.
----------------------------------------------------------------------------------------------------------------
                                              Geologic Environment
----------------------------------------------------------------------------------------------------------------
Geology and soils..........................            1  SMALL. The effect of geologic and soil conditions on
                                                           plant operations and the impact of continued
                                                           operations and refurbishment activities on geology
                                                           and soils would be small for all nuclear power plants
                                                           and would not change appreciably during the license
                                                           renewal term.
----------------------------------------------------------------------------------------------------------------
                                             Surface Water Resources
----------------------------------------------------------------------------------------------------------------
Surface water use and quality (non-cooling             1  SMALL. Impacts are expected to be small if best
 system impacts).                                          management practices are employed to control soil
                                                           erosion and spills. Surface water use associated with
                                                           continued operations and refurbishment associated
                                                           with license renewal would not increase significantly
                                                           or would be reduced if refurbishment occurs during a
                                                           plant outage.
Altered current patterns at intake and                 1  SMALL. Altered current patterns would be limited to
 discharge structures.                                     the area in the vicinity of the intake and discharge
                                                           structures. These impacts have been small at
                                                           operating nuclear power plants.
Altered salinity gradients.................            1  SMALL. Effects on salinity gradients would be limited
                                                           to the area in the vicinity of the intake and
                                                           discharge structures. These impacts have been small
                                                           at operating nuclear power plants.
Altered thermal stratification of lakes....            1  SMALL. Effects on thermal stratification would be
                                                           limited to the area in the vicinity of the intake and
                                                           discharge structures. These impacts have been small
                                                           at operating nuclear power plants.
Scouring caused by discharged cooling water            1  SMALL. Scouring effects would be limited to the area
                                                           in the vicinity of the intake and discharge
                                                           structures. These impacts have been small at
                                                           operating nuclear power plants.

[[Page 62]]

 
Discharge of metals in cooling system                  1  SMALL. Discharges of metals have not been found to be
 effluent.                                                 a problem at operating nuclear power plants with
                                                           cooling-tower-based heat dissipation systems and have
                                                           been satisfactorily mitigated at other plants.
                                                           Discharges are monitored and controlled as part of
                                                           the National Pollutant Discharge Elimination System
                                                           (NPDES) permit process.
Discharge of biocides, sanitary wastes, and            1  SMALL. The effects of these discharges are regulated
 minor chemical spills.                                    by Federal and State environmental agencies.
                                                           Discharges are monitored and controlled as part of
                                                           the NPDES permit process. These impacts have been
                                                           small at operating nuclear power plants.
Surface water use conflicts (plants with               1  SMALL. These conflicts have not been found to be a
 once-through cooling systems).                            problem at operating nuclear power plants with once-
                                                           through heat dissipation systems.
Surface water use conflicts (plants with               2  SMALL or MODERATE. Impacts could be of small or
 cooling ponds or cooling towers using                     moderate significance, depending on makeup water
 makeup water from a river).                               requirements, water availability, and competing water
                                                           demands.
Effects of dredging on surface water                   1  SMALL. Dredging to remove accumulated sediments in the
 quality.                                                  vicinity of intake and discharge structures and to
                                                           maintain barge shipping has not been found to be a
                                                           problem for surface water quality. Dredging is
                                                           performed under permit from the U.S. Army Corps of
                                                           Engineers, and possibly, from other State or local
                                                           agencies.
Temperature effects on sediment transport              1  SMALL. These effects have not been found to be a
 capacity.                                                 problem at operating nuclear power plants and are not
                                                           expected to be a problem.
----------------------------------------------------------------------------------------------------------------
                                              Groundwater Resources
----------------------------------------------------------------------------------------------------------------
Groundwater contamination and use (non-                1  SMALL. Extensive dewatering is not anticipated from
 cooling system impacts).                                  continued operations and refurbishment associated
                                                           with license renewal. Industrial practices involving
                                                           the use of solvents, hydrocarbons, heavy metals, or
                                                           other chemicals, and/or the use of wastewater ponds
                                                           or lagoons have the potential to contaminate site
                                                           groundwater, soil, and subsoil. Contamination is
                                                           subject to State or Environmental Protection Agency
                                                           regulated cleanup and monitoring programs. The
                                                           application of best management practices for handling
                                                           any materials produced or used during these
                                                           activities would reduce impacts.
Groundwater use conflicts (plants that                 1  SMALL. Plants that withdraw less than 100 gpm are not
 withdraw less than 100 gallons per minute                 expected to cause any groundwater use conflicts.
 [gpm]).
Groundwater use conflicts (plants that                 2  SMALL, MODERATE, or LARGE. Plants that withdraw more
 withdraw more than 100 gallons per minute                 than 100 gpm could cause groundwater use conflicts
 [gpm]).                                                   with nearby groundwater users.
Groundwater use conflicts (plants with                 2  SMALL, MODERATE, or LARGE. Water use conflicts could
 closed-cycle cooling systems that withdraw                result from water withdrawals from rivers during low-
 makeup water from a river).                               flow conditions, which may affect aquifer recharge.
                                                           The significance of impacts would depend on makeup
                                                           water requirements, water availability, and competing
                                                           water demands.
Groundwater quality degradation resulting              1  SMALL. Groundwater withdrawals at operating nuclear
 from water withdrawals.                                   power plants would not contribute significantly to
                                                           groundwater quality degradation.
Groundwater quality degradation (plants                1  SMALL. Sites with closed-cycle cooling ponds could
 with cooling ponds in salt marshes).                      degrade groundwater quality. However, groundwater in
                                                           salt marshes is naturally brackish and thus, not
                                                           potable. Consequently, the human use of such
                                                           groundwater is limited to industrial purposes.
Groundwater quality degradation (plants                2  SMALL, MODERATE, or LARGE. Inland sites with closed-
 with cooling ponds at inland sites).                      cycle cooling ponds could degrade groundwater
                                                           quality. The significance of the impact would depend
                                                           on cooling pond water quality, site hydrogeologic
                                                           conditions (including the interaction of surface
                                                           water and groundwater), and the location, depth, and
                                                           pump rate of water wells.
Radionuclides released to groundwater......            2  SMALL or MODERATE. Leaks of radioactive liquids from
                                                           plant components and pipes have occurred at numerous
                                                           plants. Groundwater protection programs have been
                                                           established at all operating nuclear power plants to
                                                           minimize the potential impact from any inadvertent
                                                           releases. The magnitude of impacts would depend on
                                                           site-specific characteristics.
----------------------------------------------------------------------------------------------------------------
                                              Terrestrial Resources
----------------------------------------------------------------------------------------------------------------
Effects on terrestrial resources (non-                 2  SMALL, MODERATE, or LARGE. Impacts resulting from
 cooling system impacts).                                  continued operations and refurbishment associated
                                                           with license renewal may affect terrestrial
                                                           communities. Application of best management practices
                                                           would reduce the potential for impacts. The magnitude
                                                           of impacts would depend on the nature of the
                                                           activity, the status of the resources that could be
                                                           affected, and the effectiveness of mitigation.

[[Page 63]]

 
Exposure of terrestrial organisms to                   1  SMALL. Doses to terrestrial organisms from continued
 radionuclides.                                            operations and refurbishment associated with license
                                                           renewal are expected to be well below exposure
                                                           guidelines developed to protect these organisms.
Cooling system impacts on terrestrial                  1  SMALL. No adverse effects to terrestrial plants or
 resources (plants with once-through                       animals have been reported as a result of increased
 cooling systems or cooling ponds).                        water temperatures, fogging, humidity, or reduced
                                                           habitat quality. Due to the low concentrations of
                                                           contaminants in cooling system effluents, uptake and
                                                           accumulation of contaminants in the tissues of
                                                           wildlife exposed to the contaminated water or aquatic
                                                           food sources are not expected to be significant
                                                           issues.
Cooling tower impacts on vegetation (plants            1  SMALL. Impacts from salt drift, icing, fogging, or
 with cooling towers).                                     increased humidity associated with cooling tower
                                                           operation have the potential to affect adjacent
                                                           vegetation, but these impacts have been small at
                                                           operating nuclear power plants and are not expected
                                                           to change over the license renewal term.
Bird collisions with plant structures and              1  SMALL. Bird collisions with cooling towers and other
 transmission lines \4\.                                   plant structures and transmission lines occur at
                                                           rates that are unlikely to affect local or migratory
                                                           populations and the rates are not expected to change.
Water use conflicts with terrestrial                   2  SMALL or MODERATE. Impacts on terrestrial resources in
 resources (plants with cooling ponds or                   riparian communities affected by water use conflicts
 cooling towers using makeup water from a                  could be of moderate significance.
 river).
Transmission line right-of-way (ROW)                   1  SMALL. Continued ROW management during the license
 management impacts on terrestrial                         renewal term is expected to keep terrestrial
 resources \4\.                                            communities in their current condition. Application
                                                           of best management practices would reduce the
                                                           potential for impacts.
Electromagnetic fields on flora and fauna              1  SMALL. No significant impacts of electromagnetic
 (plants, agricultural crops, honeybees,                   fields on terrestrial flora and fauna have been
 wildlife, livestock) \4\.                                 identified. Such effects are not expected to be a
                                                           problem during the license renewal term.
----------------------------------------------------------------------------------------------------------------
                                                Aquatic Resources
----------------------------------------------------------------------------------------------------------------
Impingement and entrainment of aquatic                 2  SMALL, MODERATE, or LARGE. The impacts of impingement
 organisms (plants with once-through                       and entrainment are small at many plants but may be
 cooling systems or cooling ponds).                        moderate or even large at a few plants with once-
                                                           through and cooling-pond cooling systems, depending
                                                           on cooling system withdrawal rates and volumes and
                                                           the aquatic resources at the site.
Impingement and entrainment of aquatic                 1  SMALL. Impingement and entrainment rates are lower at
 organisms (plants with cooling towers).                   plants that use closed-cycle cooling with cooling
                                                           towers because the rates and volumes of water
                                                           withdrawal needed for makeup are minimized.
Entrainment of phytoplankton and                       1  SMALL. Entrainment of phytoplankton and zooplankton
 zooplankton (all plants).                                 has not been found to be a problem at operating
                                                           nuclear power plants and is not expected to be a
                                                           problem during the license renewal term.
Thermal impacts on aquatic organisms                   2  SMALL, MODERATE, or LARGE. Most of the effects
 (plants with once-through cooling systems                 associated with thermal discharges are localized and
 or cooling ponds).                                        are not expected to affect overall stability of
                                                           populations or resources. The magnitude of impacts,
                                                           however, would depend on site-specific thermal plume
                                                           characteristics and the nature of aquatic resources
                                                           in the area.
Thermal impacts on aquatic organisms                   1  SMALL. Thermal effects associated with plants that use
 (plants with cooling towers).                             cooling towers are expected to be small because of
                                                           the reduced amount of heated discharge.
Infrequently reported thermal impacts (all             1  SMALL. Continued operations during the license renewal
 plants).                                                  term are expected to have small thermal impacts with
                                                           respect to the following:
                                                          Cold shock has been satisfactorily mitigated at
                                                           operating nuclear plants with once-through cooling
                                                           systems, has not endangered fish populations or been
                                                           found to be a problem at operating nuclear power
                                                           plants with cooling towers or cooling ponds, and is
                                                           not expected to be a problem.
                                                          Thermal plumes have not been found to be a problem at
                                                           operating nuclear power plants and are not expected
                                                           to be a problem.
                                                          Thermal discharge may have localized effects but is
                                                           not expected to affect the larger geographical
                                                           distribution of aquatic organisms.
                                                          Premature emergence has been found to be a localized
                                                           effect at some operating nuclear power plants but has
                                                           not been a problem and is not expected to be a
                                                           problem.
                                                          Stimulation of nuisance organisms has been
                                                           satisfactorily mitigated at the single nuclear power
                                                           plant with a once-through cooling system where
                                                           previously it was a problem. It has not been found to
                                                           be a problem at operating nuclear power plants with
                                                           cooling towers or cooling ponds and is not expected
                                                           to be a problem.

[[Page 64]]

 
Effects of cooling water discharge on                  1  SMALL. Gas supersaturation was a concern at a small
 dissolved oxygen, gas supersaturation, and                number of operating nuclear power plants with once-
 eutrophication.                                           through cooling systems but has been mitigated. Low
                                                           dissolved oxygen was a concern at one nuclear power
                                                           plant with a once-through cooling system but has been
                                                           mitigated. Eutrophication (nutrient loading) and
                                                           resulting effects on chemical and biological oxygen
                                                           demands have not been found to be a problem at
                                                           operating nuclear power plants.
Effects of non-radiological contaminants on            1  SMALL. Best management practices and discharge
 aquatic organisms.                                        limitations of NPDES permits are expected to minimize
                                                           the potential for impacts to aquatic resources during
                                                           continued operations and refurbishment associated
                                                           with license renewal. Accumulation of metal
                                                           contaminants has been a concern at a few nuclear
                                                           power plants but has been satisfactorily mitigated by
                                                           replacing copper alloy condenser tubes with those of
                                                           another metal.
Exposure of aquatic organisms to                       1  SMALL. Doses to aquatic organisms are expected to be
 radionuclides.                                            well below exposure guidelines developed to protect
                                                           these aquatic organisms.
Effects of dredging on aquatic organisms...            1  SMALL. Dredging at nuclear power plants is expected to
                                                           occur infrequently, would be of relatively short
                                                           duration, and would affect relatively small areas.
                                                           Dredging is performed under permit from the U.S. Army
                                                           Corps of Engineers, and possibly, from other State or
                                                           local agencies.
Water use conflicts with aquatic resources             2  SMALL or MODERATE. Impacts on aquatic resources in
 (plants with cooling ponds or cooling                     stream communities affected by water use conflicts
 towers using makeup water from a river).                  could be of moderate significance in some situations.
Effects on aquatic resources (non-cooling              1  SMALL. Licensee application of appropriate mitigation
 system impacts).                                          measures is expected to result in no more than small
                                                           changes to aquatic communities from their current
                                                           condition.
Impacts of transmission line right-of-way              1  SMALL. Licensee application of best management
 (ROW) management on aquatic resources \4\.                practices to ROW maintenance is expected to result in
                                                           no more than small impacts to aquatic resources.
Losses from predation, parasitism, and                 1  SMALL. These types of losses have not been found to be
 disease among organisms exposed to                        a problem at operating nuclear power plants and are
 sublethal stresses.                                       not expected to be a problem during the license
                                                           renewal term.
----------------------------------------------------------------------------------------------------------------
                                       Special Status Species and Habitats
----------------------------------------------------------------------------------------------------------------
Threatened, endangered, and protected                  2  The magnitude of impacts on threatened, endangered,
 species and essential fish habitat.                       and protected species, critical habitat, and
                                                           essential fish habitat would depend on the occurrence
                                                           of listed species and habitats and the effects of
                                                           power plant systems on them. Consultation with
                                                           appropriate agencies would be needed to determine
                                                           whether special status species or habitats are
                                                           present and whether they would be adversely affected
                                                           by continued operations and refurbishment associated
                                                           with license renewal.
----------------------------------------------------------------------------------------------------------------
                                         Historic and Cultural Resources
----------------------------------------------------------------------------------------------------------------
Historic and cultural resources \4\........            2  Continued operations and refurbishment associated with
                                                           license renewal are expected to have no more than
                                                           small impacts on historic and cultural resources
                                                           located onsite and in the transmission line ROW
                                                           because most impacts could be mitigated by avoiding
                                                           those resources. The National Historic Preservation
                                                           Act (NHPA) requires the Federal agency to consult
                                                           with the State Historic Preservation Officer (SHPO)
                                                           and appropriate Native American Tribes to determine
                                                           the potential effects on historic properties and
                                                           mitigation, if necessary.
----------------------------------------------------------------------------------------------------------------
                                                 Socioeconomics
----------------------------------------------------------------------------------------------------------------
Employment and income, recreation and                  1  SMALL. Although most nuclear plants have large numbers
 tourism.                                                  of employees with higher than average wages and
                                                           salaries, employment, income, recreation, and tourism
                                                           impacts from continued operations and refurbishment
                                                           associated with license renewal are expected to be
                                                           small.
Tax revenues...............................            1  SMALL. Nuclear plants provide tax revenue to local
                                                           jurisdictions in the form of property tax payments,
                                                           payments in lieu of tax (PILOT), or tax payments on
                                                           energy production. The amount of tax revenue paid
                                                           during the license renewal term as a result of
                                                           continued operations and refurbishment associated
                                                           with license renewal is not expected to change.

[[Page 65]]

 
Community services and education...........            1  SMALL. Changes resulting from continued operations and
                                                           refurbishment associated with license renewal to
                                                           local community and educational services would be
                                                           small. With little or no change in employment at the
                                                           licensee's plant, value of the power plant, payments
                                                           on energy production, and PILOT payments expected
                                                           during the license renewal term, community and
                                                           educational services would not be affected by
                                                           continued power plant operations.
Population and housing.....................            1  SMALL. Changes resulting from continued operations and
                                                           refurbishment associated with license renewal to
                                                           regional population and housing availability and
                                                           value would be small. With little or no change in
                                                           employment at the licensee's plant expected during
                                                           the license renewal term, population and housing
                                                           availability and values would not be affected by
                                                           continued power plant operations.
Transportation.............................            1  SMALL. Changes resulting from continued operations and
                                                           refurbishment associated with license renewal to
                                                           traffic volumes would be small.
----------------------------------------------------------------------------------------------------------------
                                                  Human Health
----------------------------------------------------------------------------------------------------------------
Radiation exposures to the public..........            1  SMALL. Radiation doses to the public from continued
                                                           operations and refurbishment associated with license
                                                           renewal are expected to continue at current levels,
                                                           and would be well below regulatory limits.
Radiation exposures to plant workers.......            1  SMALL. Occupational doses from continued operations
                                                           and refurbishment associated with license renewal are
                                                           expected to be within the range of doses experienced
                                                           during the current license term, and would continue
                                                           to be well below regulatory limits.
Human health impact from chemicals.........            1  SMALL. Chemical hazards to plant workers resulting
                                                           from continued operations and refurbishment
                                                           associated with license renewal are expected to be
                                                           minimized by the licensee implementing good
                                                           industrial hygiene practices as required by permits
                                                           and Federal and State regulations. Chemical releases
                                                           to the environment and the potential for impacts to
                                                           the public are expected to be minimized by adherence
                                                           to discharge limitations of NPDES and other permits.
Microbiological hazards to the public                  2  SMALL, MODERATE, or LARGE. These organisms are not
 (plants with cooling ponds or canals or                   expected to be a problem at most operating plants
 cooling towers that discharge to a river).                except possibly at plants using cooling ponds, lakes,
                                                           or canals, or that discharge into rivers. Impacts
                                                           would depend on site-specific characteristics.
Microbiological hazards to plant workers...            1  SMALL. Occupational health impacts are expected to be
                                                           controlled by continued application of accepted
                                                           industrial hygiene practices to minimize worker
                                                           exposures as required by permits and Federal and
                                                           State regulations.
Chronic effects of electromagnetic fields        N/A \5\  Uncertain impact. Studies of 60-Hz EMFs have not
 (EMFs) \4 6\.                                             uncovered consistent evidence linking harmful effects
                                                           with field exposures. EMFs are unlike other agents
                                                           that have a toxic effect (e.g., toxic chemicals and
                                                           ionizing radiation) in that dramatic acute effects
                                                           cannot be forced and longer-term effects, if real,
                                                           are subtle. Because the state of the science is
                                                           currently inadequate, no generic conclusion on human
                                                           health impacts is possible.
Physical occupational hazards..............            1  SMALL. Occupational safety and health hazards are
                                                           generic to all types of electrical generating
                                                           stations, including nuclear power plants, and are of
                                                           small significance if the workers adhere to safety
                                                           standards and use protective equipment as required by
                                                           Federal and State regulations.
Electric shock hazards \4\.................            2  SMALL, MODERATE, or LARGE. Electrical shock potential
                                                           is of small significance for transmission lines that
                                                           are operated in adherence with the National
                                                           Electrical Safety Code (NESC). Without a review of
                                                           conformance with NESC criteria of each nuclear power
                                                           plant's in-scope transmission lines, it is not
                                                           possible to determine the significance of the
                                                           electrical shock potential.
----------------------------------------------------------------------------------------------------------------
                                              Postulated Accidents
----------------------------------------------------------------------------------------------------------------
Design-basis accidents.....................            1  SMALL. The NRC staff has concluded that the
                                                           environmental impacts of design-basis accidents are
                                                           of small significance for all plants.
Severe accidents...........................            2  SMALL. The probability-weighted consequences of
                                                           atmospheric releases, fallout onto open bodies of
                                                           water, releases to groundwater, and societal and
                                                           economic impacts from severe accidents are small for
                                                           all plants. However, alternatives to mitigate severe
                                                           accidents must be considered for all plants that have
                                                           not considered such alternatives.
----------------------------------------------------------------------------------------------------------------

[[Page 66]]

 
                                              Environmental Justice
----------------------------------------------------------------------------------------------------------------
Minority and low-income populations........            2  Impacts to minority and low-income populations and
                                                           subsistence consumption resulting from continued
                                                           operations and refurbishment associated with license
                                                           renewal will be addressed in plant-specific reviews.
                                                           See NRC Policy Statement on the Treatment of
                                                           Environmental Justice Matters in NRC Regulatory and
                                                           Licensing Actions (69 FR 52040; August 24, 2004).
----------------------------------------------------------------------------------------------------------------
                                                Waste Management
----------------------------------------------------------------------------------------------------------------
Low-level waste storage and disposal.......            1  SMALL. The comprehensive regulatory controls that are
                                                           in place and the low public doses being achieved at
                                                           reactors ensure that the radiological impacts to the
                                                           environment would remain small during the license
                                                           renewal term.
Onsite storage of spent nuclear fuel.......            1  During the license renewal term, SMALL. The expected
                                                           increase in the volume of spent nuclear fuel from an
                                                           additional 20 years of operation can be safely
                                                           accommodated onsite during the license renewal term
                                                           with small environmental impacts through dry or pool
                                                           storage at all plants.
                                             ...........  For the period after the licensed life for reactor
                                                           operations, the impacts of onsite storage of spent
                                                           nuclear fuel during the continued storage period are
                                                           discussed in NUREG-2157 and as stated in Sec.
                                                           51.23(b), shall be deemed incorporated into this
                                                           issue.
Offsite radiological impacts of spent                  1  For the high-level waste and spent-fuel disposal
 nuclear fuel and high-level waste disposal.               component of the fuel cycle, the EPA established a
                                                           dose limit of 0.15 mSv (15 millirem) per year for the
                                                           first 10,000 years and 1.0 mSv (100 millirem) per
                                                           year between 10,000 years and 1 million years for
                                                           offsite releases of radionuclides at the proposed
                                                           repository at Yucca Mountain, Nevada.
                                                          The Commission concludes that the impacts would not be
                                                           sufficiently large to require the NEPA conclusion,
                                                           for any plant, that the option of extended operation
                                                           under 10 CFR part 54 should be eliminated.
                                                           Accordingly, while the Commission has not assigned a
                                                           single level of significance for the impacts of spent
                                                           fuel and high level waste disposal, this issue is
                                                           considered Category 1.
Mixed-waste storage and disposal...........            1  SMALL. The comprehensive regulatory controls and the
                                                           facilities and procedures that are in place ensure
                                                           proper handling and storage, as well as negligible
                                                           doses and exposure to toxic materials for the public
                                                           and the environment at all plants. License renewal
                                                           would not increase the small, continuing risk to
                                                           human health and the environment posed by mixed waste
                                                           at all plants. The radiological and nonradiological
                                                           environmental impacts of long-term disposal of mixed
                                                           waste from any individual plant at licensed sites are
                                                           small.
Nonradioactive waste storage and disposal..            1  SMALL. No changes to systems that generate
                                                           nonradioactive waste are anticipated during the
                                                           license renewal term. Facilities and procedures are
                                                           in place to ensure continued proper handling,
                                                           storage, and disposal, as well as negligible exposure
                                                           to toxic materials for the public and the environment
                                                           at all plants.
----------------------------------------------------------------------------------------------------------------
                                               Cumulative Impacts
----------------------------------------------------------------------------------------------------------------
Cumulative impacts.........................            2  Cumulative impacts of continued operations and
                                                           refurbishment associated with license renewal must be
                                                           considered on a plant-specific basis. Impacts would
                                                           depend on regional resource characteristics, the
                                                           resource-specific impacts of license renewal, and the
                                                           cumulative significance of other factors affecting
                                                           the resource.
----------------------------------------------------------------------------------------------------------------
                                               Uranium Fuel Cycle
----------------------------------------------------------------------------------------------------------------
Offsite radiological impacts--individual               1  SMALL. The impacts to the public from radiological
 impacts from other than the disposal of                   exposures have been considered by the Commission in
 spent fuel and high-level waste.                          Table S-3 of this part. Based on information in the
                                                           GEIS, impacts to individuals from radioactive gaseous
                                                           and liquid releases, including radon-222 and
                                                           technetium-99, would remain at or below the NRC's
                                                           regulatory limits.
Offsite radiological impacts--collective               1  There are no regulatory limits applicable to
 impacts from other than the disposal of                   collective doses to the general public from fuel-
 spent fuel and high-level waste.                          cycle facilities. The practice of estimating health
                                                           effects on the basis of collective doses may not be
                                                           meaningful. All fuel-cycle facilities are designed
                                                           and operated to meet the applicable regulatory limits
                                                           and standards. The Commission concludes that the
                                                           collective impacts are acceptable.

[[Page 67]]

 
                                                          The Commission concludes that the impacts would not be
                                                           sufficiently large to require the NEPA conclusion,
                                                           for any plant, that the option of extended operation
                                                           under 10 CFR part 54 should be eliminated.
                                                           Accordingly, while the Commission has not assigned a
                                                           single level of significance for the collective
                                                           impacts of the uranium fuel cycle, this issue is
                                                           considered Category 1.
Nonradiological impacts of the uranium fuel            1  SMALL. The nonradiological impacts of the uranium fuel
 cycle.                                                    cycle resulting from the renewal of an operating
                                                           license for any plant would be small.
Transportation.............................            1  SMALL. The impacts of transporting materials to and
                                                           from uranium-fuel-cycle facilities on workers, the
                                                           public, and the environment are expected to be small.
----------------------------------------------------------------------------------------------------------------
                        Termination of Nuclear Power Plant Operations and Decommissioning
----------------------------------------------------------------------------------------------------------------
Termination of plant operations and                    1  SMALL. License renewal is expected to have a
 decommissioning.                                          negligible effect on the impacts of terminating
                                                           operations and decommissioning on all resources.
----------------------------------------------------------------------------------------------------------------
\1\ Data supporting this table are contained in NUREG-1437, Revision 1, ``Generic Environmental Impact Statement
  for License Renewal of Nuclear Plants'' (June 2013).
\2\ The numerical entries in this column are based on the following category definitions:
Category 1: For the issue, the analysis reported in the Generic Environmental Impact Statement has shown:
(1) The environmental impacts associated with the issue have been determined to apply either to all plants or,
  for some issues, to plants having a specific type of cooling system or other specified plant or site
  characteristic;
(2) A single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for
  Offsite radiological impacts--collective impacts from other than the disposal of spent fuel and high-level
  waste); and
(3) Mitigation of adverse impacts associated with the issue has been considered in the analysis, and it has been
  determined that additional plant-specific mitigation measures are not likely to be sufficiently beneficial to
  warrant implementation.
The generic analysis of the issue may be adopted in each plant-specific review.
Category 2: For the issue, the analysis reported in the Generic Environmental Impact Statement has shown that
  one or more of the criteria of Category 1 cannot be met, and therefore additional plant-specific review is
  required.
\3\ The impact findings in this column are based on the definitions of three significance levels. Unless the
  significance level is identified as beneficial, the impact is adverse, or in the case of ``small,'' may be
  negligible. The definitions of significance follow:
SMALL--For the issue, environmental effects are not detectable or are so minor that they will neither
  destabilize nor noticeably alter any important attribute of the resource. For the purposes of assessing
  radiological impacts, the Commission has concluded that those impacts that do not exceed permissible levels in
  the Commission's regulations are considered small as the term is used in this table.
MODERATE--For the issue, environmental effects are sufficient to alter noticeably, but not to destabilize,
  important attributes of the resource.
LARGE--For the issue, environmental effects are clearly noticeable and are sufficient to destabilize important
  attributes of the resource.
For issues where probability is a key consideration (i.e., accident consequences), probability was a factor in
  determining significance.
\4\ This issue applies only to the in-scope portion of electric power transmission lines, which are defined as
  transmission lines that connect the nuclear power plant to the substation where electricity is fed into the
  regional power distribution system and transmission lines that supply power to the nuclear plant from the
  grid.
\5\ NA (not applicable). The categorization and impact finding definitions do not apply to these issues.
\6\ If, in the future, the Commission finds that, contrary to current indications, a consensus has been reached
  by appropriate Federal health agencies that there are adverse health effects from electromagnetic fields, the
  Commission will require applicants to submit plant-specific reviews of these health effects as part of their
  license renewal applications. Until such time, applicants for license renewal are not required to submit
  information on this issue.


[61 FR 66546, Dec. 18, 1996, as amended at 62 FR 59276, Nov. 3, 1997; 64 
FR 48507, Sept. 3, 1999; 66 FR 39278, July 30, 2001; 78 FR 37317, June 
20, 2013; 79 FR 56262, Sept. 19, 2014]

Subpart B [Reserved]



PART 52_LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR 
POWER PLANTS--Table of Contents



                           General Provisions

Sec.
52.0 Scope; applicability of 10 CFR Chapter I provisions.
52.1 Definitions.
52.2 Interpretations.
52.3 Written communications.
52.4 Deliberate misconduct.
52.5 Employee protection.
52.6 Completeness and accuracy of information.
52.7 Specific exemptions.
52.8 Combining licenses; elimination of repetition.
52.9 Jurisdictional limits.
52.10 Attacks and destructive acts.
52.11 Information collection requirements: OMB approval.

                      Subpart A_Early Site Permits

52.12 Scope of subpart.
52.13 Relationship to other subparts.
52.15 Filing of applications.
52.16 Contents of applications; general information.

[[Page 68]]

52.17 Contents of applications; technical information.
52.18 Standards for review of applications.
52.21 Administrative review of applications; hearings.
52.23 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
52.24 Issuance of early site permit.
52.25 Extent of activities permitted.
52.26 Duration of permit.
52.27 Limited work authorization after issuance of early site permit.
52.28 Transfer of early site permit.
52.29 Application for renewal.
52.31 Criteria for renewal.
52.33 Duration of renewal.
52.35 Use of site for other purposes.
52.39 Finality of early site permit determinations.

                Subpart B_Standard Design Certifications

52.41 Scope of subpart.
52.43 Relationship to other subparts.
52.45 Filing of applications.
52.46 Contents of applications; general information.
52.47 Contents of applications; technical information.
52.48 Standards for review of applications.
52.51 Administrative review of applications.
52.53 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
52.54 Issuance of standard design certification.
52.55 Duration of certification.
52.57 Application for renewal.
52.59 Criteria for renewal.
52.61 Duration of renewal.
52.63 Finality of standard design certifications.

                       Subpart C_Combined Licenses

52.71 Scope of subpart.
52.73 Relationship to other subparts.
52.75 Filing of applications.
52.77 Contents of applications; general information.
52.79 Contents of applications; technical information in final safety 
          analysis report.
52.80 Contents of applications; additional technical information.
52.81 Standards for review of applications.
52.83 Finality of referenced NRC approvals; partial initial decision on 
          site suitability.
52.85 Administrative review of applications; hearings.
52.87 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
52.89 [Reserved]
52.91 Authorization to conduct limited work authorization activities.
52.93 Exemptions and variances.
52.97 Issuance of combined licenses.
52.98 Finality of combined licenses; information requests.
52.99 Inspection during construction; ITAAC schedules and notifications; 
          NRC notices.
52.103 Operation under a combined license.
52.104 Duration of combined license.
52.105 Transfer of combined license.
52.107 Application for renewal.
52.109 Continuation of combined license.
52.110 Termination of license.

Subpart D [Reserved]

                   Subpart E_Standard Design Approvals

52.131 Scope of subpart.
52.133 Relationship to other subparts.
52.135 Filing of applications.
52.136 Contents of applications; general information.
52.137 Contents of applications; technical information.
52.139 Standards for review of applications.
52.141 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
52.143 Staff approval of design.
52.145 Finality of standard design approvals; information requests.
52.147 Duration of design approval.

                    Subpart F_Manufacturing Licenses

52.151 Scope of subpart.
52.153 Relationship to other subparts.
52.155 Filing of applications.
52.156 Contents of applications; general information.
52.157 Contents of applications; technical information in final safety 
          analysis report.
52.158 Contents of application; additional technical information.
52.159 Standards for review of application.
52.161 [Reserved]
52.163 Administrative review of applications; hearings.
52.165 Referral to the Advisory Committee on Reactor Safeguards (ACRS).
52.167 Issuance of manufacturing license.
52.169 [Reserved]
52.171 Finality of manufacturing licenses; information requests.
52.173 Duration of manufacturing license.
52.175 Transfer of manufacturing license.
52.177 Application for renewal.
52.179 Criteria for renewal.
52.181 Duration of renewal.

Subpart G [Reserved]

                          Subpart H_Enforcement

52.301 Violations.
52.303 Criminal penalties.

Appendix A to Part 52--Design Certification Rule for the U.S. Advanced 
          Boiling Water Reactor
Appendix B to Part 52--Design Certification Rule for the System 80 + 
          Design

[[Page 69]]

Appendix C to Part 52--Design Certification Rule for the AP600 Design
Appendix D to Part 52--Design Certification Rule for the AP1000 Design
Appendix E to Part 52--Design Certification Rule for the ESBWR Design
Appendixes F-M to Part 52 [Reserved]
Appendix N to Part 52--Standardization of Nuclear Power Plant Designs: 
          Combined Licenses to Construct and Operate Nuclear Power 
          Reactors of Identical Design at Multiple Sites

    Authority: Atomic Energy Act of 1954, secs. 103, 104, 147, 149, 161, 
181, 182, 183, 185, 186, 189, 223, 234 (42 U.S.C. 2133, 2134, 2167, 
2169, 2201, 2231, 2232, 2233, 2235, 2236, 2239, 2273, 2282); Energy 
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 
5842, 5846, 5851); 44 U.S.C. 3504 note.

    Source: 72 FR 49517, Aug. 28, 2007, unless otherwise noted.

                           General Provisions



Sec. 52.0  Scope; applicability of 10 CFR Chapter I provisions.

    (a) This part governs the issuance of early site permits, standard 
design certifications, combined licenses, standard design approvals, and 
manufacturing licenses for nuclear power facilities licensed under 
Section 103 of the Atomic Energy Act of 1954, as amended (68 Stat. 919), 
and Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242). 
This part also gives notice to all persons who knowingly provide to any 
holder of or applicant for an approval, certification, permit, or 
license, or to a contractor, subcontractor, or consultant of any of 
them, components, equipment, materials, or other goods or services that 
relate to the activities of a holder of or applicant for an approval, 
certification, permit, or license, subject to this part, that they may 
be individually subject to NRC enforcement action for violation of the 
provisions in 10 CFR 52.4.
    (b) Unless otherwise specifically provided for in this part, the 
regulations in 10 CFR Chapter I apply to a holder of or applicant for an 
approval, certification, permit, or license. A holder of or applicant 
for an approval, certification, permit, or license issued under this 
part shall comply with all requirements in 10 CFR Chapter I that are 
applicable. A license, approval, certification, or permit issued under 
this part is subject to all requirements in 10 CFR Chapter I which, by 
their terms, are applicable to early site permits, design 
certifications, combined licenses, design approvals, or manufacturing 
licenses.



Sec. 52.1  Definitions.

    (a) As used in this part--
    Combined license means a combined construction permit and operating 
license with conditions for a nuclear power facility issued under 
subpart C of this part.
    Decommission means to remove a facility or site safely from service 
and reduce residual radioactivity to a level that permits--
    (i) Release of the property for unrestricted use and termination of 
the license; or
    (ii) Release of the property under restricted conditions and 
termination of the license.
    Design characteristics are the actual features of a reactor or 
reactors. Design characteristics are specified in a standard design 
approval, a standard design certification, a combined license 
application, or a manufacturing license.
    Design parameters are the postulated features of a reactor or 
reactors that could be built at a proposed site. Design parameters are 
specified in an early site permit.
    Early site permit means a Commission approval, issued under subpart 
A of this part, for a site for one or more nuclear power facilities. An 
early site permit is a partial construction permit.
    License means a license, including an early site permit, combined 
license or manufacturing license under this part or a renewed license 
issued by the Commission under this part or part 54 of this chapter.
    Licensee means a person who is authorized to conduct activities 
under a license issued by the Commission.
    Limited work authorization means the authorization provided by the 
Director of New Reactors or the Director of Nuclear Reactor Regulation 
under Sec. 50.10 of this chapter.
    Major feature of the emergency plans means an aspect of those plans 
necessary to:

[[Page 70]]

    (i) Address in whole or part one or more of the 16 standards in 10 
CFR 50.47(b); or
    (ii) Describe the emergency planning zones as required in 10 CFR 
50.33(g).
    Manufacturing license means a license, issued under subpart F of 
this part, authorizing the manufacture of nuclear power reactors but not 
their construction, installation, or operation at the sites on which the 
reactors are to be operated.
    Modular design means a nuclear power station that consists of two or 
more essentially identical nuclear reactors (modules) and each module is 
a separate nuclear reactor capable of being operated independent of the 
state of completion or operating condition of any other module co-
located on the same site, even though the nuclear power station may have 
some shared or common systems.
    Prototype plant means a nuclear power plant that is used to test new 
safety features, such as the testing required under 10 CFR 50.43(e). The 
prototype plant is similar to a first-of-a-kind or standard plant design 
in all features and size, but may include additional safety features to 
protect the public and the plant staff from the possible consequences of 
accidents during the testing period.
    Site characteristics are the actual physical, environmental and 
demographic features of a site. Site characteristics are specified in an 
early site permit or in a final safety analysis report for a combined 
license.
    Site parameters are the postulated physical, environmental and 
demographic features of an assumed site. Site parameters are specified 
in a standard design approval, standard design certification, or 
manufacturing license.
    Standard design means a design which is sufficiently detailed and 
complete to support certification or approval in accordance with subpart 
B or E of this part, and which is usable for a multiple number of units 
or at a multiple number of sites without reopening or repeating the 
review.
    Standard design approval or design approval means an NRC staff 
approval, issued under subpart E of this part, of a final standard 
design for a nuclear power reactor of the type described in 10 CFR 
50.22. The approval may be for either the final design for the entire 
reactor facility or the final design of major portions thereof.
    Standard design certification or design certification means a 
Commission approval, issued under subpart B of this part, of a final 
standard design for a nuclear power facility. This design may be 
referred to as a certified standard design.
    (b) All other terms in this part have the meaning set out in 10 CFR 
50.2, or Section 11 of the Atomic Energy Act, as applicable.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 57446, Oct. 9, 2007; 79 
FR 66604, Nov. 10, 2014]



Sec. 52.2  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 52.3  Written communications.

    (a) General requirements. All correspondence, reports, applications, 
and other written communications from an applicant, licensee, or holder 
of a standard design approval to the Nuclear Regulatory Commission 
concerning the regulations in this part, individual license conditions, 
or the terms and conditions of an early site permit or standard design 
approval, must be sent either by mail addressed: ATTN: Document Control 
Desk, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by 
hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland, between the hours of 7:30 a.m. and 4:15 p.m. eastern time; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, e-mail, or CD-ROM. Electronic submissions must be 
made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained

[[Page 71]]

by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-
submittals.html; by e-mail to [email protected]; or by writing the 
Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. The guidance discusses, among 
other topics, the formats the NRC can accept, the use of electronic 
signatures, and the treatment of nonpublic information. If the 
communication is on paper, the signed original must be sent. If a 
submission due date falls on a Saturday, Sunday, or Federal holiday, the 
next Federal working day becomes the official due date.
    (b) Distribution requirements. Copies of all correspondence, 
reports, and other written communications concerning the regulations in 
this part or individual license conditions, or the terms and conditions 
of an early site permit or standard design approval, must be submitted 
to the persons listed in paragraph (b)(1) of this section (addresses for 
the NRC Regional Offices are listed in appendix D to part 20 of this 
chapter).
    (1) Applications for amendment of permits and licenses; reports; and 
other communications. All written communications (including responses 
to: generic letters, bulletins, information notices, regulatory 
information summaries, inspection reports, and miscellaneous requests 
for additional information) that are required of holders of early site 
permits, standard design approvals, combined licenses, or manufacturing 
licenses issued under this part must be submitted as follows, except as 
otherwise specified in paragraphs (b)(2) through (b)(7) of this section: 
to the NRC's Document Control Desk (if on paper, the signed original), 
with a copy to the appropriate Regional Office, and a copy to the 
appropriate NRC Resident Inspector, if one has been assigned to the site 
of the facility or the place of manufacture of a reactor licensed under 
subpart F of this part.
    (2) Applications and amendments to applications. Applications for 
early site permits, standard design approvals, combined licenses, 
manufacturing licenses and amendments to any of these types of 
applications must be submitted to the NRC's Document Control Desk, with 
a copy to the appropriate Regional Office, and a copy to the appropriate 
NRC Resident Inspector, if one has been assigned to the site of the 
facility or the place of manufacture of a reactor licensed under subpart 
F of this part, except as otherwise specified in paragraphs (b)(3) 
through (b)(7) of this section. If the application or amendment is on 
paper, the submission to the Document Control Desk must be the signed 
original.
    (3) Acceptance review application. Written communications required 
for an application for determination of suitability for docketing must 
be submitted to the NRC's Document Control Desk, with a copy to the 
appropriate Regional Office. If the communication is on paper, the 
submission to the Document Control Desk must be the signed original.
    (4) Security plan and related submissions. Written communications, 
as defined in paragraphs (b)(4)(i) through (iv) of this section, must be 
submitted to the NRC's Document Control Desk, with a copy to the 
appropriate Regional Office. If the communication is on paper, the 
submission to the Document Control Desk must be the signed original.
    (i) Physical security plan under Sec. 52.79 of this chapter;
    (ii) Safeguards contingency plan under Sec. 52.79 of this chapter;
    (iii) Change to security plan, guard training and qualification 
plan, or safeguards contingency plan made without prior Commission 
approval under Sec. 50.54(p) of this chapter;
    (iv) Application for amendment of physical security plan, guard 
training and qualification plan, or safeguards contingency plan under 
Sec. 50.90 of this chapter.
    (5) Emergency plan and related submissions. Written communications 
as defined in paragraphs (b)(5)(i) through (iii) of this section must be 
submitted to the NRC's Document Control Desk, with a copy to the 
appropriate Regional Office, and a copy to the appropriate NRC Resident 
Inspector if one has been assigned to the site of the facility. If the 
communication is on paper, the submission to the Document Control Desk 
must be the signed original.

[[Page 72]]

    (i) Emergency plan under Sec. 52.17(b) or Sec. 52.79(a);
    (ii) Change to an emergency plan under Sec. 50.54(q) of this 
chapter;
    (iii) Emergency implementing procedures under appendix E, Section V 
of part 50 of this chapter.
    (6) Updated FSAR. An updated final safety analysis report (FSAR) or 
replacement pages under Sec. 50.71(e) of this chapter, or the 
regulations in this part must be submitted to the NRC's Document Control 
Desk, with a copy to the appropriate Regional Office, and a copy to the 
appropriate NRC Resident Inspector if one has been assigned to the site 
of the facility or the place of manufacture of a reactor licensed under 
subpart F of this part. Paper copy submissions may be made using 
replacement pages; however, if a licensee chooses to use electronic 
submission, all subsequent updates or submissions must be performed 
electronically on a total replacement basis. If the communication is on 
paper, the submission to the Document Control Desk must be the signed 
original. If the communications are submitted electronically, see 
Guidance for Electronic Submissions to the Commission.
    (7) Quality assurance related submissions. (i) A change to the 
safety analysis report quality assurance program description under Sec. 
50.54(a)(3) or Sec. 50.55(f)(4) of this chapter, or a change to a 
licensee's NRC-accepted quality assurance topical report under Sec. 
50.54(a)(3) or Sec. 50.55(f)(4) of this chapter, must be submitted to 
the NRC's Document Control Desk, with a copy to the appropriate Regional 
Office, and a copy to the appropriate NRC Resident Inspector if one has 
been assigned to the site of the facility. If the communication is on 
paper, the submission to the Document Control Desk must be the signed 
original.
    (ii) A change to an NRC-accepted quality assurance topical report 
from nonlicensees (i.e., architect/engineers, NSSS suppliers, fuel 
suppliers, constructors, etc.) must be submitted to the NRC's Document 
Control Desk. If the communication is on paper, the signed original must 
be sent.
    (8) Certification of permanent cessation of operations. The 
licensee's certification of permanent cessation of operations under 
Sec. 52.110(a)(1), must state the date on which operations have ceased 
or will cease, and must be submitted to the NRC's Document Control Desk. 
This submission must be under oath or affirmation.
    (9) Certification of permanent fuel removal. The licensee's 
certification of permanent fuel removal under Sec. 52.110(a)(1), must 
state the date on which the fuel was removed from the reactor vessel and 
the disposition of the fuel, and must be submitted to the NRC's Document 
Control Desk. This submission must be under oath or affirmation.
    (c) Form of communications. All paper copies submitted to meet the 
requirements set forth in paragraph (b) of this section must be 
typewritten, printed or otherwise reproduced in permanent form on 
unglazed paper. Exceptions to these requirements imposed on paper 
submissions may be granted for the submission of micrographic, 
photographic, or similar forms.
    (d) Regulation governing submission. Applicants, licensees, and 
holders of standard design approvals submitting correspondence, reports, 
and other written communications under the regulations of this part are 
requested but not required to cite whenever practical, in the upper 
right corner of the first page of the submission, the specific 
regulation or other basis requiring submission.

[72 FR 49517, Aug. 28, 2007, as amended at 74 FR 62682, Dec. 1, 2009; 80 
FR 74980, Dec. 1, 2015]



Sec. 52.4  Deliberate misconduct.

    (a) Applicability. This section applies to any:
    (1) Licensee;
    (2) Holder of a standard design approval;
    (3) Applicant for a standard design certification;
    (4) Applicant for a license or permit;
    (5) Applicant for a standard design approval;
    (6) Employee of a licensee;
    (7) Employee of an applicant for a license, a standard design 
certification, or a standard design approval;
    (8) Any contractor (including a supplier or consultant), 
subcontractor, or

[[Page 73]]

employee of a contractor or subcontractor of any licensee; or
    (9) Any contractor (including a supplier or consultant), 
subcontractor, or employee of a contractor or subcontractor of any 
applicant for a license, a standard design certification, or a standard 
design approval.
    (b) Definitions. For purposes of this section:
    Deliberate misconduct means an intentional act or omission that a 
person or entity knows:
    (i) Would cause a licensee or an applicant for a license, standard 
design certification, or standard design approval to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation, 
of any license, standard design certification, or standard design 
approval; or
    (ii) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, holder 
of a standard design approval, applicant for a license, standard design 
certification, or standard design approval, or contractor, or 
subcontractor.
    (c) Prohibition against deliberate misconduct. Any person or entity 
subject to this section, who knowingly provides to any licensee, any 
applicant for a license, standard design certification or standard 
design approval, or a contractor, or subcontractor of a person or entity 
subject to this section, any components, equipment, materials, or other 
goods or services that relate to a licensee's or applicant's activities 
under this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee, holder of a standard design 
approval, or applicant to be in violation of any rule, regulation, or 
order; or any term, condition, or limitation of any license issued by 
the Commission, any standard design approval, or standard design 
certification; or
    (2) Deliberately submit to the NRC; a licensee, an applicant for a 
license, standard design certification or standard design approval; or a 
licensee's, standard design approval holder's, or applicant's contractor 
or subcontractor, information that the person submitting the information 
knows to be incomplete or inaccurate in some respect material to the 
NRC.
    (d) A person or entity who violates paragraph (c)(1) or (c)(2) of 
this section may be subject to enforcement action in accordance with the 
procedures in 10 CFR part 2, subpart B.



Sec. 52.5  Employee protection.

    (a) Discrimination by a Commission licensee, holder of a standard 
design approval, an applicant for a license, standard design 
certification, or standard design approval, a contractor or 
subcontractor of a Commission licensee, holder of a standard design 
approval, applicant for a license, standard design certification, or 
standard design approval, against an employee for engaging in certain 
protected activities is prohibited. Discrimination includes discharge 
and other actions that relate to compensation, terms, conditions, or 
privileges of employment. The protected activities are established in 
Section 211 of the Energy Reorganization Act of 1974, as amended, and in 
general are related to the administration or enforcement of a 
requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in the 
introductory text of paragraph (a) of this section or possible 
violations of requirements imposed under either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in the introductory text of paragraph (a) of this 
section or under these requirements if the employee has identified the 
alleged illegality to the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in the introductory text of 
paragraph (a) of this section; and

[[Page 74]]

    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, a holder of a standard design approval, an 
applicant for a Commission license, standard design certification, or a 
standard design approval, or a contractor or subcontractor of a 
Commission licensee, holder of a standard design approval, or any 
applicant may be grounds for--
    (1) Denial, revocation, or suspension of the license or standard 
design approval;
    (2) Withdrawal or revocation of a proposed or final standard design 
certification;
    (3) Imposition of a civil penalty on the licensee, holder of a 
standard design approval, or applicant (including an applicant for a 
standard design certification under this part following Commission 
adoption of final design certification rule) or a contractor or 
subcontractor of the licensee, holder of a standard design approval, or 
applicant.
    (4) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee, each holder of a standard design approval, and 
each applicant for a license, standard design certification, or standard 
design approval, shall prominently post the revision of NRC Form 3, 
``Notice to Employees,'' referenced in 10 CFR 19.11(e). This form must 
be posted at locations sufficient to permit employees protected by this 
section to observe a copy on the way to or from their place of work. 
Premises must be posted not later than thirty (30) days after an 
application is docketed and remain posted while the application is 
pending before the Commission, during the term of the license, standard 
design certification, or standard design approval under 10 CFR part 52, 
and for 30 days following license termination or the expiration or 
termination of the standard design certification or standard design 
approval under 10 CFR part 52.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor under Section 211 of 
the Energy Reorganization Act of 1974, as amended, may contain any 
provision which would prohibit, restrict, or otherwise discourage an 
employee from

[[Page 75]]

participating in protected activity as defined in paragraph (a)(1) of 
this section including, but not limited to, providing information to the 
NRC or to his or her employer on potential violations or other matters 
within NRC's regulatory responsibilities.
    (g) Part 19 of this chapter sets forth requirements and regulatory 
provisions applicable to licensees, holders of a standard design 
approval, applicants for a license, standard design certification, or 
standard design approval, and contractors or subcontractors of a 
Commission licensee, or holder of a standard design approval, and are in 
addition to the requirements in this section.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 63974, Nov. 14, 2007; 
73 FR 30458, May 28, 2008; 79 FR 66604, Nov. 10, 2014]



Sec. 52.6  Completeness and accuracy of information.

    (a) Information provided to the Commission by a licensee (including 
an early site permit holder, a combined license holder, and a 
manufacturing license holder), a holder of a standard design approval 
under this part, and an applicant for a license or an applicant for a 
standard design certification or a standard design approval under this 
part, and information required by statute or by the Commission's 
regulations, orders, license conditions, or terms and conditions of a 
standard design approval to be maintained by the licensee, the holder of 
a standard design approval under this part, the applicant for a standard 
design certification under this part following Commission adoption of a 
final design certification rule, and an applicant for a license, a 
standard design certification, or a standard design approval under this 
part shall be complete and accurate in all material respects.
    (b) Each applicant or licensee, each holder of a standard design 
approval under this part, and each applicant for a standard design 
certification under this part following Commission adoption of a final 
design certification regulation, shall notify the Commission of 
information identified by the applicant or the licensee as having for 
the regulated activity a significant implication for public health and 
safety or common defense and security. An applicant, licensee, or holder 
violates this paragraph only if the applicant, licensee, or holder fails 
to notify the Commission of information that the applicant, licensee, or 
holder has been identified as having a significant implication for 
public health and safety or common defense and security. Notification 
shall be provided to the Administrator of the appropriate Regional 
Office within 2 working days of identifying the information. This 
requirement is not applicable to information which is already required 
to be provided to the Commission by other reporting or updating 
requirements.



Sec. 52.7  Specific exemptions.

    The Commission may, upon application by any interested person or 
upon its own initiative, grant exemptions from the requirements of the 
regulations of this part. The Commission's consideration will be 
governed by Sec. 50.12 of this chapter, unless other criteria are 
provided for in this part, in which case the Commission's consideration 
will be governed by the criteria in this part. Only if those criteria 
are not met will the Commission's consideration be governed by Sec. 
50.12 of this chapter. The Commission's consideration of requests for 
exemptions from requirements of the regulations of other parts in this 
chapter, which are applicable by virtue of this part, shall be governed 
by the exemption requirements of those parts.



Sec. 52.8  Combining licenses; elimination of repetition.

    (a) An applicant for a license under this part may combine in its 
application several applications for different kinds of licenses under 
the regulations of this chapter.
    (b) An applicant may incorporate by reference in its application 
information contained in previous applications, statements or reports 
filed with the Commission, provided, however, that such references are 
clear and specific.
    (c) The Commission may combine in a single license the activities of 
an applicant which would otherwise be licensed separately.

[[Page 76]]



Sec. 52.9  Jurisdictional limits.

    No permit, license, standard design approval, or standard design 
certification under this part shall be deemed to have been issued for 
activities which are not under or within the jurisdiction of the United 
States.



Sec. 52.10  Attacks and destructive acts.

    Neither an applicant for a license to manufacture, construct, and 
operate a utilization facility under this part, nor for an amendment to 
this license, or an applicant for an early site permit, a standard 
design certification, or standard design approval under this part, or 
for an amendment to the early site permit, standard design 
certification, or standard design approval, is required to provide for 
design features or other measures for the specific purpose of protection 
against the effects of--
    (a) Attacks and destructive acts, including sabotage, directed 
against the facility by an enemy of the United States, whether a foreign 
government or other person; or
    (b) Use or deployment of weapons incident to U.S. defense 
activities.



Sec. 52.11  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under Control Number 3150-0151.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 52.7, 52.15, 52.16, 52.17, 52.29, 52.35, 
52.39, 52.45, 52.46, 52.47, 52.57, 52.63, 52.75, 52.77, 52.79, 52.80, 
52.93, 52.99, 52.110, 52.135, 52.136, 52.137, 52.155, 52.156, 52.157, 
52.158, 52.171, 52.177, and appendices A, B, C, D, E, and N of this 
part.

[72 FR 49517, Aug. 28, 2007, as amended at 79 FR 61983, Nov. 14, 2014]



                      Subpart A_Early Site Permits



Sec. 52.12  Scope of subpart.

    This subpart sets out the requirements and procedures applicable to 
Commission issuance of an early site permit for approval of a site for 
one or more nuclear power facilities separate from the filing of an 
application for a construction permit or combined license for the 
facility.



Sec. 52.13  Relationship to other subparts.

    This subpart applies when any person who may apply for a 
construction permit under 10 CFR part 50, or for a combined license 
under this part seeks an early site permit from the Commission 
separately from an application for a construction permit or a combined 
license.



Sec. 52.15  Filing of applications.

    (a) Any person who may apply for a construction permit under 10 CFR 
part 50, or for a combined license under this part, may file an 
application for an early site permit with the Director, Office of New 
Reactors, or the Director, Office of Nuclear Reactor Regulation, as 
appropriate. An application for an early site permit may be filed 
notwithstanding the fact that an application for a construction permit 
or a combined license has not been filed in connection with the site for 
which a permit is sought.
    (b) The application must comply with the applicable filing 
requirements of Sec. Sec. 52.3 and 50.30 of this chapter.
    (c) The fees associated with the filing and review of an application 
for the initial issuance or renewal of an early site permit are set 
forth in 10 CFR part 170.



Sec. 52.16  Contents of applications; general information.

    The application must contain all of the information required by 10 
CFR 50.33(a) through (d) and (j) of this chapter.



Sec. 52.17  Contents of applications; technical information.

    (a) For applications submitted before September 27, 2007, the rule 
provisions in effect at the date of docketing apply

[[Page 77]]

unless otherwise requested by the applicant in writing. The application 
must contain:
    (1) A site safety analysis report. The site safety analysis report 
shall include the following:
    (i) The specific number, type, and thermal power level of the 
facilities, or range of possible facilities, for which the site may be 
used;
    (ii) The anticipated maximum levels of radiological and thermal 
effluents each facility will produce;
    (iii) The type of cooling systems, intakes, and outflows that may be 
associated with each facility;
    (iv) The boundaries of the site;
    (v) The proposed general location of each facility on the site;
    (vi) The seismic, meteorological, hydrologic, and geologic 
characteristics of the proposed site with appropriate consideration of 
the most severe of the natural phenomena that have been historically 
reported for the site and surrounding area and with sufficient margin 
for the limited accuracy, quantity, and period of time in which the 
historical data have been accumulated;
    (vii) The location and description of any nearby industrial, 
military, or transportation facilities and routes;
    (viii) The existing and projected future population profile of the 
area surrounding the site;
    (ix) A description and safety assessment of the site on which a 
facility is to be located. The assessment must contain an analysis and 
evaluation of the major structures, systems, and components of the 
facility that bear significantly on the acceptability of the site under 
the radiological consequence evaluation factors identified in paragraphs 
(a)(1)(ix)(A) and (a)(1)(ix)(B) of this section. In performing this 
assessment, an applicant shall assume a fission product release \1\ from 
the core into the containment assuming that the facility is operated at 
the ultimate power level contemplated. The applicant shall perform an 
evaluation and analysis of the postulated fission product release, using 
the expected demonstrable containment leak rate and any fission product 
cleanup systems intended to mitigate the consequences of the accidents, 
together with applicable site characteristics, including site 
meteorology, to evaluate the offsite radiological consequences. Site 
characteristics must comply with part 100 of this chapter. The 
evaluation must determine that:
---------------------------------------------------------------------------

    \1\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. Such accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (A) An individual located at any point on the boundary of the 
exclusion area for any 2 hour period following the onset of the 
postulated fission product release, would not receive a radiation dose 
in excess of 25 rem \2\ total effective dose equivalent (TEDE).
---------------------------------------------------------------------------

    \2\ A whole body dose of 25 rem has been stated to correspond 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations at the time 
could be disregarded in the determination of their radiation exposure 
status (see NBS Handbook 69 dated June 5, 1959). However, its use is not 
intended to imply that this number constitutes an acceptable limit for 
an emergency dose to the public under accident conditions. Rather, this 
dose value has been set forth in this section as a reference value, 
which can be used in the evaluation of plant design features with 
respect to postulated reactor accidents, to assure that these designs 
provide assurance of low risk of public exposure to radiation, in the 
event of an accidents.
---------------------------------------------------------------------------

    (B) An individual located at any point on the outer boundary of the 
low population zone, who is exposed to the radioactive cloud resulting 
from the postulated fission product release (during the entire period of 
its passage) would not receive a radiation dose in excess of 25 rem 
TEDE;
    (x) Information demonstrating that site characteristics are such 
that adequate security plans and measures can be developed;
    (xi) For applications submitted after September 27, 2007, a 
description of the quality assurance program applied to site-related 
activities for the future design, fabrication, construction, and testing 
of the structures, systems, and components of a facility or facilities 
that may be constructed on the site.

[[Page 78]]

Appendix B to 10 CFR part 50 sets forth the requirements for quality 
assurance programs for nuclear power plants. The description of the 
quality assurance program for a nuclear power plant site shall include a 
discussion of how the applicable requirements of appendix B to part 50 
of this chapter will be satisfied; and
    (xii) An evaluation of the site against applicable sections of the 
Standard Review Plan (SRP) revision in effect 6 months before the docket 
date of the application. The evaluation required by this section shall 
include an identification and description of all differences in 
analytical techniques and procedural measures proposed for a site and 
those corresponding techniques and measures given in the SRP acceptance 
criteria. Where such a difference exists, the evaluation shall discuss 
how the proposed alternative provides an acceptable method of complying 
with the Commission's regulations, or portions thereof, that underlie 
the corresponding SRP acceptance criteria. The SRP is not a substitute 
for the regulations, and compliance is not a requirement.
    (2) A complete environmental report as required by 10 CFR 51.50(b).
    (b)(1) The site safety analysis report must identify physical 
characteristics of the proposed site, such as egress limitations from 
the area surrounding the site, that could pose a significant impediment 
to the development of emergency plans. If physical characteristics are 
identified that could pose a significant impediment to the development 
of emergency plans, the application must identify measures that would, 
when implemented, mitigate or eliminate the significant impediment.
    (2) The site safety analysis report may also:
    (i) Propose major features of the emergency plans, in accordance 
with the pertinent standards of Sec. 50.47 of this chapter and the 
requirements of appendix E to part 50 of this chapter, such as the exact 
size and configuration of the emergency planning zones, for review and 
approval by the NRC, in consultation with the Federal Emergency 
Management Agency (FEMA) in the absence of complete and integrated 
emergency plans; or
    (ii) Propose complete and integrated emergency plans for review and 
approval by the NRC, in consultation with FEMA, in accordance with the 
applicable standards of Sec. 50.47 of this chapter and the requirements 
of appendix E to part 50 of this chapter. To the extent approval of 
emergency plans is sought, the application must contain the information 
required by Sec. 50.33(g) and (j) of this chapter.
    (3) Emergency plans submitted under paragraph (b)(2)(ii) of this 
section must include the proposed inspections, tests, and analyses that 
the holder of a combined license referencing the early site permit shall 
perform, and the acceptance criteria that are necessary and sufficient 
to provide reasonable assurance that, if the inspections, tests, and 
analyses are performed and the acceptance criteria met, the facility has 
been constructed and will be operated in conformity with the emergency 
plans, the provisions of the Act, and the Commission's rules and 
regulations. Major features of an emergency plan submitted under 
paragraph (b)(2)(i) of this section may include proposed inspections, 
tests, analyses, and acceptance criteria.
    (4) Under paragraphs (b)(1) and (b)(2)(i) of this section, the site 
safety analysis report must include a description of contacts and 
arrangements made with Federal, State, and local governmental agencies 
with emergency planning responsibilities. The site safety analysis 
report must contain any certifications that have been obtained. If these 
certifications cannot be obtained, the site safety analysis report must 
contain information, including a utility plan, sufficient to show that 
the proposed plans provide reasonable assurance that adequate protective 
measures can and will be taken in the event of a radiological emergency 
at the site. Under the option set forth in paragraph (b)(2)(ii) of this 
section, the applicant shall make good faith efforts to obtain from the 
same governmental agencies certifications that:
    (i) The proposed emergency plans are practicable;
    (ii) These agencies are committed to participating in any further 
development of the plans, including any required field demonstrations, 
and

[[Page 79]]

    (iii) That these agencies are committed to executing their 
responsibilities under the plans in the event of an emergency.
    (c) An applicant may request that a limited work authorization under 
10 CFR 50.10 be issued in conjunction with the early site permit. The 
application must include the information otherwise required by 10 CFR 
50.10(d)(3). Applications submitted before, and pending as of November 
8, 2007, must include the information required by Sec. 52.17(c) 
effective on the date of docketing.
    (d) Each applicant for an early site permit under this part shall 
protect Safeguards Information against unauthorized disclosure in 
accordance with the requirements in Sec. Sec. 73.21 and 73.22 of this 
chapter, as applicable.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 57447, Oct. 9, 2007; 73 
FR 63571, Oct. 24, 2008; 78 FR 34249, June 7, 2013; 78 FR 75450, Dec. 
12, 2013]



Sec. 52.18  Standards for review of applications.

    Applications filed under this subpart will be reviewed according to 
the applicable standards set out in 10 CFR part 50 and its appendices 
and 10 CFR part 100. In addition, the Commission shall prepare an 
environmental impact statement during review of the application, in 
accordance with the applicable provisions of 10 CFR part 51. The 
Commission shall determine, after consultation with FEMA, whether the 
information required of the applicant by Sec. 52.17(b)(1) shows that 
there is not significant impediment to the development of emergen cy 
plans that cannot be mitigated or eliminated by measures proposed by the 
applicant, whether any major features of emergency plans submitted by 
the applicant under Sec. 52.17(b)(2)(i) are acceptable in accordance 
with the applicable standards of Sec. 50.47 of this chapter and the 
requirements of appendix E to part 50 of this chapter, and whether any 
emergency plans submitted by the applicant under Sec. 52.17(b)(2)(ii) 
provide reasonable assurance that adequate protective measures can and 
will be taken in the event of a radiological emergency.

[72 FR 49517, Aug. 28, 2007, as amended at 78 FR 34249, June 7, 2013; 78 
FR 75450, Dec. 12, 2013]



Sec. 52.21  Administrative review of applications; hearings.

    An early site permit is subject to all procedural requirements in 10 
CFR part 2, including the requirements for docketing in Sec. 
2.101(a)(1) through (4) of this chapter, and the requirements for 
issuance of a notice of hearing in Sec. Sec. 2.104(a) and (d) of this 
chapter, provided that the designated sections may not be construed to 
require that the environmental report, or draft or final environmental 
impact statement include an assessment of the benefits of construction 
and operation of the reactor or reactors, or an analysis of alternative 
energy sources. The presiding officer in an early site permit hearing 
shall not admit contentions proffered by any party concerning an 
assessment of the benefits of construction and operation of the reactor 
or reactors, or an analysis of alternative energy sources if those 
issues were not addressed by the applicant in the early site permit 
application. All hearings conducted on applications for early site 
permits filed under this part are governed by the procedures contained 
in subparts C, G, L, and N of 10 CFR part 2, as applicable.



Sec. 52.23  Referral to the Advisory Committee on Reactor Safeguards 
(ACRS).

    The Commission shall refer a copy of the application for an early 
site permit to the ACRS. The ACRS shall report on those portions of the 
application which concern safety.



Sec. 52.24  Issuance of early site permit.

    (a) After conducting a hearing under Sec. 52.21 and receiving the 
report to be submitted by the ACRS under Sec. 52.23, the Commission may 
issue an early site permit, in the form the Commission deems 
appropriate, if the Commission finds that:
    (1) An application for an early site permit meets the applicable 
standards and requirements of the Act and the Commission's regulations;

[[Page 80]]

    (2) Notifications, if any, to other agencies or bodies have been 
duly made;
    (3) There is reasonable assurance that the site is in conformity 
with the provisions of the Act, and the Commission's regulations;
    (4) The applicant is technically qualified to engage in any 
activities authorized;
    (5) The proposed inspections, tests, analyses and acceptance 
criteria, including any on emergency planning, are necessary and 
sufficient, within the scope of the early site permit, to provide 
reasonable assurance that the facility has been constructed and will be 
operated in conformity with the license, the provisions of the Act, and 
the Commission's regulations;
    (6) Issuance of the permit will not be inimical to the common 
defense and security or to the health and safety of the public;
    (7) Any significant adverse environmental impact resulting from 
activities requested under Sec. 52.17(c) can be redressed; and
    (8) The findings required by subpart A of 10 CFR part 51 have been 
made.
    (b) The early site permit must specify the site characteristics, 
design parameters, and terms and conditions of the early site permit the 
Commission deems appropriate. Before issuance of either a construction 
permit or combined license referencing an early site permit, the 
Commission shall find that any relevant terms and conditions of the 
early site permit have been met. Any terms or conditions of the early 
site permit that could not be met by the time of issuance of the 
construction permit or combined license, must be set forth as terms or 
conditions of the construction permit or combined license.
    (c) The early site permit shall specify those 10 CFR 50.10 
activities requested under Sec. 52.17(c) that the permit holder is 
authorized to perform.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 57447, Oct. 9, 2007]



Sec. 52.25  Extent of activities permitted.

    If the activities authorized by Sec. 52.24(c) are performed and the 
site is not referenced in an application for a construction permit or a 
combined license issued under subpart C of this part while the permit 
remains valid, then the early site permit remains in effect solely for 
the purpose of site redress, and the holder of the permit shall redress 
the site in accordance with the terms of the site redress plan required 
by Sec. 52.17(c). If, before redress is complete, a use not envisaged 
in the redress plan is found for the site or parts thereof, the holder 
of the permit shall carry out the redress plan to the greatest extent 
possible consistent with the alternate use.



Sec. 52.26  Duration of permit.

    (a) Except as provided in paragraph (b) of this section, an early 
site permit issued under this subpart may be valid for not less than 10, 
nor more than 20 years from the date of issuance.
    (b) An early site permit continues to be valid beyond the date of 
expiration in any proceeding on a construction permit application or a 
combined license application that references the early site permit and 
is docketed before the date of expiration of the early site permit, or, 
if a timely application for renewal of the permit has been docketed, 
before the Commission has determined whether to renew the permit.
    (c) An applicant for a construction permit or combined license may, 
at its own risk, reference in its application a site for which an early 
site permit application has been docketed but not granted.
    (d) Upon issuance of a construction permit or combined license, a 
referenced early site permit is subsumed, to the extent referenced, into 
the construction permit or combined license.

[72 FR 49517, Aug. 28, 2007. Redesignated at 72 FR 57447, Oct. 9, 2007]



Sec. 52.27  Limited work authorization after issuance of early
site permit.

    A holder of an early site permit may request a limited work 
authorization in accordance with Sec. 50.10 of this chapter.

[72 FR 57447, Oct. 9, 2007]

[[Page 81]]



Sec. 52.28  Transfer of early site permit.

    An application to transfer an early site permit will be processed 
under 10 CFR 50.80.



Sec. 52.29  Application for renewal.

    (a) Not less than 12, nor more than 36 months before the expiration 
date stated in the early site permit, or any later renewal period, the 
permit holder may apply for a renewal of the permit. An application for 
renewal must contain all information necessary to bring up to date the 
information and data contained in the previous application.
    (b) Any person whose interests may be affected by renewal of the 
permit may request a hearing on the application for renewal. The request 
for a hearing must comply with 10 CFR 2.309. If a hearing is granted, 
notice of the hearing will be published in accordance with 10 CFR 2.309.
    (c) An early site permit, either original or renewed, for which a 
timely application for renewal has been filed, remains in effect until 
the Commission has determined whether to renew the permit. If the permit 
is not renewed, it continues to be valid in certain proceedings in 
accordance with the provisions of Sec. 52.27(b).
    (d) The Commission shall refer a copy of the application for renewal 
to the ACRS. The ACRS shall report on those portions of the application 
which concern safety and shall apply the criteria set forth in Sec. 
52.31.



Sec. 52.31  Criteria for renewal.

    (a) The Commission shall grant the renewal if it determines that:
    (1) The site complies with the Act, the Commission's regulations, 
and orders applicable and in effect at the time the site permit was 
originally issued; and
    (2) Any new requirements the Commission may wish to impose are:
    (i) Necessary for adequate protection to public health and safety or 
common defense and security;
    (ii) Necessary for compliance with the Commission's regulations, and 
orders applicable and in effect at the time the site permit was 
originally issued; or
    (iii) A substantial increase in overall protection of the public 
health and safety or the common defense and security to be derived from 
the new requirements, and the direct and indirect costs of 
implementation of those requirements are justified in view of this 
increased protection.
    (b) A denial of renewal for failure to comply with the provisions of 
Sec. 52.31(a) does not bar the permit holder or another applicant from 
filing a new application for the site which proposes changes to the site 
or the way that it is used to correct the deficiencies cited in the 
denial of the renewal.



Sec. 52.33  Duration of renewal.

    Each renewal of an early site permit may be for not less than 10, 
nor more than 20 years, plus any remaining years on the early site 
permit then in effect before renewal.



Sec. 52.35  Use of site for other purposes.

    A site for which an early site permit has been issued under this 
subpart may be used for purposes other than those described in the 
permit, including the location of other types of energy facilities. The 
permit holder shall inform the Director, Office of New Reactors or 
Director, Office of Nuclear Reactor Regulation, as appropriate, 
(Director) of any significant uses for the site which have not been 
approved in the early site permit. The information about the activities 
must be given to the Director at least 30 days in advance of any actual 
construction or site modification for the activities. The information 
provided could be the basis for imposing new requirements on the permit, 
in accordance with the provisions of Sec. 52.39. If the permit holder 
informs the Director that the holder no longer intends to use the site 
for a nuclear power plant, the Director may terminate the permit.

[73 FR 5724, Jan. 31, 2008]



Sec. 52.39  Finality of early site permit determinations.

    (a) Commission finality. (1) Notwithstanding any provision in 10 CFR 
50.109, while an early site permit is in effect under Sec. Sec. 52.27 
or 52.33, the Commission may not change or impose new site 
characteristics, design parameters, or terms and conditions, including 
emergency planning requirements, on the

[[Page 82]]

early site permit unless the Commission:
    (i) Determines that a modification is necessary to bring the permit 
or the site into compliance with the Commission's regulations and orders 
applicable and in effect at the time the permit was issued;
    (ii) Determines the modification is necessary to assure adequate 
protection of the public health and safety or the common defense and 
security;
    (iii) Determines that a modification is necessary based on an update 
under paragraph (b) of this section; or
    (iv) Issues a variance requested under paragraph (d) of this 
section.
    (2) In making the findings required for issuance of a construction 
permit or combined license, or the findings required by Sec. 52.103, or 
in any enforcement hearing other than one initiated by the Commission 
under paragraph (a)(1) of this section, if the application for the 
construction permit or combined license references an early site permit, 
the Commission shall treat as resolved those matters resolved in the 
proceeding on the application for issuance or renewal of the early site 
permit, except as provided for in paragraphs (b), (c), and (d) of this 
section.
    (i) If the early site permit approved an emergency plan (or major 
features thereof) that is in use by a licensee of a nuclear power plant, 
the Commission shall treat as resolved changes to the early site permit 
emergency plan (or major features thereof) that are identical to changes 
made to the licensee's emergency plans in compliance with Sec. 50.54(q) 
of this chapter occurring after issuance of the early site permit.
    (ii) If the early site permit approved an emergency plan (or major 
features thereof) that is not in use by a licensee of a nuclear power 
plant, the Commission shall treat as resolved changes that are 
equivalent to those that could be made under Sec. 50.54(q) of this 
chapter without prior NRC approval had the emergency plan been in use by 
a licensee.
    (b) Updating of early site permit-emergency preparedness. An 
applicant for a construction permit, operating license, or combined 
license who has filed an application referencing an early site permit 
issued under this subpart shall update the emergency preparedness 
information that was provided under Sec. 52.17(b), and discuss whether 
the updated information materially changes the bases for compliance with 
applicable NRC requirements.
    (c) Hearings and petitions. (1) In any proceeding for the issuance 
of a construction permit, operating license, or combined license 
referencing an early site permit, contentions on the following matters 
may be litigated in the same manner as other issues material to the 
proceeding:
    (i) The nuclear power reactor proposed to be built does not fit 
within one or more of the site characteristics or design parameters 
included in the early site permit;
    (ii) One or more of the terms and conditions of the early site 
permit have not been met;
    (iii) A variance requested under paragraph (d) of this section is 
unwarranted or should be modified;
    (iv) New or additional information is provided in the application 
that substantially alters the bases for a previous NRC conclusion or 
constitutes a sufficient basis for the Commission to modify or impose 
new terms and conditions related to emergency preparedness; or
    (v) Any significant environmental issue that was not resolved in the 
early site permit proceeding, or any issue involving the impacts of 
construction and operation of the facility that was resolved in the 
early site permit proceeding for which significant new information has 
been identified.
    (2) Any person may file a petition requesting that the site 
characteristics, design parameters, or terms and conditions of the early 
site permit should be modified, or that the permit should be suspended 
or revoked. The petition will be considered in accordance with Sec. 
2.206 of this chapter. Before construction commences, the Commission 
shall consider the petition and determine whether any immediate action 
is required. If the petition is granted, an appropriate order will be 
issued. Construction under the construction permit or combined license 
will not be affected by the granting of the petition unless the order is 
made immediately effective. Any change required by the

[[Page 83]]

Commission in response to the petition must meet the requirements of 
paragraph (a)(1) of this section.
    (d) Variances. An applicant for a construction permit, operating 
license, or combined license referencing an early site permit may 
include in its application a request for a variance from one or more 
site characteristics, design parameters, or terms and conditions of the 
early site permit, or from the site safety analysis report. In 
determining whether to grant the variance, the Commission shall apply 
the same technically relevant criteria applicable to the application for 
the original or renewed early site permit. Once a construction permit or 
combined license referencing an early site permit is issued, variances 
from the early site permit will not be granted for that construction 
permit or combined license.
    (e) Early site permit amendment. The holder of an early site permit 
may not make changes to the early site permit, including the site safety 
analysis report, without prior Commission approval. The request for a 
change to the early site permit must be in the form of an application 
for a license amendment, and must meet the requirements of 10 CFR 50.90 
and 50.92.
    (f) Information requests. Except for information requests seeking to 
verify compliance with the current licensing basis of the early site 
permit, information requests to the holder of an early site permit must 
be evaluated before issuance to ensure that the burden to be imposed on 
respondents is justified in view of the potential safety significance of 
the issue to be addressed in the requested information. Each evaluation 
performed by the NRC staff must be in accordance with 10 CFR 50.54(f), 
and must be approved by the Executive Director for Operations or his or 
her designee before issuance of the request.



                Subpart B_Standard Design Certifications



Sec. 52.41  Scope of subpart.

    (a) This subpart sets forth the requirements and procedures 
applicable to Commission issuance of rules granting standard design 
certifications for nuclear power facilities separate from the filing of 
an application for a construction permit or combined license for such a 
facility.
    (b)(1) Any person may seek a standard design certification for an 
essentially complete nuclear power plant design which is an evolutionary 
change from light water reactor designs of plants which have been 
licensed and in commercial operation before April 18, 1989.
    (2) Any person may also seek a standard design certification for a 
nuclear power plant design which differs significantly from the light 
water reactor designs described in paragraph (b)(1) of this section or 
uses simplified, inherent, passive, or other innovative means to 
accomplish its safety functions.



Sec. 52.43  Relationship to other subparts.

    (a) This subpart applies to a person that requests a standard design 
certification from the NRC separately from an application for a combined 
license filed under subpart C of this part for a nuclear power facility. 
An applicant for a combined license may reference a standard design 
certification.
    (b) Subpart E of this part governs the NRC staff review and approval 
of a final standard design. Subpart E may be used independently of the 
provisions in this subpart.
    (c) Subpart F of this part governs the issuance of licenses to 
manufacture nuclear power reactors to be installed and operated at sites 
not identified in the manufacturing license application. Subpart F may 
be used independently of the provisions in this subpart. However, an 
applicant for a manufacturing license under subpart F may reference a 
design certification.



Sec. 52.45  Filing of applications.

    (a) An application for design certification may be filed 
notwithstanding the fact that an application for a construction permit, 
combined license, or manufacturing license for such a facility has not 
been filed.
    (b) The application must comply with the applicable filing 
requirements of Sec. Sec. 52.3 and Sec. Sec. 2.811 through 2.819 of 
this chapter.
    (c) The fees associated with the review of an application for the 
initial

[[Page 84]]

issuance or renewal of a standard design certification are set forth in 
10 CFR part 170.



Sec. 52.46  Contents of applications; general information.

    The application must contain all of the information required by 10 
CFR 50.33(a) through (c) and (j).



Sec. 52.47  Contents of applications; technical information.

    The application must contain a level of design information 
sufficient to enable the Commission to judge the applicant's proposed 
means of assuring that construction conforms to the design and to reach 
a final conclusion on all safety questions associated with the design 
before the certification is granted. The information submitted for a 
design certification must include performance requirements and design 
information sufficiently detailed to permit the preparation of 
acceptance and inspection requirements by the NRC, and procurement 
specifications and construction and installation specifications by an 
applicant. The Commission will require, before design certification, 
that information normally contained in certain procurement 
specifications and construction and installation specifications be 
completed and available for audit if the information is necessary for 
the Commission to make its safety determination.
    (a) The application must contain a final safety analysis report 
(FSAR) that describes the facility, presents the design bases and the 
limits on its operation, and presents a safety analysis of the 
structures, systems, and components and of the facility as a whole, and 
must include the following information:
    (1) The site parameters postulated for the design, and an analysis 
and evaluation of the design in terms of those site parameters;
    (2) A description and analysis of the structures, systems, and 
components (SSCs) of the facility, with emphasis upon performance 
requirements, the bases, with technical justification therefor, upon 
which these requirements have been established, and the evaluations 
required to show that safety functions will be accomplished. It is 
expected that the standard plant will reflect through its design, 
construction, and operation an extremely low probability for accidents 
that could result in the release of significant quantities of 
radioactive fission products. The description shall be sufficient to 
permit understanding of the system designs and their relationship to the 
safety evaluations. Such items as the reactor core, reactor coolant 
system, instrumentation and control systems, electrical systems, 
containment system, other engineered safety features, auxiliary and 
emergency systems, power conversion systems, radioactive waste handling 
systems, and fuel handling systems shall be discussed insofar as they 
are pertinent. The following power reactor design characteristics will 
be taken into consideration by the Commission:
    (i) Intended use of the reactor including the proposed maximum power 
level and the nature and inventory of contained radioactive materials;
    (ii) The extent to which generally accepted engineering standards 
are applied to the design of the reactor;
    (iii) The extent to which the reactor incorporates unique, unusual 
or enhanced safety features having a significant bearing on the 
probability or consequences of accidental release of radioactive 
materials; and
    (iv) The safety features that are to be engineered into the facility 
and those barriers that must be breached as a result of an accident 
before a release of radioactive material to the environment can occur. 
Special attention must be directed to plant design features intended to 
mitigate the radiological consequences of accidents. In performing this 
assessment, an applicant shall assume a fission product release \3\ from 
the core into the containment assuming that the facility is operated at 
the ultimate power level contemplated. The applicant shall perform

[[Page 85]]

an evaluation and analysis of the postulated fission product release, 
using the expected demonstrable containment leak rate and any fission 
product cleanup systems intended to mitigate the consequences of the 
accidents, together with applicable postulated site parameters, 
including site meteorology, to evaluate the offsite radiological 
consequences. The evaluation must determine that:
---------------------------------------------------------------------------

    \3\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. These accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (A) An individual located at any point on the boundary of the 
exclusion area for any 2-hour period following the onset of the 
postulated fission product release, would not receive a radiation dose 
in excess of 25 rem \4\ total effective dose equivalent (TEDE);
---------------------------------------------------------------------------

    \4\ A whole body dose of 25 rem has been stated to correspond 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations at the time 
could be disregarded in the determination of their radiation exposure 
status (see NBS Handbook 69 dated June 5, 1959). However, its use is not 
intended to imply that this number constitutes an acceptable limit for 
an emergency dose to the public under accident conditions. This dose 
value has been set forth in this section as a reference value, which can 
be used in the evaluation of plant design features with respect to 
postulated reactor accidents, to assure that these designs provide 
assurance of low risk of public exposure to radiation, in the event of 
an accident.
---------------------------------------------------------------------------

    (B) An individual located at any point on the outer boundary of the 
low population zone, who is exposed to the radioactive cloud resulting 
from the postulated fission product release (during the entire period of 
its passage) would not receive a radiation dose in excess of 25 rem 
TEDE;
    (3) The design of the facility including:
    (i) The principal design criteria for the facility. Appendix A to 10 
CFR part 50, general design criteria (GDC), establishes minimum 
requirements for the principal design criteria for water-cooled nuclear 
power plants similar in design and location to plants for which 
construction permits have previously been issued by the Commission and 
provides guidance to applicants in establishing principal design 
criteria for other types of nuclear power units;
    (ii) The design bases and the relation of the design bases to the 
principal design criteria;
    (iii) Information relative to materials of construction, general 
arrangement, and approximate dimensions, sufficient to provide 
reasonable assurance that the design will conform to the design bases 
with an adequate margin for safety;
    (4) An analysis and evaluation of the design and performance of 
structures, systems, and components with the objective of assessing the 
risk to public health and safety resulting from operation of the 
facility and including determination of the margins of safety during 
normal operations and transient conditions anticipated during the life 
of the facility, and the adequacy of structures, systems, and components 
provided for the prevention of accidents and the mitigation of the 
consequences of accidents. Analysis and evaluation of emergency core 
cooling system (ECCS) cooling performance and the need for high-point 
vents following postulated loss-of-coolant accidents shall be performed 
in accordance with the requirements of Sec. Sec. 50.46 and 50.46a of 
this chapter;
    (5) The kinds and quantities of radioactive materials expected to be 
produced in the operation and the means for controlling and limiting 
radioactive effluents and radiation exposures within the limits set 
forth in part 20 of this chapter;
    (6) The information required by Sec. 20.1406 of this chapter;
    (7) The technical qualifications of the applicant to engage in the 
proposed activities in accordance with the regulations in this chapter;
    (8) The information necessary to demonstrate compliance with any 
technically relevant portions of the Three Mile Island requirements set 
forth in 10 CFR 50.34(f), except paragraphs (f)(1)(xii), (f)(2)(ix), and 
(f)(3)(v);
    (9) For applications for light-water-cooled nuclear power plants, an 
evaluation of the standard plant design against the Standard Review Plan 
(SRP) revision in effect 6 months before the docket date of the 
application. The evaluation required by this section shall include an 
identification and description of all differences in design

[[Page 86]]

features, analytical techniques, and procedural measures proposed for 
the design and those corresponding features, techniques, and measures 
given in the SRP acceptance criteria. Where a difference exists, the 
evaluation shall discuss how the proposed alternative provides an 
acceptable method of complying with the Commission's regulations, or 
portions thereof, that underlie the corresponding SRP acceptance 
criteria. The SRP is not a substitute for the regulations, and 
compliance is not a requirement.
    (10) The information with respect to the design of equipment to 
maintain control over radioactive materials in gaseous and liquid 
effluents produced during normal reactor operations described in 10 CFR 
50.34a(e);
    (11) Proposed technical specifications prepared in accordance with 
the requirements of Sec. Sec. 50.36 and 50.36a of this chapter;
    (12) An analysis and description of the equipment and systems for 
combustible gas control as required by 10 CFR 50.44;
    (13) The list of electric equipment important to safety that is 
required by 10 CFR 50.49(d);
    (14) A description of protection provided against pressurized 
thermal shock events, including projected values of the reference 
temperature for reactor vessel beltline materials as defined in 10 CFR 
50.60 and 50.61;
    (15) Information demonstrating how the applicant will comply with 
requirements for reduction of risk from anticipated transients without 
scram events in Sec. 50.62;
    (16) A coping analysis, and any design features necessary to address 
station blackout, as required by 10 CFR 50.63;
    (17) Information demonstrating how the applicant will comply with 
requirements for criticality accidents in Sec. 50.68(b)(2)-(b)(4);
    (18) A description and analysis of the fire protection design 
features for the standard plant necessary to comply with 10 CFR part 50, 
appendix A, GDC 3, and Sec. 50.48 of this chapter;
    (19) A description of the quality assurance program applied to the 
design of the structures, systems, and components of the facility. 
Appendix B to 10 CFR part 50, ``Quality Assurance Criteria for Nuclear 
Power Plants and Fuel Reprocessing Plants,'' sets forth the requirements 
for quality assurance programs for nuclear power plants. The description 
of the quality assurance program for a nuclear power plant shall include 
a discussion of how the applicable requirements of appendix B to 10 CFR 
part 50 were satisfied;
    (20) The information necessary to demonstrate that the standard 
plant complies with the earthquake engineering criteria in 10 CFR part 
50, appendix S;
    (21) Proposed technical resolutions of those Unresolved Safety 
Issues and medium- and high-priority generic safety issues which are 
identified in the version of NUREG-0933 current on the date up to 6 
months before the docket date of the application and which are 
technically relevant to the design;
    (22) The information necessary to demonstrate how operating 
experience insights have been incorporated into the plant design;
    (23) For light-water reactor designs, a description and analysis of 
design features for the prevention and mitigation of severe accidents, 
e.g., challenges to containment integrity caused by core-concrete 
interaction, steam explosion, high-pressure core melt ejection, hydrogen 
combustion, and containment bypass;
    (24) A representative conceptual design for those portions of the 
plant for which the application does not seek certification, to aid the 
NRC in its review of the FSAR and to permit assessment of the adequacy 
of the interface requirements in paragraph (a)(25) of this section;
    (25) The interface requirements to be met by those portions of the 
plant for which the application does not seek certification. These 
requirements must be sufficiently detailed to allow completion of the 
FSAR;
    (26) Justification that compliance with the interface requirements 
of paragraph (a)(25) of this section is verifiable through inspections, 
tests, or analyses. The method to be used for verification of interface 
requirements must be included as part of the proposed ITAAC required by 
paragraph (b)(1) of this section; and

[[Page 87]]

    (27) A description of the design-specific probabilistic risk 
assessment (PRA) and its results.
    (28) For applications for standard design certifications which are 
subject to 10 CFR 50.150(a), the information required by 10 CFR 
50.150(b).
    (b) The application must also contain:
    (1) The proposed inspections, tests, analyses, and acceptance 
criteria that are necessary and sufficient to provide reasonable 
assurance that, if the inspections, tests, and analyses are performed 
and the acceptance criteria met, a facility that incorporates the design 
certification has been constructed and will be operated in conformity 
with the design certification, the provisions of the Act, and the 
Commission's rules and regulations; and
    (2) An environmental report as required by 10 CFR 51.55.
    (c) This paragraph applies, according to its provisions, to 
particular applications:
    (1) An application for certification of a nuclear power reactor 
design that is an evolutionary change from light-water reactor designs 
of plants that have been licensed and in commercial operation before 
April 18, 1989, must provide an essentially complete nuclear power plant 
design except for site-specific elements such as the service water 
intake structure and the ultimate heat sink;
    (2) An application for certification of a nuclear power reactor 
design that differs significantly from the light-water reactor designs 
described in paragraph (c)(1) of this section or uses simplified, 
inherent, passive, or other innovative means to accomplish its safety 
functions must provide an essentially complete nuclear power reactor 
design except for site-specific elements such as the service water 
intake structure and the ultimate heat sink, and must meet the 
requirements of 10 CFR 50.43(e); and
    (3) An application for certification of a modular nuclear power 
reactor design must describe and analyze the possible operating 
configurations of the reactor modules with common systems, interface 
requirements, and system interactions. The final safety analysis must 
also account for differences among the configurations, including any 
restrictions that will be necessary during the construction and startup 
of a given module to ensure the safe operation of any module already 
operating.
    (d) Each applicant for a standard design certification under this 
part shall protect Safeguards Information against unauthorized 
disclosure in accordance with the requirements in Sec. Sec. 73.21 and 
73.22 of this chapter, as applicable.

[72 FR 49517, Aug. 28, 2007, as amended at 73 FR 63571, Oct. 24, 2008; 
74 FR 28147, June 12, 2009]



Sec. 52.48  Standards for review of applications.

    Applications filed under this subpart will be reviewed for 
compliance with the standards set out in 10 CFR parts 20, 50 and its 
appendices, 51, 73, and 100.



Sec. 52.51  Administrative review of applications.

    (a) A standard design certification is a rule that will be issued in 
accordance with the provisions of subpart H of 10 CFR part 2, as 
supplemented by the provisions of this section. The Commission shall 
initiate the rulemaking after an application has been filed under Sec. 
52.45 and shall specify the procedures to be used for the rulemaking. 
The notice of proposed rulemaking published in the Federal Register must 
provide an opportunity for the submission of comments on the proposed 
design certification rule. If, at the time a proposed design 
certification rule is published in the Federal Register under this 
paragraph (a), the Commission decides that a legislative hearing should 
be held, the information required by 10 CFR 2.1502(c) must be included 
in the Federal Register document for the proposed design certification.
    (b) Following the submission of comments on the proposed design 
certification rule, the Commission may, at its discretion, hold a 
legislative hearing under the procedures in subpart O of part 2 of this 
chapter. The Commission shall publish a document in the Federal Register 
of its decision to hold a legislative hearing. The document shall 
contain the information

[[Page 88]]

specified in paragraph (c) of this section, and specify whether the 
Commission or a presiding officer will conduct the legislative hearing.
    (c) Notwithstanding anything in 10 CFR 2.390 to the contrary, 
proprietary information will be protected in the same manner and to the 
same extent as proprietary information submitted in connection with 
applications for licenses, provided that the design certification shall 
be published in Chapter I of this title.



Sec. 52.53  Referral to the Advisory Committee on Reactor Safeguards 
(ACRS).

    The Commission shall refer a copy of the application to the ACRS. 
The ACRS shall report on those portions of the application which concern 
safety.



Sec. 52.54  Issuance of standard design certification.

    (a) After conducting a rulemaking proceeding under Sec. 52.51 on an 
application for a standard design certification and receiving the report 
to be submitted by the Advisory Committee on Reactor Safeguards under 
Sec. 52.53, the Commission may issue a standard design certification in 
the form of a rule for the design which is the subject of the 
application, if the Commission determines that:
    (1) The application meets the applicable standards and requirements 
of the Atomic Energy Act and the Commission's regulations;
    (2) Notifications, if any, to other agencies or bodies have been 
duly made;
    (3) There is reasonable assurance that the standard design conforms 
with the provisions of the Act, and the Commission's regulations;
    (4) The applicant is technically qualified;
    (5) The proposed inspections, tests, analyses, and acceptance 
criteria are necessary and sufficient, within the scope of the standard 
design, to provide reasonable assurance that, if the inspections, tests, 
and analyses are performed and the acceptance criteria met, the facility 
has been constructed and will be operated in accordance with the design 
certification, the provisions of the Act, and the Commission's 
regulations;
    (6) Issuance of the standard design certification will not be 
inimical to the common defense and security or to the health and safety 
of the public;
    (7) The findings required by subpart A of part 51 of this chapter 
have been made; and
    (8) The applicant has implemented the quality assurance program 
described or referenced in the safety analysis report.
    (b) The design certification rule must specify the site parameters, 
design characteristics, and any additional requirements and restrictions 
of the design certification rule.
    (c) After the Commission has adopted a final design certification 
rule, the applicant shall not permit any individual to have access to or 
any facility to possess restricted data or classified National Security 
Information until the individual and/or facility has been approved for 
access under the provisions of 10 CFR parts 25 and/or 95, as applicable.



Sec. 52.55  Duration of certification.

    (a) Except as provided in paragraph (b) of this section, a standard 
design certification issued under this subpart is valid for 15 years 
from the date of issuance.
    (b) A standard design certification continues to be valid beyond the 
date of expiration in any proceeding on an application for a combined 
license or an operating license that references the standard design 
certification and is docketed either before the date of expiration of 
the certification, or, if a timely application for renewal of the 
certification has been filed, before the Commission has determined 
whether to renew the certification. A design certification also 
continues to be valid beyond the date of expiration in any hearing held 
under Sec. 52.103 before operation begins under a combined license that 
references the design certification.
    (c) An applicant for a construction permit or a combined license 
may, at its own risk, reference in its application a design for which a 
design certification application has been docketed but not granted.

[[Page 89]]



Sec. 52.57  Application for renewal.

    (a) Not less than 12 nor more than 36 months before the expiration 
of the initial 15-year period, or any later renewal period, any person 
may apply for renewal of the certification. An application for renewal 
must contain all information necessary to bring up to date the 
information and data contained in the previous application. The 
Commission will require, before renewal of certification, that 
information normally contained in certain procurement specifications and 
construction and installation specifications be completed and available 
for audit if this information is necessary for the Commission to make 
its safety determination. Notice and comment procedures must be used for 
a rulemaking proceeding on the application for renewal. The Commission, 
in its discretion, may require the use of additional procedures in 
individual renewal proceedings.
    (b) A design certification, either original or renewed, for which a 
timely application for renewal has been filed remains in effect until 
the Commission has determined whether to renew the certification. If the 
certification is not renewed, it continues to be valid in certain 
proceedings, in accordance with the provisions of Sec. 52.55.
    (c) The Commission shall refer a copy of the application for renewal 
to the Advisory Committee on Reactor Safeguards (ACRS). The ACRS shall 
report on those portions of the application which concern safety and 
shall apply the criteria set forth in Sec. 52.59.



Sec. 52.59  Criteria for renewal.

    (a) The Commission shall issue a rule granting the renewal if the 
design, either as originally certified or as modified during the 
rulemaking on the renewal, complies with the Atomic Energy Act and the 
Commission's regulations applicable and in effect at the time the 
certification was issued, provided, however, that the first time the 
Commission issues a rule granting the renewal for a standard design 
certification in effect on July 13, 2009, the Commission shall, in 
addition, find that the renewed design complies with the applicable 
requirements of 10 CFR 50.150.
    (b) The Commission may impose other requirements if it determines 
that:
    (1) They are necessary for adequate protection to public health and 
safety or common defense and security;
    (2) They are necessary for compliance with the Commission's 
regulations and orders applicable and in effect at the time the design 
certification was issued; or
    (3) There is a substantial increase in overall protection of the 
public health and safety or the common defense and security to be 
derived from the new requirements, and the direct and indirect costs of 
implementing those requirements are justified in view of this increased 
protection.
    (c) In addition, the applicant for renewal may request an amendment 
to the design certification. The Commission shall grant the amendment 
request if it determines that the amendment will comply with the Atomic 
Energy Act and the Commission's regulations in effect at the time of 
renewal. If the amendment request entails such an extensive change to 
the design certification that an essentially new standard design is 
being proposed, an application for a design certification must be filed 
in accordance with this subpart.
    (d) Denial of renewal does not bar the applicant, or another 
applicant, from filing a new application for certification of the 
design, which proposes design changes that correct the deficiencies 
cited in the denial of the renewal.

[72 FR 49517, Aug. 28, 2007, as amended at 74 FR 28147, June 12, 2009]



Sec. 52.61  Duration of renewal.

    Each renewal of certification for a standard design will be for not 
less than 10, nor more than 15 years.



Sec. 52.63  Finality of standard design certifications.

    (a)(1) Notwithstanding any provision in 10 CFR 50.109, while a 
standard design certification rule is in effect under Sec. Sec. 52.55 
or 52.61, the Commission may not modify, rescind, or impose new 
requirements on the certification information, whether on its own 
motion, or

[[Page 90]]

in response to a petition from any person, unless the Commission 
determines in a rulemaking that the change:
    (i) Is necessary either to bring the certification information or 
the referencing plants into compliance with the Commission's regulations 
applicable and in effect at the time the certification was issued;
    (ii) Is necessary to provide adequate protection of the public 
health and safety or the common defense and security;
    (iii) Reduces unnecessary regulatory burden and maintains protection 
to public health and safety and the common defense and security;
    (iv) Provides the detailed design information to be verified under 
those inspections, tests, analyses, and acceptance criteria (ITAAC) 
which are directed at certification information (i.e., design acceptance 
criteria);
    (v) Is necessary to correct material errors in the certification 
information;
    (vi) Substantially increases overall safety, reliability, or 
security of facility design, construction, or operation, and the direct 
and indirect costs of implementation of the rule change are justified in 
view of this increased safety, reliability, or security; or
    (vii) Contributes to increased standardization of the certification 
information.
    (2)(i) In a rulemaking under Sec. 52.63(a)(1), except for Sec. 
52.63(a)(1)(ii), the Commission will give consideration to whether the 
benefits justify the costs for plants that are already licensed or for 
which an application for a permit or license is under consideration.
    (ii) The rulemaking procedures for changes under Sec. 52.63(a)(1) 
must provide for notice and opportunity for public comment.
    (3) Any modification the NRC imposes on a design certification rule 
under paragraph (a)(1) of this section will be applied to all plants 
referencing the certified design, except those to which the modification 
has been rendered technically irrelevant by action taken under 
paragraphs (a)(4) or (b)(1) of this section.
    (4) The Commission may not impose new requirements by plant-specific 
order on any part of the design of a specific plant referencing the 
design certification rule if that part was approved in the design 
certification while a design certification rule is in effect under Sec. 
52.55 or Sec. 52.61, unless:
    (i) A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time the 
certification was issued, or to assure adequate protection of the public 
health and safety or the common defense and security; and
    (ii) Special circumstances as defined in 10 CFR 52.7 are present. In 
addition to the factors listed in Sec. 52.7, the Commission shall 
consider whether the special circumstances which Sec. 52.7 requires to 
be present outweigh any decrease in safety that may result from the 
reduction in standardization caused by the plant-specific order.
    (5) Except as provided in 10 CFR 2.335, in making the findings 
required for issuance of a combined license, construction permit, 
operating license, or manufacturing license, or for any hearing under 
Sec. 52.103, the Commission shall treat as resolved those matters 
resolved in connection with the issuance or renewal of a design 
certification rule.
    (b)(1) An applicant or licensee who references a design 
certification rule may request an exemption from one or more elements of 
the certification information. The Commission may grant such a request 
only if it determines that the exemption will comply with the 
requirements of Sec. 52.7. In addition to the factors listed in Sec. 
52.7, the Commission shall consider whether the special circumstances 
that Sec. 52.7 requires to be present outweigh any decrease in safety 
that may result from the reduction in standardization caused by the 
exemption. The granting of an exemption on request of an applicant is 
subject to litigation in the same manner as other issues in the 
operating license or combined license hearing.
    (2) Subject to Sec. 50.59 of this chapter, a licensee who 
references a design certification rule may make departures from the 
design of the nuclear power facility, without prior Commission approval, 
unless the proposed departure involves a change to the design as 
described in the rule certifying the design. The licensee shall maintain

[[Page 91]]

records of all departures from the facility and these records must be 
maintained and available for audit until the date of termination of the 
license.
    (c) The Commission will require, before granting a construction 
permit, combined license, operating license, or manufacturing license 
which references a design certification rule, that information normally 
contained in certain procurement specifications and construction and 
installation specifications be completed and available for audit if the 
information is necessary for the Commission to make its safety 
determinations, including the determination that the application is 
consistent with the certification information. This information may be 
acquired by appropriate arrangements with the design certification 
applicant.



                       Subpart C_Combined Licenses



Sec. 52.71  Scope of subpart.

    This subpart sets out the requirements and procedures applicable to 
Commission issuance of combined licenses for nuclear power facilities.



Sec. 52.73  Relationship to other subparts.

    (a) An application for a combined license under this subpart may, 
but need not, reference a standard design certification, standard design 
approval, or manufacturing license issued under subparts B, E, or F of 
this part, respectively, or an early site permit issued under subpart A 
of this part. In the absence of a demonstration that an entity other 
than the one originally sponsoring and obtaining a design certification 
is qualified to supply a design, the Commission will entertain an 
application for a combined license that references a standard design 
certification issued under subpart B of this part only if the entity 
that sponsored and obtained the certification supplies the design for 
the applicant's use.
    (b) The Commission will require, before granting a combined license 
that references a standard design certification, that information 
normally contained in certain procurement specifications and 
construction and installation specifications be completed and available 
for audit if the information is necessary for the Commission to make its 
safety determinations, including the determination that the application 
is consistent with the certification information.



Sec. 52.75  Filing of applications.

    (a) Any person except one excluded by Sec. 50.38 of this chapter 
may file an application for a combined license for a nuclear power 
facility with the Director, Office of New Reactors or Director, Office 
of Nuclear Reactor Regulation, as appropriate.
    (b) The application must comply with the applicable filing 
requirements of Sec. Sec. 52.3 and 50.30 of this chapter.
    (c) The fees associated with the filing and review of the 
application are set forth in 10 CFR part 170.

[72 FR 49517, Aug. 28, 2007, as amended at 73 FR 5724, Jan. 31, 2008]



Sec. 52.77  Contents of applications; general information.

    The application must contain all of the information required by 10 
CFR 50.33.



Sec. 52.79  Contents of applications; technical information in final
safety analysis report.

    (a) The application must contain a final safety analysis report that 
describes the facility, presents the design bases and the limits on its 
operation, and presents a safety analysis of the structures, systems, 
and components of the facility as a whole. The final safety analysis 
report shall include the following information, at a level of 
information sufficient to enable the Commission to reach a final 
conclusion on all safety matters that must be resolved by the Commission 
before issuance of a combined license:
    (1)(i) The boundaries of the site;
    (ii) The proposed general location of each facility on the site;
    (iii) The seismic, meteorological, hydrologic, and geologic 
characteristics of the proposed site with appropriate consideration of 
the most severe of the natural phenomena that have been historically 
reported for the site and surrounding area and with sufficient margin 
for the limited accuracy, quantity, and time in which the historical 
data have been accumulated;

[[Page 92]]

    (iv) The location and description of any nearby industrial, 
military, or transportation facilities and routes;
    (v) The existing and projected future population profile of the area 
surrounding the site;
    (vi) A description and safety assessment of the site on which the 
facility is to be located. The assessment must contain an analysis and 
evaluation of the major structures, systems, and components of the 
facility that bear significantly on the acceptability of the site under 
the radiological consequence evaluation factors identified in paragraphs 
(a)(1)(vi)(A) and (a)(1)(vi)(B) of this section. In performing this 
assessment, an applicant shall assume a fission product release \5\ from 
the core into the containment assuming that the facility is operated at 
the ultimate power level contemplated. The applicant shall perform an 
evaluation and analysis of the postulated fission product release, using 
the expected demonstrable containment leak rate and any fission product 
cleanup systems intended to mitigate the consequences of the accidents, 
together with applicable site characteristics, including site 
meteorology, to evaluate the offsite radiological consequences. Site 
characteristics must comply with part 100 of this chapter. The 
evaluation must determine that:
---------------------------------------------------------------------------

    \5\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. These accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (A) An individual located at any point on the boundary of the 
exclusion area for any 2-hour period following the onset of the 
postulated fission product release, would not receive a radiation dose 
in excess of 25 rem \6\ total effective dose equivalent (TEDE).
---------------------------------------------------------------------------

    \6\ A whole body dose of 25 rem has been stated to correspond 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations at the time 
could be disregarded in the determination of their radiation exposure 
status (see NBS Handbook 69 dated June 5, 1959). However, its use is not 
intended to imply that this number constitutes an acceptable limit for 
an emergency dose to the public under accident conditions. Rather, this 
dose value has been set forth in this section as a reference value, 
which can be used in the evaluation of plant design features with 
respect to postulated reactor accidents, to assure that these designs 
provide assurance of low risk of public exposure to radiation, in the 
event of an accident.
---------------------------------------------------------------------------

    (B) An individual located at any point on the outer boundary of the 
low population zone, who is exposed to the radioactive cloud resulting 
from the postulated fission product release (during the entire period of 
its passage) would not receive a radiation dose in excess of 25 rem 
TEDE; and
    (2) A description and analysis of the structures, systems, and 
components of the facility with emphasis upon performance requirements, 
the bases, with technical justification therefor, upon which these 
requirements have been established, and the evaluations required to show 
that safety functions will be accomplished. It is expected that reactors 
will reflect through their design, construction, and operation an 
extremely low probability for accidents that could result in the release 
of significant quantities of radioactive fission products. The 
descriptions shall be sufficient to permit understanding of the system 
designs and their relationship to safety evaluations. Items such as the 
reactor core, reactor coolant system, instrumentation and control 
systems, electrical systems, containment system, other engineered safety 
features, auxiliary and emergency systems, power conversion systems, 
radioactive waste handling systems, and fuel handling systems shall be 
discussed insofar as they are pertinent. The following power reactor 
design characteristics and proposed operation will be taken into 
consideration by the Commission:
    (i) Intended use of the reactor including the proposed maximum power 
level and the nature and inventory of contained radioactive materials;
    (ii) The extent to which generally accepted engineering standards 
are applied to the design of the reactor;

[[Page 93]]

    (iii) The extent to which the reactor incorporates unique, unusual 
or enhanced safety features having a significant bearing on the 
probability or consequences of accidental release of radioactive 
materials;
    (iv) The safety features that are to be engineered into the facility 
and those barriers that must be breached as a result of an accident 
before a release of radioactive material to the environment can occur. 
Special attention must be directed to plant design features intended to 
mitigate the radiological consequences of accidents. In performing this 
assessment, an applicant shall assume a fission product release \7\ from 
the core into the containment assuming that the facility is operated at 
the ultimate power level contemplated;
---------------------------------------------------------------------------

    \7\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. These accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (3) The kinds and quantities of radioactive materials expected to be 
produced in the operation and the means for controlling and limiting 
radioactive effluents and radiation exposures within the limits set 
forth in part 20 of this chapter;
    (4) The design of the facility including:
    (i) The principal design criteria for the facility. Appendix A to 
part 50 of this chapter, ``General Design Criteria for Nuclear Power 
Plants,'' establishes minimum requirements for the principal design 
criteria for water-cooled nuclear power plants similar in design and 
location to plants for which construction permits have previously been 
issued by the Commission and provides guidance to applicants in 
establishing principal design criteria for other types of nuclear power 
units;
    (ii) The design bases and the relation of the design bases to the 
principal design criteria;
    (iii) Information relative to materials of construction, 
arrangement, and dimensions, sufficient to provide reasonable assurance 
that the design will conform to the design bases with adequate margin 
for safety.
    (5) An analysis and evaluation of the design and performance of 
structures, systems, and components with the objective of assessing the 
risk to public health and safety resulting from operation of the 
facility and including determination of the margins of safety during 
normal operations and transient conditions anticipated during the life 
of the facility, and the adequacy of structures, systems, and components 
provided for the prevention of accidents and the mitigation of the 
consequences of accidents. Analysis and evaluation of ECCS cooling 
performance and the need for high-point vents following postulated loss-
of-coolant accidents shall be performed in accordance with the 
requirements of Sec. Sec. 50.46 and 50.46a of this chapter;
    (6) A description and analysis of the fire protection design 
features for the reactor necessary to comply with 10 CFR part 50, 
appendix A, GDC 3, and Sec. 50.48 of this chapter;
    (7) A description of protection provided against pressurized thermal 
shock events, including projected values of the reference temperature 
for reactor vessel beltline materials as defined in Sec. Sec. 50.60 and 
50.61(b)(1) and (b)(2) of this chapter;
    (8) An analysis and description of the equipment and systems for 
combustible gas control as required by Sec. 50.44 of this chapter;
    (9) The coping analyses, and any design features necessary to 
address station blackout, as described in Sec. 50.63 of this chapter;
    (10) A description of the program, and its implementation, required 
by Sec. 50.49(a) of this chapter for the environmental qualification of 
electric equipment important to safety and the list of electric 
equipment important to safety that is required by 10 CFR 50.49(d);
    (11) A description of the program(s), and their implementation, 
necessary to ensure that the systems and components meet the 
requirements of the ASME Boiler and Pressure Vessel Code and the ASME 
Code for Operation and Maintenance of Nuclear Power Plants in accordance 
with 50.55a of this chapter;

[[Page 94]]

    (12) A description of the primary containment leakage rate testing 
program, and its implementation, necessary to ensure that the 
containment meets the requirements of appendix J to 10 CFR part 50;
    (13) A description of the reactor vessel material surveillance 
program required by appendix H to 10 CFR part 50 and its implementation;
    (14) A description of the operator training program, and its 
implementation, necessary to meet the requirements of 10 CFR part 55;
    (15) A description of the program, and its implementation, for 
monitoring the effectiveness of maintenance necessary to meet the 
requirements of Sec. 50.65 of this chapter;
    (16)(i) The information with respect to the design of equipment to 
maintain control over radioactive materials in gaseous and liquid 
effluents produced during normal reactor operations, as described in 
Sec. 50.34a(d) of this chapter;
    (ii) A description of the process and effluent monitoring and 
sampling program required by appendix I to 10 CFR part 50 and its 
implementation.
    (17) The information with respect to compliance with technically 
relevant positions of the Three Mile Island requirements in Sec. 
50.34(f) of this chapter, with the exception of Sec. 50.34(f)(1)(xii), 
(f)(2)(ix), (f)(2)(xxv), and (f)(3)(v);
    (18) If the applicant seeks to use risk-informed treatment of SSCs 
in accordance with Sec. 50.69 of this chapter, the information required 
by Sec. 50.69(b)(2) of this chapter;
    (19) Information necessary to demonstrate that the plant complies 
with the earthquake engineering criteria in 10 CFR part 50, appendix S;
    (20) Proposed technical resolutions of those Unresolved Safety 
Issues and medium- and high-priority generic safety issues which are 
identified in the version of NUREG-0933 current on the date up to 6 
months before the docket date of the application and which are 
technically relevant to the design;
    (21) Emergency plans complying with the requirements of Sec. 50.47 
of this chapter, and 10 CFR part 50, appendix E;
    (22)(i) All emergency plan certifications that have been obtained 
from the State and local governmental agencies with emergency planning 
responsibilities must state that:
    (A) The proposed emergency plans are practicable;
    (B) These agencies are committed to participating in any further 
development of the plans, including any required field demonstrations; 
and
    (C) These agencies are committed to executing their responsibilities 
under the plans in the event of an emergency;
    (ii) If certifications cannot be obtained after sustained, good 
faith efforts by the applicant, then the application must contain 
information, including a utility plan, sufficient to show that the 
proposed plans provide reasonable assurance that adequate protective 
measures can and will be taken in the event of a radiological emergency 
at the site.
    (23) [Reserved]
    (24) If the application is for a nuclear power reactor design which 
differs significantly from light-water reactor designs that were 
licensed before 1997 or use simplified, inherent, passive, or other 
innovative means to accomplish their safety functions, the application 
must describe how the design meets the requirements in Sec. 50.43(e) of 
this chapter;
    (25) A description of the quality assurance program, applied to the 
design, and to be applied to the fabrication, construction, and testing, 
of the structures, systems, and components of the facility. Appendix B 
to 10 CFR part 50 sets forth the requirements for quality assurance 
programs for nuclear power plants. The description of the quality 
assurance program for a nuclear power plant must include a discussion of 
how the applicable requirements of appendix B to 10 CFR part 50 have 
been and will be satisfied, including a discussion of how the quality 
assurance program will be implemented;
    (26) The applicant's organizational structure, allocations or 
responsibilities and authorities, and personnel qualifications 
requirements for operation;
    (27) Managerial and administrative controls to be used to assure 
safe operation. Appendix B to 10 CFR part 50 sets forth the requirements 
for these controls for nuclear power plants. The information on the 
controls to be used

[[Page 95]]

for a nuclear power plant shall include a discussion of how the 
applicable requirements of appendix B to 10 CFR part 50 will be 
satisfied;
    (28) Plans for preoperational testing and initial operations;
    (29)(i) Plans for conduct of normal operations, including 
maintenance, surveillance, and periodic testing of structures, systems, 
and components;
    (ii) Plans for coping with emergencies, other than the plans 
required by Sec. 52.79(a)(21);
    (30) Proposed technical specifications prepared in accordance with 
the requirements of Sec. Sec. 50.36 and 50.36a of this chapter;
    (31) For nuclear power plants to be operated on multi-unit sites, an 
evaluation of the potential hazards to the structures, systems, and 
components important to safety of operating units resulting from 
construction activities, as well as a description of the managerial and 
administrative controls to be used to provide assurance that the 
limiting conditions for operation are not exceeded as a result of 
construction activities at the multi-unit sites;
    (32) The technical qualifications of the applicant to engage in the 
proposed activities in accordance with the regulations in this chapter;
    (33) A description of the training program required by Sec. 50.120 
of this chapter and its implementation;
    (34) A description and plans for implementation of an operator 
requalification program. The operator requalification program must as a 
minimum, meet the requirements for those programs contained in Sec. 
55.59 of this chapter;
    (35)(i) A physical security plan, describing how the applicant will 
meet the requirements of 10 CFR part 73 (and 10 CFR part 11, if 
applicable, including the identification and description of jobs as 
required by Sec. 11.11(a) of this chapter, at the proposed facility). 
The plan must list tests, inspections, audits, and other means to be 
used to demonstrate compliance with the requirements of 10 CFR parts 11 
and 73, if applicable;
    (ii) A description of the implementation of the physical security 
plan;
    (36)(i) A safeguards contingency plan in accordance with the 
criteria set forth in appendix C to 10 CFR part 73. The safeguards 
contingency plan shall include plans for dealing with threats, thefts, 
and radiological sabotage, as defined in part 73 of this chapter, 
relating to the special nuclear material and nuclear facilities licensed 
under this chapter and in the applicant's possession and control. Each 
application for this type of license shall include the information 
contained in the applicant's safeguards contingency plan. \8\ 
(Implementing procedures required for this plan need not be submitted 
for approval.)
---------------------------------------------------------------------------

    \8\ A physical security plan that contains all the information 
required in both Sec. 73.55 of this chapter and appendix C to 10 CFR 
part 73 satisfies the requirement for a contingency plan.
---------------------------------------------------------------------------

    (ii) A training and qualification plan in accordance with the 
criteria set forth in appendix B to 10 CFR part 73.
    (iii) A cyber security plan in accordance with the criteria set 
forth in Sec. 73.54 of this chapter;
    (iv) A description of the implementation of the safeguards 
contingency plan, training and qualification plan, and cyber security 
plan; and
    (v) Each applicant who prepares a physical security plan, a 
safeguards contingency plan, a training and qualification plan, or a 
cyber security plan, shall protect the plans and other related 
Safeguards Information against unauthorized disclosure in accordance 
with the requirements of Sec. 73.21 of this chapter.
    (37) The information necessary to demonstrate how operating 
experience insights have been incorporated into the plant design;
    (38) For light-water reactor designs, a description and analysis of 
design features for the prevention and mitigation of severe accidents, 
e.g., challenges to containment integrity caused by core-concrete 
interaction, steam explosion, high-pressure core melt ejection, hydrogen 
combustion, and containment bypass;
    (39) A description of the radiation protection program required by 
Sec. 20.1101 of this chapter and its implementation.
    (40) A description of the fire protection program required by Sec. 
50.48 of this chapter and its implementation.

[[Page 96]]

    (41) For applications for light-water-cooled nuclear power plant 
combined licenses, an evaluation of the facility against the Standard 
Review Plan (SRP) revision in effect 6 months before the docket date of 
the application. The evaluation required by this section shall include 
an identification and description of all differences in design features, 
analytical techniques, and procedural measures proposed for a facility 
and those corresponding features, techniques, and measures given in the 
SRP acceptance criteria. Where a difference exists, the evaluation shall 
discuss how the proposed alternative provides an acceptable method of 
complying with the Commission's regulations, or portions thereof, that 
underlie the corresponding SRP acceptance criteria. The SRP is not a 
substitute for the regulations, and compliance is not a requirement;
    (42) Information demonstrating how the applicant will comply with 
requirements for reduction of risk from anticipated transients without 
scram (ATWS) events in Sec. 50.62 of this chapter;
    (43) Information demonstrating how the applicant will comply with 
requirements for criticality accidents in Sec. 50.68 of this chapter;
    (44) A description of the fitness-for-duty program required by 10 
CFR part 26 and its implementation.
    (45) The information required by Sec. 20.1406 of this chapter.
    (46) A description of the plant-specific probabilistic risk 
assessment (PRA) and its results.
    (47) For applications for combined licenses which are subject to 10 
CFR 50.150(a), the information required by 10 CFR 50.150(b).
    (b) If the combined license application references an early site 
permit, then the following requirements apply:
    (1) The final safety analysis report need not contain information or 
analyses submitted to the Commission in connection with the early site 
permit, provided, however, that the final safety analysis report must 
either include or incorporate by reference the early site permit site 
safety analysis report and must contain, in addition to the information 
and analyses otherwise required, information sufficient to demonstrate 
that the design of the facility falls within the site characteristics 
and design parameters specified in the early site permit.
    (2) If the final safety analysis report does not demonstrate that 
design of the facility falls within the site characteristics and design 
parameters, the application shall include a request for a variance that 
complies with the requirements of Sec. Sec. 52.39 and 52.93.
    (3) The final safety analysis report must demonstrate that all terms 
and conditions that have been included in the early site permit, other 
than those imposed under Sec. 50.36b, will be satisfied by the date of 
issuance of the combined license. Any terms or conditions of the early 
site permit that could not be met by the time of issuance of the 
combined license, must be set forth as terms or conditions of the 
combined license.
    (4) If the early site permit approves complete and integrated 
emergency plans, or major features of emergency plans, then the final 
safety analysis report must include any new or additional information 
that updates and corrects the information that was provided under Sec. 
52.17(b), and discuss whether the new or additional information 
materially changes the bases for compliance with the applicable 
requirements. The application must identify changes to the emergency 
plans or major features of emergency plans that have been incorporated 
into the proposed facility emergency plans and that constitute or would 
constitute a reduction in effectiveness under Sec. 50.54(q) of this 
chapter.
    (5) If complete and integrated emergency plans are approved as part 
of the early site permit, new certifications meeting the requirements of 
paragraph (a)(22) of this section are not required.
    (c) If the combined license application references a standard design 
approval, then the following requirements apply:
    (1) The final safety analysis report need not contain information or 
analyses submitted to the Commission in connection with the design 
approval, provided, however, that the final safety analysis report must 
either include or incorporate by reference the standard design approval 
final safety analysis report and must contain, in addition to

[[Page 97]]

the information and analyses otherwise required, information sufficient 
to demonstrate that the characteristics of the site fall within the site 
parameters specified in the design approval. In addition, the plant-
specific PRA information must use the PRA information for the design 
approval and must be updated to account for site-specific design 
information and any design changes or departures.
    (2) The final safety analysis report must demonstrate that all terms 
and conditions that have been included in the final design approval will 
be satisfied by the date of issuance of the combined license.
    (d) If the combined license application references a standard design 
certification, then the following requirements apply:
    (1) The final safety analysis report need not contain information or 
analyses submitted to the Commission in connection with the design 
certification, provided, however, that the final safety analysis report 
must either include or incorporate by reference the standard design 
certification final safety analysis report and must contain, in addition 
to the information and analyses otherwise required, information 
sufficient to demonstrate that the site characteristics fall within the 
site parameters specified in the design certification. In addition, the 
plant-specific PRA information must use the PRA information for the 
design certification and must be updated to account for site-specific 
design information and any design changes or departures.
    (2) The final safety analysis report must demonstrate that the 
interface requirements established for the design under Sec. 52.47 have 
been met.
    (3) The final safety analysis report must demonstrate that all 
requirements and restrictions set forth in the referenced design 
certification rule, other than those imposed under Sec. 50.36b, must be 
satisfied by the date of issuance of the combined license. Any 
requirements and restrictions set forth in the referenced design 
certification rule that could not be satisfied by the time of issuance 
of the combined license, must be set forth as terms or conditions of the 
combined license.
    (e) If the combined license application references the use of one or 
more manufactured nuclear power reactors licensed under subpart F of 
this part, then the following requirements apply:
    (1) The final safety analysis report need not contain information or 
analyses submitted to the Commission in connection with the 
manufacturing license, provided, however, that the final safety analysis 
report must either include or incorporate by reference the manufacturing 
license final safety analysis report and must contain, in addition to 
the information and analyses otherwise required, information sufficient 
to demonstrate that the site characteristics fall within the site 
parameters specified in the manufacturing license. In addition, the 
plant-specific PRA information must use the PRA information for the 
manufactured reactor and must be updated to account for site-specific 
design information and any design changes or departures.
    (2) The final safety analysis report must demonstrate that the 
interface requirements established for the design have been met.
    (3) The final safety analysis report must demonstrate that all terms 
and conditions that have been included in the manufacturing license, 
other than those imposed under Sec. 50.36b, will be satisfied by the 
date of issuance of the combined license. Any terms or conditions of the 
manufacturing license that could not be met by the time of issuance of 
the combined license, must be set forth as terms or conditions of the 
combined license.
    (f) Each applicant for a combined license under this subpart shall 
protect Safeguards Information against unauthorized disclosure in 
accordance with the requirements in Sec. Sec. 73.21 and 73.22 of this 
chapter, as applicable.

[72 FR 49517, Aug. 28, 2007, as amended at 73 FR 63571, Oct. 24, 2008; 
74 FR 13970, Mar. 27, 2009; 74 FR 28147, June 12, 2009; 76 FR 72600, 
Nov. 23, 2011; 78 FR 34249, June 7, 2013]



Sec. 52.80  Contents of applications; additional technical information.

    The application must contain:

[[Page 98]]

    (a) The proposed inspections, tests, and analyses, including those 
applicable to emergency planning, that the licensee shall perform, and 
the acceptance criteria that are necessary and sufficient to provide 
reasonable assurance that, if the inspections, tests, and analyses are 
performed and the acceptance criteria met, the facility has been 
constructed and will be operated in conformity with the combined 
license, the provisions of the Act, and the Commission's rules and 
regulations.
    (1) If the application references an early site permit with ITAAC, 
the early site permit ITAAC must apply to those aspects of the combined 
license which are approved in the early site permit.
    (2) If the application references a standard design certification, 
the ITAAC contained in the certified design must apply to those portions 
of the facility design which are approved in the design certification.
    (3) If the application references an early site permit with ITAAC or 
a standard design certification or both, the application may include a 
notification that a required inspection, test, or analysis in the ITAAC 
has been successfully completed and that the corresponding acceptance 
criterion has been met. The Federal Register notification required by 
Sec. 52.85 must indicate that the application includes this 
notification.
    (b) An environmental report, either in accordance with 10 CFR 
51.50(c) if a limited work authorization under 10 CFR 50.10 is not 
requested in conjunction with the combined license application, or in 
accordance with Sec. Sec. 51.49 and 51.50(c) of this chapter if a 
limited work authorization is requested in conjunction with the combined 
license application.
    (c) If the applicant wishes to request that a limited work 
authorization under 10 CFR 50.10 be issued before issuance of the 
combined license, the application must include the information otherwise 
required by 10 CFR 50.10, in accordance with either 10 CFR 2.101(a)(1) 
through (a)(4), or 10 CFR 2.101(a)(9).
    (d) A description and plans for implementation of the guidance and 
strategies intended to maintain or restore core cooling, containment, 
and spent fuel pool cooling capabilities under the circumstances 
associated with the loss of large areas of the plant due to explosions 
or fire as required by Sec. 50.54(hh)(2) of this chapter.

[72 FR 49517, Aug. 28, 2007, as amended at 72 FR 57447, Oct. 9, 2007; 74 
FR 13970, Mar. 27, 2009]



Sec. 52.81  Standards for review of applications.

    Applications filed under this subpart will be reviewed according to 
the standards set out in 10 CFR parts 20, 50, 51, 54, 55, 73, 100, and 
140.



Sec. 52.83  Finality of referenced NRC approvals; partial initial
decision on site suitability.

    (a) If the application for a combined license under this subpart 
references an early site permit, design certification rule, standard 
design approval, or manufacturing license, the scope and nature of 
matters resolved for the application and any combined license issued are 
governed by the relevant provisions addressing finality, including 
Sec. Sec. 52.39, 52.63, 52.98, 52.145, and 52.171.
    (b) While a partial decision on site suitability is in effect under 
10 CFR 2.617(b)(2), the scope and nature of matters resolved in the 
proceeding are governed by the finality provisions in 10 CFR 2.629.



Sec. 52.85  Administrative review of applications; hearings.

    A proceeding on a combined license is subject to all applicable 
procedural requirements contained in 10 CFR part 2, including the 
requirements for docketing (Sec. 2.101 of this chapter) and issuance of 
a notice of hearing (Sec. 2.104 of this chapter). If an applicant 
requests a Commission finding on certain ITAAC with the issuance of the 
combined license, then those ITAAC will be identified in the notice of 
hearing. All hearings on combined licenses are governed by the 
procedures contained in 10 CFR part 2.



Sec. 52.87  Referral to the Advisory Committee on Reactor Safeguards
(ACRS).

    The Commission shall refer a copy of the application to the ACRS. 
The

[[Page 99]]

ACRS shall report on those portions of the application that concern 
safety and shall apply the standards referenced in Sec. 52.81, in 
accordance with the finality provisions in Sec. 52.83.



Sec. 52.89  [Reserved]



Sec. 52.91  Authorization to conduct limited work authorization 
activities.

    (a) If the application does not reference an early site permit which 
authorizes the holder to perform the activities under 10 CFR 50.10(d), 
the applicant may not perform those activities without obtaining the 
separate authorization required by 10 CFR 50.10(d). Authorization may be 
granted only after the presiding officer in the proceeding on the 
application has made the findings and determination required by 10 CFR 
50.10(e), and the Director of New Reactors or the Director of Nuclear 
Reactor Regulation makes the determination required by 10 CFR 50.10(e).
    (b) If, after an applicant has performed the activities permitted by 
paragraph (a) of this section, the application for the combined license 
is withdrawn or denied, then the applicant shall implement the approved 
site redress plan.

[72 FR 57447, Oct. 9, 2007]



Sec. 52.93  Exemptions and variances.

    (a) Applicants for a combined license under this subpart, or any 
amendment to a combined license, may include in the application a 
request for an exemption from one or more of the Commission's 
regulations.
    (1) If the request is for an exemption from any part of a referenced 
design certification rule, the Commission may grant the request if it 
determines that the exemption complies with any exemption provisions of 
the referenced design certification rule, or with Sec. 52.63 if there 
are no applicable exemption provisions in the referenced design 
certification rule.
    (2) For all other requests for exemptions, the Commission may grant 
a request if it determines that the exemption complies with Sec. 52.7.
    (b) An applicant for a combined license who has filed an application 
referencing an early site permit issued under subpart A of this part may 
include in the application a request for a variance from one or more 
site characteristics, design parameters, or terms and conditions of the 
permit, or from the site safety analysis report. In determining whether 
to grant the variance, the Commission shall apply the same technically 
relevant criteria as were applicable to the application for the original 
or renewed site permit. Once a construction permit or combined license 
referencing an early site permit is issued, variances from the early 
site permit will not be granted for that construction permit or combined 
license.
    (c) An applicant for a combined license who has filed an application 
referencing a nuclear power reactor manufactured under a manufacturing 
license issued under subpart F of this part may include in the 
application a request for a departure from one or more design 
characteristics, site parameters, terms and conditions, or approved 
design of the manufactured reactor. The Commission may grant a request 
only if it determines that the departure will comply with the 
requirements of 10 CFR 52.7, and that the special circumstances outweigh 
any decrease in safety that may result from the reduction in 
standardization caused by the departure.
    (d) Issuance of a variance under paragraph (b) or a departure under 
paragraph (c) of this section is subject to litigation during the 
combined license proceeding in the same manner as other issues material 
to that proceeding.



Sec. 52.97  Issuance of combined licenses.

    (a)(1) After conducting a hearing in accordance with Sec. 52.85 and 
receiving the report submitted by the ACRS, the Commission may issue a 
combined license if the Commission finds that:
    (i) The applicable standards and requirements of the Act and the 
Commission's regulations have been met;
    (ii) Any required notifications to other agencies or bodies have 
been duly made;
    (iii) There is reasonable assurance that the facility will be 
constructed and will operate in conformity with the

[[Page 100]]

license, the provisions of the Act, and the Commission's regulations.
    (iv) The applicant is technically and financially qualified to 
engage in the activities authorized; and
    (v) Issuance of the license will not be inimical to the common 
defense and security or to the health and safety of the public; and
    (vi) The findings required by subpart A of part 51 of this chapter 
have been made.
    (2) The Commission may also find, at the time it issues the combined 
license, that certain acceptance criteria in one or more of the 
inspections, tests, analyses, and acceptance criteria (ITAAC) in a 
referenced early site permit or standard design certification have been 
met. This finding will finally resolve that those acceptance criteria 
have been met, those acceptance criteria will be deemed to be excluded 
from the combined license, and findings under Sec. 52.103(g) with 
respect to those acceptance criteria are unnecessary.
    (b) The Commission shall identify within the combined license the 
inspections, tests, and analyses, including those applicable to 
emergency planning, that the licensee shall perform, and the acceptance 
criteria that, if met, are necessary and sufficient to provide 
reasonable assurance that the facility has been constructed and will be 
operated in conformity with the license, the provisions of the Act, and 
the Commission's rules and regulations.
    (c) A combined license shall contain the terms and conditions, 
including technical specifications, as the Commission deems necessary 
and appropriate.



Sec. 52.98  Finality of combined licenses; information requests.

    (a) After issuance of a combined license, the Commission may not 
modify, add, or delete any term or condition of the combined license, 
the design of the facility, the inspections, tests, analyses, and 
acceptance criteria contained in the license which are not derived from 
a referenced standard design certification or manufacturing license, 
except in accordance with the provisions of Sec. 52.103 or Sec. 50.109 
of this chapter, as applicable.
    (b) If the combined license does not reference a design 
certification or a reactor manufactured under a subpart F of this part 
manufacturing license, then a licensee may make changes in the facility 
as described in the final safety analysis report (as updated), make 
changes in the procedures as described in the final safety analysis 
report (as updated), and conduct tests or experiments not described in 
the final safety analysis report (as updated) under the applicable 
change processes in 10 CFR part 50 (e.g., Sec. Sec. 50.54, 50.59, or 
50.90 of this chapter).
    (c) If the combined license references a certified design, then--
    (1) Changes to or departures from information within the scope of 
the referenced design certification rule are subject to the applicable 
change processes in that rule; and
    (2) Changes that are not within the scope of the referenced design 
certification rule are subject to the applicable change processes in 10 
CFR part 50, unless they also involve changes to or noncompliance with 
information within the scope of the referenced design certification 
rule. In these cases, the applicable provisions of this section and the 
design certification rule apply.
    (d) If the combined license references a reactor manufactured under 
a subpart F of this part manufacturing license, then--
    (1) Changes to or departures from information within the scope of 
the manufactured reactor's design are subject to the change processes in 
Sec. 52.171; and
    (2) Changes that are not within the scope of the manufactured 
reactor's design are subject to the applicable change processes in 10 
CFR part 50.
    (e) The Commission may issue and make immediately effective any 
amendment to a combined license upon a determination by the Commission 
that the amendment involves no significant hazards consideration, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person. The amendment may be issued and made 
immediately effective in advance of the holding and completion of any 
required hearing. The amendment will be processed in accordance with the 
procedures specified in 10 CFR 50.91.

[[Page 101]]

    (f) Any modification to, addition to, or deletion from the terms and 
conditions of a combined license, including any modification to, 
addition to, or deletion from the inspections, tests, analyses, or 
related acceptance criteria contained in the license is a proposed 
amendment to the license. There must be an opportunity for a hearing on 
the amendment.
    (g) Except for information sought to verify licensee compliance with 
the current licensing basis for that facility, information requests to 
the holder of a combined license must be evaluated before issuance to 
ensure that the burden to be imposed on the licensee is justified in 
view of the potential safety significance of the issue to be addressed 
in the requested information. Each evaluation performed by the NRC staff 
must be in accordance with 10 CFR 50.54(f) and must be approved by the 
Executive Director for Operations or his or her designee before issuance 
of the request.



Sec. 52.99  Inspection during construction; ITAAC schedules and
notifications; NRC notices.

    (a) Licensee schedule for completing inspections, tests, or 
analyses. The licensee shall submit to the NRC, no later than 1 year 
after issuance of the combined license or at the start of construction 
as defined at 10 CFR 50.10(a), whichever is later, its schedule for 
completing the inspections, tests, or analyses in the ITAAC. The 
licensee shall submit updates to the ITAAC schedules every 6 months 
thereafter and, within 1 year of its scheduled date for initial loading 
of fuel, the licensee shall submit updates to the ITAAC schedule every 
30 days until the final notification is provided to the NRC under 
paragraph (c)(1) of this section.
    (b) Licensee and applicant conduct of activities subject to ITAAC. 
With respect to activities subject to an ITAAC, an applicant for a 
combined license may proceed at its own risk with design and procurement 
activities, and a licensee may proceed at its own risk with design, 
procurement, construction, and preoperational activities, even though 
the NRC may not have found that any one of the prescribed acceptance 
criteria are met.
    (c) Licensee notifications--(1) ITAAC closure notification. The 
licensee shall notify the NRC that prescribed inspections, tests, and 
analyses have been performed and that the prescribed acceptance criteria 
are met. The notification must contain sufficient information to 
demonstrate that the prescribed inspections, tests, and analyses have 
been performed and that the prescribed acceptance criteria are met.
    (2) ITAAC post-closure notifications. Following the licensee's ITAAC 
closure notifications under paragraph (c)(1) of this section until the 
Commission makes the finding under 10 CFR 52.103(g), the licensee shall 
notify the NRC, in a timely manner, of new information that materially 
alters the basis for determining that either inspections, tests, or 
analyses were performed as required, or that acceptance criteria are 
met. The notification must contain sufficient information to demonstrate 
that, notwithstanding the new information, the prescribed inspections, 
tests, or analyses have been performed as required, and the prescribed 
acceptance criteria are met.
    (3) Uncompleted ITAAC notification. If the licensee has not 
provided, by the date 225 days before the scheduled date for initial 
loading of fuel, the notification required by paragraph (c)(1) of this 
section for all ITAAC, then the licensee shall notify the NRC that the 
prescribed inspections, tests, or analyses for all uncompleted ITAAC 
will be performed and that the prescribed acceptance criteria will be 
met prior to operation. The notification must be provided no later than 
the date 225 days before the scheduled date for initial loading of fuel, 
and must provide sufficient information to demonstrate that the 
prescribed inspections, tests, or analyses will be performed and the 
prescribed acceptance criteria for the uncompleted ITAAC will be met, 
including, but not limited to, a description of the specific procedures 
and analytical methods to be used for performing the prescribed 
inspections, tests, and analyses and determining that the prescribed 
acceptance criteria are met.
    (4) All ITAAC complete notification. The licensee shall notify the 
NRC that all ITAAC are complete.

[[Page 102]]

    (d) Licensee determination of non-compliance with ITAAC. (1) In the 
event that an activity is subject to an ITAAC derived from a referenced 
standard design certification and the licensee has not demonstrated that 
the prescribed acceptance criteria are met, the licensee may take 
corrective actions to successfully complete that ITAAC or request an 
exemption from the standard design certification ITAAC, as applicable. A 
request for an exemption must also be accompanied by a request for a 
license amendment under 10 CFR 52.98(f).
    (2) In the event that an activity is subject to an ITAAC not derived 
from a referenced standard design certification and the licensee has not 
demonstrated that the prescribed acceptance criteria are met, the 
licensee may take corrective actions to successfully complete that ITAAC 
or request a license amendment under 10 CFR 52.98(f).
    (e) NRC inspection, publication of notices, and availability of 
licensee notifications. The NRC shall ensure that the prescribed 
inspections, tests, and analyses in the ITAAC are performed.
    (1) At appropriate intervals until the last date for submission of 
requests for hearing under 10 CFR 52.103(a), the NRC shall publish 
notices in the Federal Register of the NRC staff's determination of the 
successful completion of inspections, tests, and analyses.
    (2) The NRC shall make publicly available the licensee notifications 
under paragraph (c) of this section. The NRC shall, no later than the 
date of publication of the notice of intended operation required by 10 
CFR 52.103(a), make publicly available those licensee notifications 
under paragraph (c) of this section that have been submitted to the NRC 
at least seven (7) days before that notice.

[77 FR 51892, Aug. 28, 2012]



Sec. 52.103  Operation under a combined license.

    (a) The licensee shall notify the NRC of its scheduled date for 
initial loading of fuel no later than 270 days before the scheduled date 
and shall notify the NRC of updates to its schedule every 30 days 
thereafter. Not less than 180 days before the date scheduled for initial 
loading of fuel into a plant by a licensee that has been issued a 
combined license under this part, the Commission shall publish notice of 
intended operation in the Federal Register. The notice must provide that 
any person whose interest may be affected by operation of the plant may, 
within 60 days, request that the Commission hold a hearing on whether 
the facility as constructed complies, or on completion will comply, with 
the acceptance criteria in the combined license, except that a hearing 
shall not be granted for those ITAAC which the Commission found were met 
under Sec. 52.97(a)(2).
    (b) A request for hearing under paragraph (a) of this section must 
show, prima facie, that--
    (1) One or more of the acceptance criteria of the ITAAC in the 
combined license have not been, or will not be, met; and
    (2) The specific operational consequences of nonconformance that 
would be contrary to providing reasonable assurance of adequate 
protection of the public health and safety.
    (c) The Commission, acting as the presiding officer, shall determine 
whether to grant or deny the request for hearing in accordance with the 
applicable requirements of 10 CFR 2.309. If the Commission grants the 
request, the Commission, acting as the presiding officer, shall 
determine whether during a period of interim operation there will be 
reasonable assurance of adequate protection to the public health and 
safety. The Commission's determination must consider the petitioner's 
prima facie showing and any answers thereto. If the Commission 
determines there is such reasonable assurance, it shall allow operation 
during an interim period under the combined license.
    (d) The Commission, in its discretion, shall determine appropriate 
hearing procedures, whether informal or formal adjudicatory, for any 
hearing under paragraph (a) of this section, and shall state its reasons 
therefore.
    (e) The Commission shall, to the maximum possible extent, render a 
decision on issues raised by the hearing

[[Page 103]]

request within 180 days of the publication of the notice provided by 
paragraph (a) of this section or by the anticipated date for initial 
loading of fuel into the reactor, whichever is later.
    (f) A petition to modify the terms and conditions of the combined 
license will be processed as a request for action in accordance with 10 
CFR 2.206. The petitioner shall file the petition with the Secretary of 
the Commission. Before the licensed activity allegedly affected by the 
petition (fuel loading, low power testing, etc.) commences, the 
Commission shall determine whether any immediate action is required. If 
the petition is granted, then an appropriate order will be issued. Fuel 
loading and operation under the combined license will not be affected by 
the granting of the petition unless the order is made immediately 
effective.
    (g) The licensee shall not operate the facility until the Commission 
makes a finding that the acceptance criteria in the combined license are 
met, except for those acceptance criteria that the Commission found were 
met under Sec. 52.97(a)(2). If the combined license is for a modular 
design, each reactor module may require a separate finding as 
construction proceeds.
    (h) After the Commission has made the finding in paragraph (g) of 
this section, the ITAAC do not, by virtue of their inclusion in the 
combined license, constitute regulatory requirements either for 
licensees or for renewal of the license; except for the specific ITAAC 
for which the Commission has granted a hearing under paragraph (a) of 
this section, all ITAAC expire upon final Commission action in the 
proceeding. However, subsequent changes to the facility or procedures 
described in the final safety analysis report (as updated) must comply 
with the requirements in Sec. Sec. 52.98(e) or (f), as applicable.



Sec. 52.104  Duration of combined license.

    A combined license is issued for a specified period not to exceed 40 
years from the date on which the Commission makes a finding that 
acceptance criteria are met under Sec. 52.103(g) or allowing operation 
during an interim period under the combined license under Sec. 
52.103(c).



Sec. 52.105  Transfer of combined license.

    A combined license may be transferred in accordance with Sec. 50.80 
of this chapter.



Sec. 52.107  Application for renewal.

    The filing of an application for a renewed license must be in 
accordance with 10 CFR part 54.



Sec. 52.109  Continuation of combined license.

    Each combined license for a facility that has permanently ceased 
operations, continues in effect beyond the expiration date to authorize 
ownership and possession of the production or utilization facility, 
until the Commission notifies the licensee in writing that the license 
is terminated. During this period of continued effectiveness the 
licensee shall--
    (1) Take actions necessary to decommission and decontaminate the 
facility and continue to maintain the facility, including, where 
applicable, the storage, control and maintenance of the spent fuel, in a 
safe condition; and
    (2) Conduct activities in accordance with all other restrictions 
applicable to the facility in accordance with the NRC's regulations and 
the provisions of the combined license for the facility.



Sec. 52.110  Termination of license.

    (a)(1) When a licensee has determined to permanently cease 
operations the licensee shall, within 30 days, submit a written 
certification to the NRC, consistent with the requirements of Sec. 
52.3(b)(8);
    (2) Once fuel has been permanently removed from the reactor vessel, 
the licensee shall submit a written certification to the NRC that meets 
the requirements of Sec. 52.3(b)(9); and
    (3) For licensees whose licenses have been permanently modified to 
allow possession but not operation of the facility, before September 27, 
2007, the certification required in paragraph (a)(1) of this section 
shall be deemed to have been submitted.
    (b) Upon docketing of the certifications for permanent cessation of 
operations and permanent removal of fuel from the reactor vessel, or 
when a final legally effective order to permanently cease operations has 
come into effect,

[[Page 104]]

the 10 CFR part 52 license no longer authorizes operation of the reactor 
or emplacement or retention of fuel into the reactor vessel.
    (c) Decommissioning will be completed within 60 years of permanent 
cessation of operations. Completion of decommissioning beyond 60 years 
will be approved by the Commission only when necessary to protect public 
health and safety. Factors that will be considered by the Commission in 
evaluating an alternative that provides for completion of 
decommissioning beyond 60 years of permanent cessation of operations 
include unavailability of waste disposal capacity and other site-
specific factors affecting the licensee's capability to carry out 
decommissioning, including presence of other nuclear facilities at the 
site.
    (d)(1) Before or within 2 years following permanent cessation of 
operations, the licensee shall submit a post-shutdown decommissioning 
activities report (PSDAR) to the NRC, and a copy to the affected 
State(s). The report must include a description of the planned 
decommissioning activities along with a schedule for their 
accomplishment, an estimate of expected costs, and a discussion that 
provides the reasons for concluding that the environmental impacts 
associated with site-specific decommissioning activities will be bounded 
by appropriate previously issued environmental impact statements.
    (2) The NRC shall notice receipt of the PSDAR and make the PSDAR 
available for public comment. The NRC shall also schedule a public 
meeting in the vicinity of the licensee's facility upon receipt of the 
PSDAR. The NRC shall publish a document in the Federal Register and in a 
forum, such as local newspapers, that is readily accessible to 
individuals in the vicinity of the site, announcing the date, time and 
location of the meeting, along with a brief description of the purpose 
of the meeting.
    (e) Licensees shall not perform any major decommissioning 
activities, as defined in Sec. 50.2 of this chapter, until 90 days 
after the NRC has received the licensee's PSDAR submittal and until 
certifications of permanent cessation of operations and permanent 
removal of fuel from the reactor vessel, as required under Sec. 
52.110(a)(1), have been submitted.
    (f) Licensees shall not perform any decommissioning activities, as 
defined in Sec. 52.1, that--
    (1) Foreclose release of the site for possible unrestricted use;
    (2) Result in significant environmental impacts not previously 
reviewed; or
    (3) Result in there no longer being reasonable assurance that 
adequate funds will be available for decommissioning.
    (g) In taking actions permitted under Sec. 50.59 of this chapter 
following submittal of the PSDAR, the licensee shall notify the NRC in 
writing and send a copy to the affected State(s), before performing any 
decommissioning activity inconsistent with, or making any significant 
schedule change from, those actions and schedules described in the 
PSDAR, including changes that significantly increase the decommissioning 
cost.
    (h)(1) Decommissioning trust funds may be used by licensees if--
    (i) The withdrawals are for expenses for legitimate decommissioning 
activities consistent with the definition of decommissioning in Sec. 
52.1;
    (ii) The expenditure would not reduce the value of the 
decommissioning trust below an amount necessary to place and maintain 
the reactor in a safe storage condition if unforeseen conditions or 
expenses arise and;
    (iii) The withdrawals would not inhibit the ability of the licensee 
to complete funding of any shortfalls in the decommissioning trust 
needed to ensure the availability of funds to ultimately release the 
site and terminate the license.
    (2) Initially, 3 percent of the generic amount specified in Sec. 
50.75 of this chapter may be used for decommissioning planning. For 
licensees that have submitted the certifications required under Sec. 
52.110(a) and commencing 90 days after the NRC has received the PSDAR, 
an additional 20 percent may be used. A site-specific decommissioning 
cost estimate must be submitted to the NRC before the licensee may use 
any funding in excess of these amounts.

[[Page 105]]

    (3) Within 2 years following permanent cessation of operations, if 
not already submitted, the licensee shall submit a site-specific 
decommissioning cost estimate.
    (4) For decommissioning activities that delay completion of 
decommissioning by including a period of storage or surveillance, the 
licensee shall provide a means of adjusting cost estimates and 
associated funding levels over the storage or surveillance period.
    (i) All power reactor licensees must submit an application for 
termination of license. The application for termination of license must 
be accompanied or preceded by a license termination plan to be submitted 
for NRC approval.
    (1) The license termination plan must be a supplement to the FSAR or 
equivalent and must be submitted at least 2 years before termination of 
the license date.
    (2) The license termination plan must include--
    (i) A site characterization;
    (ii) Identification of remaining dismantlement activities;
    (iii) Plans for site remediation;
    (iv) Detailed plans for the final radiation survey;
    (v) A description of the end use of the site, if restricted;
    (vi) An updated site-specific estimate of remaining decommissioning 
costs;
    (vii) A supplement to the environmental report, under Sec. 51.53 of 
this chapter, describing any new information or significant 
environmental change associated with the licensee's proposed termination 
activities; and
    (viii) Identification of parts, if any, of the facility or site that 
were released for use before approval of the license termination plan.
    (3) The NRC shall notice receipt of the license termination plan and 
make the license termination plan available for public comment. The NRC 
shall also schedule a public meeting in the vicinity of the licensee's 
facility upon receipt of the license termination plan. The NRC shall 
publish a document in the Federal Register and in a forum, such as local 
newspapers, which is readily accessible to individuals in the vicinity 
of the site, announcing the date, time and location of the meeting, 
along with a brief description of the purpose of the meeting.
    (j) If the license termination plan demonstrates that the remainder 
of decommissioning activities will be performed in accordance with the 
regulations in this chapter, will not be inimical to the common defense 
and security or to the health and safety of the public, and will not 
have a significant effect on the quality of the environment and after 
notice to interested persons, the Commission shall approve the plan, by 
license amendment, subject to terms and conditions as it deems 
appropriate and necessary and authorize implementation of the license 
termination plan.
    (k) The Commission shall terminate the license if it determines 
that--
    (1) The remaining dismantlement has been performed in accordance 
with the approved license termination plan; and
    (2) The final radiation survey and associated documentation, 
including an assessment of dose contributions associated with parts 
released for use before approval of the license termination plan, 
demonstrate that the facility and site have met the criteria for 
decommissioning in subpart E to 10 CFR part 20.
    (l) For a facility that has permanently ceased operation before the 
expiration of its license, the collection period for any shortfall of 
funds will be determined, upon application by the licensee, on a case-
by-case basis taking into account the specific financial situation of 
each licensee.

Subpart D [Reserved]



                   Subpart E_Standard Design Approvals



Sec. 52.131  Scope of subpart.

    This subpart sets out procedures for the filing, NRC staff review, 
and referral to the Advisory Committee on Reactor Safeguards of standard 
designs for a nuclear power reactor of the type described in Sec. 50.22 
of this chapter or major portions thereof.

[[Page 106]]



Sec. 52.133  Relationship to other subparts.

    (a) This subpart applies to a person that requests a standard design 
approval from the NRC staff separately from an application for a 
construction permit filed under 10 CFR part 50 or a combined license 
filed under subpart C of this part. An applicant for a construction 
permit or combined license may reference a standard design approval.
    (b) Subpart B of this part governs the certification by rulemaking 
of the design of a nuclear power plant. Subpart B may be used 
independently of the provisions in this subpart.
    (c) Subpart F of this part governs the issuance of licenses to 
manufacture nuclear power reactors to be installed and operated at sites 
not identified in the manufacturing license application. Subpart F of 
this part may be used independently of the provisions in this subpart.



Sec. 52.135  Filing of applications.

    (a) Any person may submit a proposed standard design for a nuclear 
power reactor of the type described in 10 CFR 50.22 to the NRC staff for 
its review. The submittal may consist of either the final design for the 
entire facility or the final design of major portions thereof.
    (b) The submittal for review of the proposed standard design must be 
made in the same manner and in the same number of copies as provided in 
10 CFR 50.30 and 52.3 for license applications.
    (c) The fees associated with the filing and review of the 
application are set forth in 10 CFR part 170.



Sec. 52.136  Contents of applications; general information.

    The application must contain all of the information required by 10 
CFR 50.33(a) through (d) and (j).



Sec. 52.137  Contents of applications; technical information.

    If the applicant seeks review of a major portion of a standard 
design, the application need only contain the information required by 
this section to the extent the requirements are applicable to the major 
portion of the standard design for which NRC staff approval is sought.
    (a) The application must contain a final safety analysis report that 
describes the facility, presents the design bases and the limits on its 
operation, and presents a safety analysis of the structures, systems, 
and components and of the facility, or major portion thereof, and must 
include the following information:
    (1) The site parameters postulated for the design, and an analysis 
and evaluation of the design in terms of those site parameters;
    (2) A description and analysis of the SSCs of the facility, with 
emphasis upon performance requirements, the bases, with technical 
justification, upon which the requirements have been established, and 
the evaluations required to show that safety functions will be 
accomplished. It is expected that the standard plant will reflect 
through its design, construction, and operation an extremely low 
probability for accidents that could result in the release of 
significant quantities of radioactive fission products. The description 
shall be sufficient to permit understanding of the system designs and 
their relationship to the safety evaluations. Items such as the reactor 
core, reactor coolant system, instrumentation and control systems, 
electrical systems, containment system, other engineered safety 
features, auxiliary and emergency systems, power conversion systems, 
radioactive waste handling systems, and fuel handling systems shall be 
discussed insofar as they are pertinent. The following power reactor 
design characteristics will be taken into consideration by the 
Commission:
    (i) Intended use of the reactor including the proposed maximum power 
level and the nature and inventory of contained radioactive materials;
    (ii) The extent to which generally accepted engineering standards 
are applied to the design of the reactor;
    (iii) The extent to which the reactor incorporates unique, unusual 
or enhanced safety features having a significant bearing on the 
probability or consequences of accidental release of radioactive 
materials; and

[[Page 107]]

    (iv) The safety features that are to be engineered into the facility 
and those barriers that must be breached as a result of an accident 
before a release of radioactive material to the environment can occur. 
Special attention must be directed to plant design features intended to 
mitigate the radiological consequences of accidents. In performing this 
assessment, an applicant shall assume a fission product release \9\ from 
the core into the containment assuming that the facility is operated at 
the ultimate power level contemplated. The applicant shall perform an 
evaluation and analysis of the postulated fission product release, using 
the expected demonstrable containment leak rate and any fission product 
cleanup systems intended to mitigate the consequences of the accidents, 
together with applicable postulated site parameters, including site 
meteorology, to evaluate the offsite radiological consequences. The 
evaluation must determine that:
---------------------------------------------------------------------------

    \9\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. These accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (A) An individual located at any point on the boundary of the 
exclusion area for any 2-hour period following the onset of the 
postulated fission product release, would not receive a radiation dose 
in excess of 25 rem \10\ total effective dose equivalent (TEDE); and
---------------------------------------------------------------------------

    \10\ A whole body dose of 25 rem has been stated to correspond 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations at the time 
could be disregarded in the determination of their radiation exposure 
status (see NBS Handbook 69 dated June 5, 1959). However, its use is not 
intended to imply that this number constitutes an acceptable limit for 
an emergency dose to the public under accident conditions. Rather, this 
dose value has been set forth in this section as a reference value, 
which can be used in the evaluation of plant design features with 
respect to postulated reactor accidents, to assure that these designs 
provide assurance of low risk of public exposure to radiation, in the 
event of an accident.
---------------------------------------------------------------------------

    (B) An individual located at any point on the outer boundary of the 
low population zone, who is exposed to the radioactive cloud resulting 
from the postulated fission product release (during the entire period of 
its passage) would not receive a radiation dose in excess of 25 rem 
TEDE;
    (3) The design of the facility including:
    (i) The principal design criteria for the facility. Appendix A to 10 
CFR part 50, general design criteria (GDC), establishes minimum 
requirements for the principal design criteria for water-cooled nuclear 
power plants similar in design and location to plants for which 
construction permits have previously been issued by the Commission and 
provides guidance to applicants in establishing principal design 
criteria for other types of nuclear power units;
    (ii) The design bases and the relation of the design bases to the 
principal design criteria; and
    (iii) Information relative to materials of construction, general 
arrangement, and approximate dimensions, sufficient to provide 
reasonable assurance that the design will conform to the design bases 
with adequate margin for safety;
    (4) An analysis and evaluation of the design and performance of SSC 
with the objective of assessing the risk to public health and safety 
resulting from operation of the facility and including determination of 
the margins of safety during normal operations and transient conditions 
anticipated during the life of the facility, and the adequacy of SSCs 
provided for the prevention of accidents and the mitigation of the 
consequences of accidents. Analysis and evaluation of ECCS cooling 
performance and the need for high-point vents following postulated loss-
of-coolant accidents shall be performed in accordance with the 
requirements of 10 CFR 50.46 and 50.46a;
    (5) The kinds and quantities of radioactive materials expected to be 
produced in the operation and the means for controlling and limiting 
radioactive effluents and radiation exposures within the limits set 
forth in part 20 of this chapter;
    (6) The information required by Sec. 20.1406 of this chapter;

[[Page 108]]

    (7) The technical qualifications of the applicant to engage in the 
proposed activities in accordance with the regulations in this chapter;
    (8) The information necessary to demonstrate compliance with any 
technically relevant portions of the Three Mile Island requirements set 
forth in 10 CFR 50.34(f), except paragraphs (f)(1)(xii), (f)(2)(ix), and 
(f)(3)(v) of 10 CFR 50.34(f);
    (9) For applications for light-water-cooled nuclear power plants, an 
evaluation of the standard plant design against the Standard Review Plan 
(SRP) revision in effect 6 months before the docket date of the 
application. The evaluation required by this section shall include an 
identification and description of all differences in design features, 
analytical techniques, and procedural measures proposed for the design 
and those corresponding features, techniques, and measures given in the 
SRP acceptance criteria. Where a difference exists, the evaluation shall 
discuss how the proposed alternative provides an acceptable method of 
complying with the Commission's regulations, or portions thereof, that 
underlie the corresponding SRP acceptance criteria. The SRP is not a 
substitute for the regulations, and compliance is not a requirement;
    (10) The information with respect to the design of equipment to 
maintain control over radioactive materials in gaseous and liquid 
effluents produced during normal reactor operations described in 10 CFR 
50.34a(e);
    (11) The information pertaining to design features that affect plans 
for coping with emergencies in the operation of the reactor facility or 
a major portion thereof;
    (12) An analysis and description of the equipment and systems for 
combustible gas control as required by Sec. 50.44 of this chapter;
    (13) The list of electric equipment important to safety that is 
required by 10 CFR 50.49(d);
    (14) A description of protection provided against pressurized 
thermal shock events, including projected values of the reference 
temperature for reactor vessel beltline materials as defined in 10 CFR 
50.60 and 50.61;
    (15) Information demonstrating how the applicant will comply with 
requirements for reduction of risk from anticipated transients without 
scram (ATWS) events in Sec. 50.62;
    (16) The coping analysis, and any design features necessary to 
address station blackout, as described in Sec. 50.63 of this chapter;
    (17) Information demonstrating how the applicant will comply with 
requirements for criticality accidents in Sec. 50.68(b)(2)-(b)(4);
    (18) A description and analysis of the fire protection design 
features for the standard plant necessary to comply with part 50, 
appendix A, GDC 3, and Sec. 50.48 of this chapter;
    (19) A description of the quality assurance program applied to the 
design of the SSCs of the facility. Appendix B to 10 CFR part 50, 
``Quality Assurance Criteria for Nuclear Power Plants and Fuel 
Reprocessing Plants,'' sets forth the requirements for quality assurance 
programs for nuclear power plants. The description of the quality 
assurance program for a nuclear power plant shall include a discussion 
of how the applicable requirements of appendix B to 10 CFR part 50 were 
satisfied;
    (20) The information necessary to demonstrate that the standard 
plant complies with the earthquake engineering criteria in 10 CFR part 
50, appendix S;
    (21) Proposed technical resolutions of those Unresolved Safety 
Issues and medium- and high-priority generic safety issues which are 
identified in the version of NUREG-0933 current on the date up to 6 
months before the docket date of the application and which are 
technically relevant to the design;
    (22) The information necessary to demonstrate how operating 
experience insights have been incorporated into the plant design;
    (23) For light-water reactor designs, a description and analysis of 
design features for the prevention and mitigation of severe accidents, 
e.g., challenges to containment integrity caused by core-concrete 
interaction, steam explosion, high-pressure core melt ejection, hydrogen 
combustion, and containment bypass;

[[Page 109]]

    (24) A description, analysis, and evaluation of the interfaces 
between the standard design and the balance of the nuclear power plant; 
and
    (25) A description of the design-specific probabilistic risk 
assessment and its results.
    (26) For applications for standard design approvals which are 
subject to 10 CFR 50.150(a), the information required by 10 CFR 
50.150(b).
    (b) An application for approval of a standard design, which differs 
significantly from the light-water reactor designs of plants that have 
been licensed and in commercial operation before April 18, 1989, or uses 
simplified, inherent, passive, or other innovative means to accomplish 
its safety functions, must meet the requirements of 10 CFR 50.43(e).

[72 FR 49517, Aug. 28, 2007, as amended at 74 FR 28147, June 12, 2009]



Sec. 52.139  Standards for review of applications.

    Applications filed under this subpart will be reviewed for 
compliance with the standards set out in 10 CFR parts 20, 50 and its 
appendices, and 10 CFR parts 73 and 100.



Sec. 52.141  Referral to the Advisory Committee on Reactor Safeguards
(ACRS).

    The Commission shall refer a copy of the application to the ACRS. 
The ACRS shall report on those portions of the application which concern 
safety.



Sec. 52.143  Staff approval of design.

    Upon completion of its review of a submittal under this subpart and 
receipt of a report by the Advisory Committee on Reactor Safeguards 
under Sec. 52.141 of this subpart, the NRC staff shall publish a 
determination in the Federal Register as to whether or not the design is 
acceptable, subject to appropriate terms and conditions, and make an 
analysis of the design in the form of a report available at the NRC Web 
site, http://www.nrc.gov.



Sec. 52.145  Finality of standard design approvals; information 
requests.

    (a) An approved design must be used by and relied upon by the NRC 
staff and the ACRS in their review of any individual facility license 
application that incorporates by reference a standard design approved in 
accordance with this paragraph unless there exists significant new 
information that substantially affects the earlier determination or 
other good cause.
    (b) The determination and report by the NRC staff do not constitute 
a commitment to issue a permit or license, or in any way affect the 
authority of the Commission, Atomic Safety and Licensing Board Panel, or 
presiding officers in any proceeding under part 2 of this chapter.
    (c) Except for information requests seeking to verify compliance 
with the current licensing basis of the standard design approval, 
information requests to the holder of a standard design approval must be 
evaluated before issuance to ensure that the burden to be imposed on 
respondents is justified in view of the potential safety significance of 
the issue to be addressed in the requested information. Each evaluation 
performed by the NRC staff must be in accordance with 10 CFR 50.54(f) 
and must be approved by the Executive Director for Operations or his or 
her designee before issuance of the request.



Sec. 52.147  Duration of design approval.

    A standard design approval issued under this subpart is valid for 15 
years from the date of issuance and may not be renewed. A design 
approval continues to be valid beyond the date of expiration in any 
proceeding on an application for a construction permit or an operating 
license under part 50 or a combined license or manufacturing license 
under part 52 that references the final design approval and is docketed 
before the date of expiration of the design approval.



                    Subpart F_Manufacturing Licenses



Sec. 52.151  Scope of subpart.

    This subpart sets out the requirements and procedures applicable to 
Commission issuance of a license authorizing manufacture of nuclear 
power reactors to be installed at sites not identified in the 
manufacturing license application.

[[Page 110]]



Sec. 52.153  Relationship to other subparts.

    (a) A nuclear power reactor manufactured under a manufacturing 
license issued under this subpart may only be transported to and 
installed at a site for which either a construction permit under part 50 
of this chapter or a combined license under subpart C of this part has 
been issued.
    (b) Subpart B of this part governs the certification by rulemaking 
of the design of standard nuclear power facilities. Subpart E of this 
part governs the NRC staff review and approval of standard designs for a 
nuclear power facility. A manufacturing license applicant may reference 
a standard design certification or a standard design approval in its 
application. These subparts may also be used independently of the 
provisions in this subpart.



Sec. 52.155  Filing of applications.

    (a) Any person, except one excluded by 10 CFR 50.38, may file an 
application for a manufacturing license under this subpart with the 
Director of New Reactors or the Director of Nuclear Reactor Regulation, 
as appropriate.
    (b) The application must comply with the applicable filing 
requirements of Sec. Sec. 52.3 and 50.30 of this chapter.
    (c) The fees associated with the filing and review of the 
application are set forth in 10 CFR part 170.



Sec. 52.156  Contents of applications; general information.

    The application must contain all of the information required by 10 
CFR 50.33(a) through (d), and (j).



Sec. 52.157  Contents of applications; technical information in final
safety analysis report.

    The application must contain a final safety analysis report 
containing the information set forth below, with a level of design 
information sufficient to enable the Commission to judge the applicant's 
proposed means of assuring that the manufacturing conforms to the design 
and to reach a final conclusion on all safety questions associated with 
the design, permit the preparation of construction and installation 
specifications by an applicant who seeks to use the manufactured 
reactor, and permit the preparation of acceptance and inspection 
requirements by the NRC:
    (a) The principal design criteria for the reactor to be 
manufactured. Appendix A of 10 CFR part 50, ``General Design Criteria 
for Nuclear Power Plants,'' establishes minimum requirements for the 
principal design criteria for water-cooled nuclear power plants similar 
in design and location to plants for which construction permits have 
previously been issued by the Commission and provides guidance to 
applicants in establishing principal design criteria for other types of 
nuclear power units;
    (b) The design bases and the relation of the design bases to the 
principal design criteria;
    (c) A description and analysis of the structures, systems, and 
components of the reactor to be manufactured, with emphasis upon the 
materials of manufacture, performance requirements, the bases, with 
technical justification therefor, upon which the performance 
requirements have been established, and the evaluations required to show 
that safety functions will be accomplished. The description shall be 
sufficient to permit understanding of the system designs and their 
relationship to safety evaluations. Items such as the reactor core, 
reactor coolant system, instrumentation and control systems, electrical 
systems, containment system, other engineered safety features, auxiliary 
and emergency systems, power conversion systems, radioactive waste 
handling systems, and fuel handling systems shall be discussed insofar 
as they are pertinent. The following power reactor design 
characteristics will be taken into consideration by the Commission:
    (1) Intended use of the manufactured reactor including the proposed 
maximum power level and the nature and inventory of contained 
radioactive materials;
    (2) The extent to which generally accepted engineering standards are 
applied to the design of the reactor; and
    (3) The extent to which the reactor incorporates unique, unusual or 
enhanced safety features having a significant bearing on the probability 
or consequences of accidental release of radioactive materials;

[[Page 111]]

    (d) The safety features that are engineered into the reactor and 
those barriers that must be breached as a result of an accident before a 
release of radioactive material to the environment can occur. Special 
attention must be directed to reactor design features intended to 
mitigate the radiological consequences of accidents. In performing this 
assessment, an applicant shall assume a fission product release \11\ 
from the core into the containment assuming that the facility is 
operated at the ultimate power level contemplated. The applicant shall 
perform an evaluation and analysis of the postulated fission product 
release, using the expected demonstrable containment leak rate and any 
fission product cleanup systems intended to mitigate the consequences of 
the accidents, together with applicable postulated site parameters, 
including site meteorology, to evaluate the offsite radiological 
consequences. The evaluation must determine that:
---------------------------------------------------------------------------

    \11\ The fission product release assumed for this evaluation should 
be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events. These accidents have generally been assumed to result in 
substantial meltdown of the core with subsequent release into the 
containment of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (1) An individual located at any point on the boundary of the 
exclusion area for any 2 hour period following the onset of the 
postulated fission product release, would not receive a radiation dose 
in excess of 25 rem \12\ total effective dose equivalent (TEDE);
---------------------------------------------------------------------------

    \12\ A whole body dose of 25 rem has been stated to correspond 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations at the time 
could be disregarded in the determination of their radiation exposure 
status (see NBS Handbook 69 dated June 5, 1959). However, its use is not 
intended to imply that this number constitutes an acceptable limit for 
an emergency dose to the public under accident conditions. Rather, this 
dose value has been set forth in this section as a reference value, 
which can be used in the evaluation of plant design features with 
respect to postulated reactor accidents, to assure that these designs 
provide assurance of low risk of public exposure to radiation, in the 
event of an accident.
---------------------------------------------------------------------------

    (2) An individual located at any point on the outer boundary of the 
low population zone, who is exposed to the radioactive cloud resulting 
from the postulated fission product release (during the entire period of 
its passage) would not receive a radiation dose in excess of 25 rem 
TEDE; and
    (e) The kinds and quantities of radioactive materials expected to be 
produced in the operation and the means for controlling and limiting 
radioactive effluents and radiation exposures within the limits set 
forth in part 20 of this chapter.
    (f) Information necessary to establish that the design of the 
reactor to be manufactured complies with the technical requirements in 
10 CFR Chapter I, including:
    (1) An analysis and evaluation of the design and performance of 
structures, systems, and components with the objective of assessing the 
risk to public health and safety resulting from operation of the 
facility and including determination of the margins of safety during 
normal operations and transient conditions anticipated during the life 
of the facility, and the adequacy of structures, systems, and components 
provided for the prevention of accidents and the mitigation of the 
consequences of accidents. Analysis and evaluation of ECCS cooling 
performance and the need for high-point vents following postulated loss-
of-coolant accidents shall be performed in accordance with the 
requirements of Sec. Sec. 50.46 and 50.46a of this chapter;
    (2) A description and analysis of the fire protection design 
features for the reactor necessary to comply with 10 CFR part 50, 
appendix A, GDC 3 and Sec. 50.48 of this chapter;
    (3) A description of protection provided against pressurized thermal 
shock events, including projected values of the reference temperature 
for reactor vessel beltline materials as defined in Sec. Sec. 50.60 and 
50.61 of this chapter;
    (4) An analysis and description of the equipment and systems for 
combustible gas control as required by Sec. 50.44 of this chapter;

[[Page 112]]

    (5) The coping analysis, and any design features necessary to 
address station blackout, as described in Sec. 50.63 of this chapter;
    (6) The list of electric equipment important to safety that is 
required by 10 CFR 50.49(d);
    (7) Information demonstrating how the applicant will comply with 
requirements for reduction of risk from anticipated transients without 
scram (ATWS) events in Sec. 50.62;
    (8) Information demonstrating how the applicant will comply with 
requirements for criticality accidents in Sec. 50.68(b)(2)-(b)(4);
    (9) The information required by Sec. 20.1406 of this chapter;
    (10) [Reserved]
    (11) The information with respect to the design of equipment to 
maintain control over radioactive materials in gaseous and liquid 
effluents produced during normal reactor operations, as described in 
Sec. 50.34a(e) of this chapter;
    (12) The information necessary to demonstrate compliance with any 
technically relevant portions of the Three Mile Island requirements set 
forth in Sec. 50.34(f) of this chapter, except paragraphs (f)(1)(xii), 
(f)(2)(ix), and (f)(3)(v);
    (13) If the applicant seeks to use risk-informed treatment of SSCs 
in accordance with Sec. 50.69 of this chapter, the information required 
by Sec. 50.69(b)(2) of this chapter;
    (14) The information necessary to demonstrate that the manufactured 
reactor complies with the earthquake engineering criteria in appendix S 
to 10 CFR part 50;
    (15) Information sufficient to demonstrate compliance with the 
applicable requirements regarding testing, analysis, and prototypes as 
set forth in Sec. 50.43(e) of this chapter;
    (16) The technical qualifications of the applicant to engage in the 
proposed activities in accordance with the regulations in this chapter;
    (17) A description of the quality assurance program applied to the 
design, and to be applied to the manufacture of, the structures, 
systems, and components of the reactor. Appendix B to 10 CFR part 50, 
``Quality Assurance Criteria for Nuclear Power Plants and Fuel 
Reprocessing Plants,'' sets forth the requirements for quality assurance 
programs for nuclear power plants. The description of the quality 
assurance program must include a discussion of how the applicable 
requirements of appendix B to 10 CFR part 50 have been and will be 
satisfied; and
    (18) Proposed technical specifications applicable to the reactor 
being manufactured, prepared in accordance with the requirements of 
Sec. Sec. 50.36 and 50.36a of this chapter;
    (19) The site parameters postulated for the design, and an analysis 
and evaluation of the reactor design in terms of those site parameters;
    (20) The interface requirements between the manufactured reactor and 
the remaining portions of the nuclear power plant. These requirements 
must be sufficiently detailed to allow for completion of the final 
safety analysis;
    (21) Justification that compliance with the interface requirements 
of paragraph (f)(20) of this section is verifiable through inspections, 
testing, or analysis. The method to be used for verification of 
interface requirements must be included as part of the proposed ITAAC 
required by Sec. 52.158(a);
    (22) A representative conceptual design for a nuclear power facility 
using the manufactured reactor, to aid the NRC in its review of the 
final safety analysis required by this section and to permit assessment 
of the adequacy of the interface requirements in paragraph (f)(20) of 
this section;
    (23) For light-water reactor designs, a description and analysis of 
design features for the prevention and mitigation of severe accidents, 
e.g., challenges to containment integrity caused by core-concrete 
interaction, steam explosion, high-pressure core melt ejection, hydrogen 
combustion, and containment bypass;
    (24) [Reserved]
    (25) If the reactor is to be used in modular plant design, a 
description of the possible operating configurations of the reactor 
modules with common systems, interface requirements, and system 
interactions. The final safety analysis must also account for 
differences among the configurations, including any restrictions that 
will be necessary during the construction and startup of a given module 
to ensure the

[[Page 113]]

safe operation of any module already operating;
    (26) A description of the management plan for design and 
manufacturing activities, including:
    (i) The organizational and management structure singularly 
responsible for direction of design and manufacture of the reactor;
    (ii) Technical resources directed by the applicant, and the 
qualifications requirements;
    (iii) Details of the interaction of design and manufacture within 
the applicant's organization and the manner by which the applicant will 
ensure close integration of the architect engineer and the nuclear steam 
supply vendor, as applicable;
    (iv) Proposed procedures governing the preparation of the 
manufactured reactor for shipping to the site where it is to be 
operated, the conduct of shipping, and verifying the condition of the 
manufactured reactor upon receipt at the site; and
    (v) The degree of top level management oversight and technical 
control to be exercised by the applicant during design and manufacture, 
including the preparation and implementation of procedures necessary to 
guide the effort;
    (27) Necessary parameters to be used in developing plans for 
preoperational testing and initial operation;
    (28) Proposed technical resolutions of those Unresolved Safety 
Issues and medium- and high-priority generic safety issues which are 
identified in the version of NUREG-0933 current on the date up to 6 
months before the docket date of the application and which are 
technically relevant to the design;
    (29) The information necessary to demonstrate how operating 
experience insights have been incorporated into the manufactured reactor 
design;
    (30) For applications for light-water-cooled nuclear power plants, 
an evaluation of the design to be manufactured against the Standard 
Review Plan (SRP) revision in effect 6 months before the docket date of 
the application. The evaluation required by this section shall include 
an identification and description of all differences in design features, 
analytical techniques, and procedural measures proposed for the design 
and those corresponding features, techniques, and measures given in the 
SRP acceptance criteria. Where a difference exists, the evaluation shall 
discuss how the proposed alternative provides an acceptable method of 
complying with the Commission's regulations, or portions thereof, that 
underlie the corresponding SRP acceptance criteria. The SRP is not a 
substitute for the regulations, and compliance is not a requirement; and
    (31) A description of the design-specific probabilistic risk 
assessment and its results.
    (32) For applications for manufacturing licenses which are subject 
to 10 CFR 50.150(a), the information required by 10 CFR 50.150(b).

[72 FR 49517, Aug. 28, 2007, as amended at 74 FR 28147, June 12, 2009]



Sec. 52.158  Contents of application; additional technical information.

    The application must contain:
    (a)(1) Inspections, tests, analyses, and acceptance criteria 
(ITAAC). The proposed inspections, tests, and analyses that the licensee 
who will be operating the reactor shall perform, and the acceptance 
criteria that are necessary and sufficient to provide reasonable 
assurance that, if the inspections, tests, and analyses are performed 
and the acceptance criteria met:
    (i) The reactor has been manufactured in conformity with the 
manufacturing license; the provisions of the Act, and the Commission's 
rules and regulations; and
    (ii) The manufactured reactor will be operated in conformity with 
the approved design and any license authorizing operation of the 
manufactured reactor.
    (2) If the application references a standard design certification, 
the ITAAC contained in the certified design must apply to those portions 
of the facility design which are covered by the design certification.
    (3) If the application references a standard design certification, 
the application may include a notification that a required inspection, 
test, or analysis in the design certification ITAAC has been 
successfully completed and that the corresponding acceptance

[[Page 114]]

criterion has been met. The Federal Register notification required by 
Sec. 52.163 must indicate that the application includes this 
notification.
    (b)(1) An environmental report as required by 10 CFR 51.54.
    (2) If the manufacturing license application references a standard 
design certification, the environmental report need not contain a 
discussion of severe accident mitigation design alternatives for the 
reactor.



Sec. 52.159  Standards for review of application.

    Applications filed under this subpart will be reviewed according to 
the applicable standards set out in 10 CFR parts 20, 50 and its 
appendices, 51, 73, and 100 and its appendices.



Sec. 52.161  [Reserved]



Sec. 52.163  Administrative review of applications; hearings.

    A proceeding on a manufacturing license is subject to all applicable 
procedural requirements contained in 10 CFR part 2, including the 
requirements for docketing in Sec. 2.101(a)(1) through (4) of this 
chapter, and the requirements for issuance of a notice of proposed 
action in Sec. 2.105 of this chapter, provided, however, that the 
designated sections may not be construed to require that the 
environmental report or draft or final environmental impact statement 
include an assessment of the benefits of constructing and/or operating 
the manufactured reactor or an evaluation of alternative energy sources. 
All hearings on manufacturing licenses are governed by the hearing 
procedures contained in 10 CFR part 2, subparts C, E, G, L, and N.

[72 FR 49517, Aug. 28, 2007, as amended at 78 FR 34249, June 7, 2013]



Sec. 52.165  Referral to the Advisory Committee on Reactor Safeguards
(ACRS).

    The Commission shall refer a copy of the application to the ACRS. 
The ACRS shall report on those portions of the application which concern 
safety.



Sec. 52.167  Issuance of manufacturing license.

    (a) After completing any hearing under Sec. 52.163, and receiving 
the report submitted by the ACRS, the Commission may issue a 
manufacturing license if the Commission finds that:
    (1) Applicable standards and requirements of the Act and the 
Commission's regulations have been met;
    (2) There is reasonable assurance that the reactor(s) will be 
manufactured, and can be transported, incorporated into a nuclear power 
plant, and operated in conformity with the manufacturing license, the 
provision of the Act, and the Commission's regulations;
    (3) The proposed reactor(s) can be incorporated into a nuclear power 
plant and operated at sites having characteristics that fall within the 
site parameters postulated for the design of the manufactured reactor(s) 
without undue risk to the health and safety of the public;
    (4) The applicant is technically qualified to design and manufacture 
the proposed nuclear power reactor(s);
    (5) The proposed inspections, tests, analyses and acceptance 
criteria are necessary and sufficient, within the scope of the 
manufacturing license, to provide reasonable assurance that the 
manufactured reactor has been manufactured and will be operated in 
conformity with the license, the provisions of the Act, and the 
Commission's regulations;
    (6) The issuance of a license to the applicant will not be inimical 
to the common defense and security or to the health and safety of the 
public; and
    (7) The findings required by subpart A of part 51 of this chapter 
have been made.
    (b) Each manufacturing license issued under this subpart shall 
specify:
    (1) Terms and conditions as the Commission deems necessary and 
appropriate;
    (2) Technical specifications for operation of the manufactured 
reactor, as the Commission deems necessary and appropriate;
    (3) Site parameters and design characteristics for the manufactured 
reactor; and
    (4) The interface requirements to be met by the site-specific 
elements of the

[[Page 115]]

facility, such as the service water intake structure and the ultimate 
heat sink, not within the scope of the manufactured reactor.
    (c)(1) A holder of a manufacturing license may not transport or 
allow to be removed from the place of manufacture the manufactured 
reactor except to the site of a licensee with either a construction 
permit under part 50 of this chapter or a combined license under subpart 
C of this part. The construction permit or combined license must 
authorize the construction of a nuclear power facility using the 
manufactured reactor(s).
    (2) A holder of a manufacturing license shall include, in any 
contract governing the transport of a manufactured reactor from the 
place of manufacture to any other location, a provision requiring that 
the person or entity transporting the manufactured reactor to comply 
with all NRC-approved shipping requirements in the manufacturing 
license.



Sec. 52.169  [Reserved]



Sec. 52.171  Finality of manufacturing licenses; information requests.

    (a)(1) Notwithstanding any provision in 10 CFR 50.109, during the 
term of a manufacturing license the Commission may not modify, rescind, 
or impose new requirements on the design of the nuclear power reactor 
being manufactured, or the requirements for the manufacture of the 
nuclear power reactor, unless the Commission determines that a 
modification is necessary to bring the design of the reactor or its 
manufacture into compliance with the Commission's requirements 
applicable and in effect at the time the manufacturing license was 
issued, or to provide reasonable assurance of adequate protection to 
public health and safety or common defense and security.
    (2) Any modification to the design of a manufactured nuclear power 
reactor which is imposed by the Commission under paragraph (a)(1) of 
this section will be applied to all reactors manufactured under the 
license, including those that have already been transported and sited, 
except those reactors to which the modification has been rendered 
technically irrelevant by action taken under paragraph (b) of this 
section.
    (3) In making the findings required for issuance of a construction 
permit, operating license, combined license, in any hearing under Sec. 
52.103, or in any enforcement hearing other than one initiated by the 
Commission under paragraph (a)(1) of this section, for which a nuclear 
power reactor manufactured under this subpart is referenced or used, the 
Commission shall treat as resolved those matters resolved in the 
proceeding on the application for issuance or renewal of the 
manufacturing license, including the adequacy of design of the 
manufactured reactor, the costs and benefits of severe accident 
mitigation design alternatives, and the bases for not incorporating 
severe accident mitigation design alternatives into the design of the 
reactor to be manufactured.
    (b)(1) The holder of a manufacturing license may not make changes to 
the design of the nuclear power reactor authorized to be manufactured 
without prior Commission approval. The request for a change to the 
design must be in the form of an application for a license amendment, 
and must meet the requirements of 10 CFR 50.90 and 50.92.
    (2) An applicant or licensee who references or uses a nuclear power 
reactor manufactured under a manufacturing license under this subpart 
may request a departure from the design characteristics, site 
parameters, terms and conditions, or approved design of the manufactured 
reactor. The Commission may grant a request only if it determines that 
the departure will comply with the requirements of 10 CFR 52.7, and that 
the special circumstances outweigh any decrease in safety that may 
result from the reduction in standardization caused by the departure. 
The granting of a departure on request of an applicant is subject to 
litigation in the same manner as other issues in the construction permit 
or combined license hearing.
    (c) Except for information requests seeking to verify compliance 
with the current licensing basis of either the manufacturing license or 
the manufactured reactor, information requests to the holder of a 
manufacturing license or an applicant or licensee using a

[[Page 116]]

manufactured reactor must be evaluated before issuance to ensure that 
the burden to be imposed on respondents is justified in view of the 
potential safety significance of the issue to be addressed in the 
requested information. Each evaluation performed by the NRC staff must 
be in accordance with 10 CFR 50.54(f) and must be approved by the 
Executive Director for Operations or his or her designee before issuance 
of the request.



Sec. 52.173  Duration of manufacturing license.

    A manufacturing license issued under this subpart may be valid for 
not less than 5, nor more than 15 years from the date of issuance. A 
holder of a manufacturing license may not initiate the manufacture of a 
reactor less than 3 years before the expiration of the license even 
though a timely application for renewal has been docketed with the NRC. 
Upon expiration of the manufacturing license, the manufacture of any 
uncompleted reactors must cease unless a timely application for renewal 
has been docketed with the NRC.



Sec. 52.175  Transfer of manufacturing license.

    A manufacturing license may be transferred in accordance with Sec. 
50.80 of this chapter.



Sec. 52.177  Application for renewal.

    (a) Not less than 12 months, nor more than 5 years before the 
expiration of the manufacturing license, or any later renewal period, 
the holder of the manufacturing license may apply for a renewal of the 
license. An application for renewal must contain all information 
necessary to bring up to date the information and data contained in the 
previous application.
    (b) The filing of an application for a renewed license must be in 
accordance with subpart A of 10 CFR part 2 and 10 CFR 52.3 and 50.30.
    (c) A manufacturing license, either original or renewed, for which a 
timely application for renewal has been filed, remains in effect until 
the Commission has made a final determination on the renewal 
application, provided, however, that in accordance with Sec. 52.173, 
the holder of a manufacturing license may not begin manufacture of a 
reactor less than 3 years before the expiration of the license.
    (d) Any person whose interest may be affected by renewal of the 
permit may request a hearing on the application for renewal. The request 
for a hearing must comply with 10 CFR 2.309. If a hearing is granted, 
notice of the hearing will be published in accordance with 10 CFR 2.104.
    (e) The Commission shall refer a copy of the application for renewal 
to the Advisory Committee on Reactor Safeguards (ACRS). The ACRS shall 
report on those portions of the application which concern safety and 
shall apply the criteria set forth in Sec. 52.159.



Sec. 52.179  Criteria for renewal.

    The Commission may grant the renewal if the Commission determines:
    (a) The manufacturing license complies with the Atomic Energy Act 
and the Commission's regulations and orders applicable and in effect at 
the time the manufacturing license was originally issued; and
    (b) Any new requirements the Commission may wish to impose are:
    (1) Necessary for adequate protection to public health and safety or 
common defense and security;
    (2) Necessary for compliance with the Commission's regulations and 
orders applicable and in effect at the time the manufacturing license 
was originally issued; or
    (3) A substantial increase in overall protection of the public 
health and safety or the common defense and security to be derived from 
the new requirements, and the direct and indirect costs of 
implementation of those requirements are justified in view of this 
increased protection.



Sec. 52.181  Duration of renewal.

    A renewed manufacturing license may be issued for a term of not less 
than 5, nor more than 15 years, plus any remaining years on the 
manufacturing license then in effect before renewal. The renewed license 
shall be subject to the requirements of Sec. Sec. 52.171 and 52.175.

Subpart G [Reserved]

[[Page 117]]



                          Subpart H_Enforcement



Sec. 52.301  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued under those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under Section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any regulation, or order issued under the sections specified 
in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
Section 186 of the Atomic Energy Act of 1954, as amended.



Sec. 52.303  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
Sections 161b, 161i, or 161o of the Act. For purposes of Section 223, 
all the regulations in part 52 are issued under one or more of Sections 
161b, 161i, or 160o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 52 that are not issued under Sections 
161b, 161i, or 161o for the purposes of Section 223 are as follows: 
Sec. Sec. 52.0, 52.1, 52.2, 52.3, 52.7, 52.8, 52.9, 52.10, 52.11, 
52.12, 52.13, 52.15, 52.16, 52.17, 52.18, 52.21, 52.23, 52.24, 52.27, 
52.28, 52.29, 52.31, 52.33, 52.39, 52.41, 52.43, 52.45, 52.46, 52.47, 
52.48, 52.51, 52.53, 52.54, 52.55, 52.57, 52.59, 52.61, 52.63, 52.71, 
52.73, 52.75, 52.77, 52.79, 52.80, 52.81, 52.83, 52.85, 52.87, 52.93, 
52.97, 52.98, 52.103, 52.104, 52.105, 52.107, 52.109, 52.131, 52.133, 
52.135, 52.136, 52.137, 52.139, 52.141, 52.143, 52.145, 52.147, 52.151, 
52.153, 52.155, 52.156, 52.157, 52.158, 52.159, 52.161, 52.163, 52.165, 
52.167, 52.171, 52.173, 52.175, 52.177, 52.179, 52.181, 52.301, and 
52.303.



   Sec. Appendix A to Part 52--Design Certification Rule for the U.S. 
                     Advanced Boiling Water Reactor

                             I. Introduction

    A. Appendix A constitutes the standard design certification for the 
U.S. Advanced Boiling Water Reactor (U.S. ABWR) design, in accordance 
with 10 CFR part 52, subpart B. The applicant for the original 
certification of the U.S. ABWR design was GE Nuclear Energy (GE).
    B. The applicant for the amendment to the U.S. ABWR design to 
address the requirements in 10 CFR 50.150, ``Aircraft impact 
assessment,'' (AIA rule) is the STP Nuclear Operating Company (STPNOC).

                             II. Definitions

    A. Generic design control document (generic DCD) means either or 
both of the documents containing the Tier 1 and Tier 2 information and 
generic technical specifications that are incorporated by reference into 
this appendix.
    B. Generic technical specifications means the information, required 
by 10 CFR 50.36 and 50.36a, for the portion of the plant that is within 
the scope of this appendix.
    C. Plant-specific DCD means the document, maintained by an applicant 
or licensee who references this appendix, consisting of the information 
in the generic DCD, as modified and supplemented by the plant-specific 
departures and exemptions made under Section VIII of this appendix.
    D. Tier 1 means the portion of the design-related information 
contained in the generic DCD that is approved and certified by this 
appendix (hereinafter Tier 1 information). The design descriptions, 
interface requirements, and site parameters are derived from Tier 2 
information. Tier 1 information includes:
    1. Definitions and general provisions;
    2. Design descriptions;
    3. Inspections, tests, analyses, and acceptance criteria (ITAAC);
    4. Significant site parameters; and
    5. Significant interface requirements.
    E. Tier 2 means the portion of the design-related information 
contained in the generic DCD that is approved but not certified by this 
appendix (Tier 2 information). Compliance with Tier 2 is required, but 
generic changes to and plant-specific departures from Tier 2 are 
governed by Section VIII of this appendix. Compliance with Tier 2 
provides a sufficient, but not the only acceptable, method for complying 
with Tier 1. Compliance methods differing from Tier 2 must satisfy the 
change process in Section

[[Page 118]]

VIII of this appendix. Regardless of these differences, an applicant or 
licensee must meet the requirement in Section III.B of this appendix to 
reference Tier 2 when referencing Tier 1. Tier 2 information includes:
    1. Information required by Sec. Sec. 52.47(a) and 52.47(c), with 
the exception of generic technical specifications and conceptual design 
information;
    2. Supporting information on the inspections, tests, and analyses 
that will be performed to demonstrate that the acceptance criteria in 
the ITAAC have been met; and
    3. Combined license (COL) action items (COL license information), 
which identify certain matters that must be addressed in the site-
specific portion of the final safety analysis report (FSAR) by an 
applicant who references this appendix. These items constitute 
information requirements but are not the only acceptable set of 
information in the FSAR. An applicant may depart from or omit these 
items, provided that the departure or omission is identified and 
justified in the FSAR. After issuance of a construction permit or COL, 
these items are not requirements for the licensee unless such items are 
restated in the FSAR.
    F. Tier 2* means the portion of the Tier 2 information, designated 
as such in the generic DCD, which is subject to the change process in 
Section VIII.B.6 of this appendix. This designation expires for some 
Tier 2* information under Section VIII.B.6.
    G. Departure from a method of evaluation described in the plant-
specific DCD used in establishing the design bases or in the safety 
analyses means:
    (1) Changing any of the elements of the method described in the 
plant-specific DCD unless the results of the analysis are conservative 
or essentially the same; or
    (2) Changing from a method described in the plant-specific DCD to 
another method unless that method has been approved by NRC for the 
intended application.
    H. All other terms in this appendix have the meaning set out in 10 
CFR 50.2 or 52.1, or Section 11 of the Atomic Energy Act of 1954, as 
amended, as applicable.

                         III. Scope and Contents

                       A. Design Control Documents

    1. Incorporation by reference approval. Certain documents identified 
in paragraphs III.A.2 and III.A.3 of this section are approved for 
incorporation by reference into this appendix by the Director of the 
Office of the Federal Register in accordance with 5 U.S.C. 552(a) and 1 
CFR part 51. Documents approved for incorporation by reference and 
created or received at the NRC are available online in the NRC Library 
at http://www.nrc.gov/reading-rm/adams.html. From this page, the public 
can gain entry into ADAMS, which provides text and image files of the 
NRC's public documents. If you do not have access to ADAMS or if there 
are problems in accessing the documents located in ADAMS, then contact 
the NRC's Public Document Room (PDR) reference staff at (800) 397-4209, 
(301) 415-3747, or by email at [email protected]. A copy of these 
DCDs approved for incorporation by reference are available for 
examination and copying at the NRC's PDR located at Room O-1F21, One 
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. 
Copies are also available for examination at the NRC Library located at 
Two White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852, 
telephone: (301) 415-5610, email: [email protected]. All approved 
material is available for inspection at the National Archives and 
Records Administration (NARA). For information on the availability of 
this material at NARA, call (202) 741-6030 or go to http://
www.archives.gov/federal-register/cfr/ibr-locations.html.
    2. GE DCD: All Tier 1, Tier 2, and the generic technical 
specifications in the GE Nuclear Energy (GE) ``ABWR Design Control 
Document, Revision 4, March 1997'' (GE DCD). You may obtain copies of 
the GE DCD from the National Technical Information Service, 5285 Port 
Royal Road, Springfield, Virginia 22161, (703) 605-6515. To view the GE 
DCD in ADAMS, search under ADAMS Accession No. ML11126A129. The GE DCD 
can also be viewed at the Federal Rulemaking Web site, http://
www.regulations.gov, by searching for documents filed under Docket ID 
NRC-2010-0134.
    3. STPNOC DCD: All Tier 1 and Tier 2 information in the STP Nuclear 
Operating Company ``Design Control Document ABWR STP Aircraft Impact 
Assessment Amendment Revision 3, Copyright @ 2010'' (STPNOC DCD). You 
may obtain copies of the STPNOC DCD from the Regulatory Affairs Manager 
for STP Units 3 and 4, STP Nuclear Operating Company, P.O. Box 289, 
Wadsworth, Texas 77483, telephone: (361) 972-8440. To view the STPNOC 
DCD in ADAMS, search under ADAMS Accession No. ML102870017. The STPNOC 
DCD can also be viewed at the Federal Rulemaking Web site, http://
www.regulations.gov, by searching for documents filed under Docket ID 
NRC-2010-0134.
    B.1. An applicant or licensee referencing this appendix, in 
accordance with section IV of this appendix, shall incorporate by 
reference and comply with the requirements of this appendix, including 
Tier 1, Tier 2, and the generic technical specifications except as 
otherwise provided in this appendix. An applicant or licensee 
referencing this appendix may reference either the GE DCD, or both the 
GE DCD and the STPNOC DCD. An applicant referencing this appendix shall 
indicate

[[Page 119]]

in its application and in all necessary supporting documentation whether 
it is implementing the GE DCD, or both the GE DCD and the STPNOC DCD.
    2. Conceptual design information, as set forth in the generic DCD, 
and the ``Technical Support Document for the ABWR'' are not part of this 
appendix. Tier 2 references to the probabilistic risk assessment (PRA) 
in the ABWR standard safety analysis report do not incorporate the PRA 
into Tier 2.
    C. If there is a conflict between Tier 1 and Tier 2 of a DCD, then 
Tier 1 controls.
    D. If there is a conflict between the generic DCD and the 
application for design certification of the U.S. ABWR design, NUREG-
1503, ``Final Safety Evaluation Report related to the Certification of 
the Advanced Boiling Water Reactor Design'' (ABWR FSER), and Supplement 
No. 1, or NUREG-1948 ``Safety Evaluation Report--The STP Nuclear 
Operating Company Amendment to the Advanced Boiling Water Reactor (ABWR) 
Design Certification'' (AIA FSER), then the generic DCD controls.
    E. Design activities for structures, systems, and components that 
are wholly outside the scope of this appendix may be performed using 
site characteristics, provided the design activities do not affect the 
DCD or conflict with the interface requirements.

              IV. Additional Requirements and Restrictions

    A. An applicant for a combined license that wishes to reference this 
appendix shall, in addition to complying with the requirements of 10 CFR 
52.77, 52.79, and 52.80, comply with the following requirements:
    1. Incorporate by reference, as part of its application, this 
appendix;
    2. Include, as part of its application:
    a. A plant-specific DCD containing the same type of information and 
using the same organization and numbering as the generic DCD for the 
U.S. ABWR design, as modified and supplemented by the applicant's 
exemptions and departures;
    b. The reports on departures from and updates to the plant-specific 
DCD required by paragraph X.B of this appendix;
    c. Plant-specific technical specifications, consisting of the 
generic and site-specific technical specifications, that are required by 
10 CFR 50.36 and 50.36a;
    d. Information demonstrating compliance with the site parameters and 
interface requirements;
    e. Information that addresses the COL action items; and
    f. Information required by 10 CFR 52.47 that is not within the scope 
of this appendix.
    3. Include, in the plant-specific DCD, the sensitive unclassified 
non-safeguards information (including proprietary information) and 
safeguards information referenced in the GE DCD and the STPNOC DCD, as 
applicable.
    4.a. Include, as part of its application, a demonstration that an 
entity other than GE Nuclear Energy is qualified to supply the U.S. 
ABWR-certified design unless GE Nuclear Energy supplies the design for 
the applicant's use.
    b. For an applicant referencing the STPNOC-certified design option, 
include, as part of its application, a demonstration that an entity 
other than the STPNOC and Toshiba America Nuclear Energy (TANE) acting 
together is qualified to supply the STPNOC-certified design option, 
unless the STPNOC and TANE acting together supply the design option for 
the applicant's use.
    B. The Commission reserves the right to determine in what manner 
this appendix may be referenced by an applicant for a construction 
permit or operating license under 10 CFR part 50.

                        V. Applicable Regulations

    A.1. Except as indicated in paragraph B of this section, the 
regulations that apply to the U.S. ABWR design as contained in the GE 
DCD are in 10 CFR parts 20, 50, 73, and 100, codified as of May 2, 1997, 
that are applicable and technically relevant, as described in the FSER 
(NUREG-1503) and Supplement No. 1.
    2. Except as indicated in paragraph B of this section, the 
regulations that apply to the U.S. ABWR design as contained in the 
STPNOC DCD are those described in paragraph A.1 of this section and 10 
CFR 50.150, codified as of December 7, 2011, as described in the FSER on 
the STPNOC amendment addressing the AIA rule (NUREG-1948).
    B. The U.S. ABWR design is exempt from portions of the following 
regulations:
    1. Paragraph (f)(2)(iv) of 10 CFR 50.34--Separate Plant Safety 
Parameter Display Console;
    2. Paragraph (f)(2)(viii) of 10 CFR 50.34--Post-Accident Sampling 
for Boron, Chloride, and Dissolved Gases; and
    3. Paragraph (f)(3)(iv) of 10 CFR 50.34--Dedicated Containment 
Penetration.

                          VI. Issue Resolution

    A.1. GE DCD. The Commission has determined that the structures, 
systems, components, and design features of the U.S. ABWR design, as 
contained in the GE DCD, comply with the provisions of the Atomic Energy 
Act of 1954, as amended, and the applicable regulations identified in 
section V.A.1 of this appendix; and, therefore, provide adequate 
protection to the health and safety of the public. A conclusion that a 
matter is resolved includes the finding that additional or alternative 
structures, systems, components, design features, design criteria, 
testing,

[[Page 120]]

analyses, acceptance criteria, or justifications are not necessary for 
the U.S. ABWR design. This conclusion does not include a finding with 
respect to compliance with the requirements of 10 CFR 50.150.
    2. STPNOC DCD. The Commission has determined that the structures, 
systems, components, and design features of the STPNOC amendment to the 
U.S. ABWR design, as contained in the STPNOC DCD, comply with the 
provisions of the Atomic Energy Act of 1954, as amended, and the 
applicable regulations identified in section V.A.2 of this appendix, 
including 10 CFR 50.150; and, therefore, provide enhanced protection to 
the health and safety of the public afforded by compliance with 10 CFR 
50.150. A conclusion that a matter is resolved includes the finding that 
additional or alternative structures, systems, components, design 
features, design criteria, testing, analyses, acceptance criteria, or 
justifications to meet the requirements of 10 CFR 50.150 are not 
necessary for the STPNOC amendment to the U.S. ABWR design.
    3. GE and STPNOC DCD referenced together. The Commission has 
determined that the structures, systems, components, and design features 
of the U.S. ABWR, as contained in both the GE DCD and the STPNOC DCD, 
when referenced together, comply with the provisions of the Atomic 
Energy Act of 1954, as amended, and the applicable regulations 
identified in section V.A. of this appendix; and, therefore, provide 
adequate protection to the health and safety of the public. A conclusion 
that a matter is resolved includes the finding that additional or 
alternative structures, systems, components, design features, design 
criteria, testing, analyses, acceptance criteria, or justifications are 
not necessary for the U.S. ABWR design, when the GE DCD and the STPNOC 
DCD are referenced together.
    B. The Commission considers the following matters resolved within 
the meaning of 10 CFR 52.63(a)(5) in subsequent proceedings for issuance 
of a combined license, amendment of a combined license, or renewal of a 
combined license, proceedings held under 10 CFR 52.103, and enforcement 
proceedings involving plants referencing this appendix:
    1. All nuclear safety issues, except for the generic technical 
specifications and other operational requirements, associated with the 
information in the ABWR FSER and Supplement No. 1, Tier 1, Tier 2 
(including referenced information which the context indicates is 
intended as requirements), and the rulemaking record for the original 
certification of the U.S. ABWR design and all nuclear safety issues, 
except for operational requirements, associated with the information in 
the AIA FSER, Tier 1, Tier 2 (including referenced information which the 
context indicates is intended as requirements), and the rulemaking 
record for certification of the AIA amendment to the U.S. ABWR design;
    2. All nuclear safety and safeguards issues associated with the 
referenced sensitive unclassified non-safeguards information (including 
proprietary information) and safeguards information which, in context, 
are intended as requirements in the GE DCD and the STPNOC DCD;
    3. All generic changes to the DCD under and in compliance with the 
change processes in sections VIII.A.1 and VIII.B.1 of this appendix;
    4. All exemptions from the DCD under and in compliance with the 
change processes in sections VIII.A.4 and VIII.B.4 of this appendix, but 
only for that plant;
    5. All departures from the DCD that are approved by license 
amendment, but only for that plant;
    6. Except as provided in paragraph VIII.B.5.g of this appendix, all 
departures from Tier 2 pursuant to and in compliance with the change 
processes in paragraph VIII.B.5 of this appendix that do not require 
prior NRC approval, but only for that plant;
    7. All environmental issues concerning severe accident mitigation 
design alternatives associated with the information in the NRC's final 
environmental assessment for the U.S. ABWR design and Revision 1 of the 
technical support document for the U.S. ABWR, dated December 1994, and 
for the NRC's final environmental assessment and Revision 0 of ABWR-LIC-
09-621, ``Applicant's Supplemental Environmental Report-Amendment to 
ABWR Standard Design Certification,'' for the AIA amendment to the U.S. 
ABWR design for plants referencing this appendix whose site parameters 
are within those specified in the technical support document.
    C. The Commission does not consider operational requirements for an 
applicant or licensee who references this appendix to be matters 
resolved within the meaning of 10 CFR 52.63(a)(5). The Commission 
reserves the right to require operational requirements for an applicant 
or licensee who references this appendix by rule, regulation, order, or 
license condition.
    D. Except in accordance with the change processes in Section VIII of 
this appendix, the Commission may not require an applicant or licensee 
who references this appendix to:
    1. Modify structures, systems, components, or design features as 
described in the generic DCD;
    2. Provide additional or alternative structures, systems, 
components, or design features not discussed in the generic DCD; or
    3. Provide additional or alternative design criteria, testing, 
analyses, acceptance criteria, or justification for structures, systems, 
components, or design features discussed in the generic DCD.

[[Page 121]]

    E. The NRC will specify at an appropriate time the procedures to be 
used by an interested person who wishes to review portions of the design 
certification or references containing safeguards information or 
sensitive unclassified non-safeguards information (including proprietary 
information, such as trade secrets and commercial or financial 
information obtained from a person that are privileged or confidential 
(10 CFR 2.390 and 10 CFR part 9)), for the purpose of participating in 
the hearing required by 10 CFR 52.85, the hearing provided under 10 CFR 
52.103, or in any other proceeding relating to this appendix in which 
interested persons have a right to request an adjudicatory hearing.

                     VII. Duration of This Appendix

    This appendix may be referenced for a period of 15 years from June 
11, 1997, except as provided for in 10 CFR 52.55(b) and 52.57(b). This 
appendix remains valid for an applicant or licensee who references this 
appendix until the application is withdrawn or the license expires, 
including any period of extended operation under a renewed license.

               VIII. Processes for Changes and Departures

    A. Tier 1 information.
    1. Generic changes to Tier 1 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 1 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs A.3 or A.4 of this section.
    3. Departures from Tier 1 information that are required by the 
Commission through plant-specific orders are governed by the 
requirements in 10 CFR 52.63(a)(4).
    4. Exemptions from Tier 1 information are governed by the 
requirements in 10 CFR 52.63(b)(1) and 52.98(f). The Commission will 
deny a request for an exemption from Tier 1, if it finds that the design 
change will result in a significant decrease in the level of safety 
otherwise provided by the design.
    B. Tier 2 information.
    1. Generic changes to Tier 2 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 2 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs B.3, B.4, B.5, or B.6 of this section.
    3. The Commission may not require new requirements on Tier 2 
information by plant-specific order while this appendix is in effect 
under Sec. Sec. 52.55 or 52.61, unless:
    a. A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time this 
appendix was approved, as set forth in Section V of this appendix, or to 
assure adequate protection of the public health and safety or the common 
defense and security; and
    b. Special circumstances as defined in 10 CFR 52.7 are present.
    4. An applicant or licensee who references this appendix may request 
an exemption from Tier 2 information. The Commission may grant such a 
request only if it determines that the exemption will comply with the 
requirements of 10 CFR 52.7. The Commission will deny a request for an 
exemption from Tier 2, if it finds that the design change will result in 
a significant decrease in the level of safety otherwise provided by the 
design. The grant of an exemption to an applicant must be subject to 
litigation in the same manner as other issues material to the license 
hearing. The grant of an exemption to a licensee must be subject to an 
opportunity for a hearing in the same manner as license amendments.
    5.a. An applicant or licensee who references this appendix may 
depart from Tier 2 information, without prior NRC approval, unless the 
proposed departure involves a change to or departure from Tier 1 
information, Tier 2* information, or the technical specifications, or 
requires a license amendment under paragraphs B.5.b or B.5.c of this 
section. When evaluating the proposed departure, an applicant or 
licensee shall consider all matters described in the plant-specific DCD.
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-specific 
DCD or one affecting information required by 10 CFR 52.47(a)(28) to 
address 10 CFR 50.150, requires a license amendment if it would:
    (1) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the plant-specific 
DCD;
    (2) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a structure, system, or component (SSC) 
important to safety previously evaluated in the plant-specific DCD;
    (3) Result in more than a minimal increase in the consequences of an 
accident previously evaluated in the plant-specific DCD;
    (4) Result in more than a minimal increase in the consequences of a 
malfunction of a SSC important to safety previously evaluated in the 
plant-specific DCD;
    (5) Create a possibility for an accident of a different type than 
any evaluated previously in the plant-specific DCD;
    (6) Create a possibility for a malfunction of an SSC important to 
safety with a different

[[Page 122]]

result than any evaluated previously in the plant-specific DCD;
    (7) Result in a design basis limit for a fission product barrier as 
described in the plant-specific DCD being exceeded or altered; or
    (8) Result in a departure from a method of evaluation described in 
the plant-specific DCD used in establishing the design bases or in the 
safety analyses.
    c. A proposed departure from Tier 2 affecting resolution of an ex-
vessel severe accident design feature identified in the plant-specific 
DCD, requires a license amendment if:
    (1) There is a substantial increase in the probability of an ex-
vessel severe accident such that a particular ex-vessel severe accident 
previously reviewed and determined to be not credible could become 
credible; or
    (2) There is a substantial increase in the consequences to the 
public of a particular ex-vessel severe accident previously reviewed.
    d. If an applicant or licensee proposes to depart from the 
information required by 10 CFR 52.47(a)(28) to be included in the FSAR 
for the standard design certification, then the applicant or licensee 
shall consider the effect of the changed feature or capability on the 
original assessment required by 10 CFR 50.150(a). The applicant or 
licensee must also document how the modified design features and 
functional capabilities continue to meet the assessment requirements in 
10 CFR 50.150(a)(1) in accordance with section X of this appendix.
    e. If a departure requires a license amendment pursuant to 
paragraphs B.5.b or B.5.c of this section, it is governed by 10 CFR 
50.90.
    f. A departure from Tier 2 information that is made under paragraph 
B.5 of this section does not require an exemption from this appendix.
    g. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an applicant or licensee who references 
this appendix has not complied with paragraph VIII.B.5 of this appendix 
when departing from Tier 2 information, may petition the NRC to admit 
into the proceeding such a contention. In addition to compliance with 
the general requirements of 10 CFR 2.309, the petition must demonstrate 
that the departure does not comply with paragraph VIII.B.5 of this 
appendix. Further, the petition must demonstrate that the change bears 
on an asserted noncompliance with an ITAAC acceptance criterion in the 
case of a 10 CFR 52.103 preoperational hearing, or that the change bears 
directly on the amendment request in the case of a hearing on a license 
amendment. Any other party may file a response. If, on the basis of the 
petition and any response, the presiding officer determines that a 
sufficient showing has been made, the presiding officer shall certify 
the matter directly to the Commission for determination of the 
admissibility of the contention. The Commission may admit such a 
contention if it determines the petition raises a genuine issue of 
material fact regarding compliance with paragraph VIII.B.5 of this 
appendix.
    6.a. An applicant who references this appendix may not depart from 
Tier 2* information, which is designated with italicized text or 
brackets and an asterisk in the generic DCD, without NRC approval. The 
departure will not be considered a resolved issue, within the meaning of 
Section VI of this appendix and 10 CFR 52.63(a)(5).
    b. A licensee who references this appendix may not depart from the 
following Tier 2* matters without prior NRC approval. A request for a 
departure will be treated as a request for a license amendment under 10 
CFR 50.90.
    (1) Fuel burnup limit (4.2).
    (2) Fuel design evaluation (4.2.3).
    (3) Fuel licensing acceptance criteria (appendix 4B).
    c. A licensee who references this appendix may not, before the plant 
first achieves full power following the finding required by 10 CFR 
52.103(g), depart from the following Tier 2* matters except in 
accordance with paragraph B.6.b of this section. After the plant first 
achieves full power, the following Tier 2* matters revert to Tier 2 
status and are thereafter subject to the departure provisions in 
paragraph B.5 of this section.
    (1) ASME Boiler & Pressure Vessel Code, Section III.
    (2) ACI 349 and ANSI/AISC-690.
    (3) Motor-operated valves.
    (4) Equipment seismic qualification methods.
    (5) Piping design acceptance criteria.
    (6) Fuel system and assembly design (4.2), except burnup limit.
    (7) Nuclear design (4.3).
    (8) Equilibrium cycle and control rod patterns (App. 4A).
    (9) Control rod licensing acceptance criteria (App. 4C).
    (10) Instrument setpoint methodology.
    (11) EMS performance specifications and architecture.
    (12) SSLC hardware and software qualification.
    (13) Self-test system design testing features and commitments.
    (14) Human factors engineering design and implementation process.
    d. Departures from Tier 2* information that are made under paragraph 
B.6 of this section do not require an exemption from this appendix.
    C. Operational requirements.

[[Page 123]]

    1. Generic changes to generic technical specifications and other 
operational requirements that were completely reviewed and approved in 
the design certification rulemaking and do not require a change to a 
design feature in the generic DCD are governed by the requirements in 10 
CFR 50.109. Generic changes that do require a change to a design feature 
in the generic DCD are governed by the requirements in paragraphs A or B 
of this section.
    2. Generic changes to generic TS and other operational requirements 
are applicable to all applicants who reference this appendix, except 
those for which the change has been rendered technically irrelevant by 
action taken under paragraphs C.3 or C.4 of this section.
    3. The Commission may require plant-specific departures on generic 
technical specifications and other operational requirements that were 
completely reviewed and approved, provided a change to a design feature 
in the generic DCD is not required and special circumstances as defined 
in 10 CFR 2.335 are present. The Commission may modify or supplement 
generic technical specifications and other operational requirements that 
were not completely reviewed and approved or require additional 
technical specifications and other operational requirements on a plant-
specific basis, provided a change to a design feature in the generic DCD 
is not required.
    4. An applicant who references this appendix may request an 
exemption from the generic technical specifications or other operational 
requirements. The Commission may grant such a request only if it 
determines that the exemption will comply with the requirements of 10 
CFR 52.7. The grant of an exemption must be subject to litigation in the 
same manner as other issues material to the license hearing.
    5. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an operational requirement approved in the 
DCD or a technical specification derived from the generic technical 
specifications must be changed may petition to admit into the proceeding 
such a contention. Such petition must comply with the general 
requirements of 10 CFR 2.309 and must demonstrate why special 
circumstances as defined in 10 CFR 2.335 are present, or for compliance 
with the Commission's regulations in effect at the time this appendix 
was approved, as set forth in Section V of this appendix. Any other 
party may file a response thereto. If, on the basis of the petition and 
any response, the presiding officer determines that a sufficient showing 
has been made, the presiding officer shall certify the matter directly 
to the Commission for determination of the admissibility of the 
contention. All other issues with respect to the plant-specific 
technical specifications or other operational requirements are subject 
to a hearing as part of the license proceeding.
    6. After issuance of a license, the generic technical specifications 
have no further effect on the plant-specific technical specifications 
and changes to the plant-specific technical specifications will be 
treated as license amendments under 10 CFR 50.90.

    IX. Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

    A.1. An applicant or licensee who references this appendix shall 
perform and demonstrate conformance with the ITAAC before fuel load. 
With respect to activities subject to an ITAAC, an applicant for a 
license may proceed at its own risk with design and procurement 
activities, and a licensee may proceed at its own risk with design, 
procurement, construction, and preoperational activities, even though 
the NRC may not have found that any particular ITAAC has been met.
    2. The licensee who references this appendix shall notify the NRC 
that the required inspections, tests, and analyses in the ITAAC have 
been successfully completed and that the corresponding acceptance 
criteria have been met.
    3. In the event that an activity is subject to an ITAAC, and the 
applicant or licensee who references this appendix has not demonstrated 
that the ITAAC has been met, the applicant or licensee may either take 
corrective actions to successfully complete that ITAAC, request an 
exemption from the ITAAC in accordance with Section VIII of this 
appendix and 10 CFR 52.97(b), or petition for rulemaking to amend this 
appendix by changing the requirements of the ITAAC, under 10 CFR 2.802 
and 52.97(b). Such rulemaking changes to the ITAAC must meet the 
requirements of paragraph VIII.A.1 of this appendix.
    B.1. The NRC shall ensure that the required inspections, tests, and 
analyses in the ITAAC are performed. The NRC shall verify that the 
inspections, tests, and analyses referenced by the licensee have been 
successfully completed and, based solely thereon, find the prescribed 
acceptance criteria have been met. At appropriate intervals during 
construction, the NRC shall publish notices of the successful completion 
of ITAAC in the Federal Register.
    2. In accordance with 10 CFR 52.103(g), the Commission shall find 
that the acceptance criteria in the ITAAC for the license are met before 
fuel load.
    3. After the Commission has made the finding required by 10 CFR 
52.103(g), the ITAAC do not, by virtue of their inclusion within the 
DCD, constitute regulatory requirements either for licensees or for 
renewal of the license; except for specific ITAAC, which are

[[Page 124]]

the subject of a Sec. 52.103(a) hearing, their expiration will occur 
upon final Commission action in such proceeding. However, subsequent 
modifications must comply with the Tier 1 and Tier 2 design descriptions 
in the plant-specific DCD unless the licensee has complied with the 
applicable requirements of 10 CFR 52.98 and Section VIII of this 
appendix.

                        X. Records and Reporting

    A. Records.
    1. The applicants for this appendix shall maintain a copy of the 
applicable generic DCD that includes all generic changes to Tier 1, Tier 
2, and the generic technical specifications and other operational 
requirements. The applicants shall maintain the sensitive unclassified 
non-safeguards information (including proprietary information) and 
safeguards information referenced in the applicable generic DCD for the 
period that this appendix may be referenced, as specified in Section VII 
of this appendix.
    2. An applicant or licensee who references this appendix shall 
maintain the plant-specific DCD to accurately reflect both generic 
changes to the generic DCD and plant-specific departures made under 
Section VIII of this appendix throughout the period of application and 
for the term of the license (including any period of renewal).
    3. An applicant or licensee who references this appendix shall 
prepare and maintain written evaluations which provide the bases for the 
determinations required by Section VIII of this appendix. These 
evaluations must be retained throughout the period of application and 
for the term of the license (including any period of renewal).
    4.a. The applicant for the amendment to the U.S. ABWR design to 
address the requirements in 10 CFR 50.150, ``Aircraft impact 
assessment,'' shall maintain a copy of the aircraft impact assessment 
performed to comply with the requirements of 10 CFR 50.150(a) for the 
term of the certification (including any period of renewal).
    b. An applicant or licensee who references this appendix to include 
both the GE DCD and the STPNOC DCD shall maintain a copy of the aircraft 
impact assessment performed to comply with the requirements of 10 CFR 
50.150(a) throughout the pendency of the application and for the term of 
the license (including any period of renewal).
    B. Reporting.
    1. An applicant or licensee who references this appendix shall 
submit a report to the NRC containing a brief description of any plant-
specific departures from the DCD, including a summary of the evaluation 
of each. This report must be filed in accordance with the filing 
requirements applicable to reports in 10 CFR 52.3.
    2. An applicant or licensee who references this appendix shall 
submit updates to its DCD, which reflect the generic changes and the 
plant-specific departures from the generic DCD made under Section VIII 
of this appendix. These updates must be filed under the filing 
requirements applicable to final safety analysis report updates in 10 
CFR 52.3 and 50.71(e).
    3. The reports and updates required by paragraphs X.B.1 and X.B.2 
must be submitted as follows:
    a. On the date that an application for a license referencing this 
appendix is submitted, the application must include the report and any 
updates to the generic DCD.
    b. During the interval from the date of application for a license to 
the date the Commission makes the finding required by 10 CFR 52.103(g), 
the report must be submitted semiannually. Updates to the plant-specific 
DCD must be submitted annually and may be submitted along with 
amendments to the application.
    c. After the Commission makes the finding required by 10 CFR 
52.103(g), reports and updates to the plant-specific DCD must be 
submitted, along with updates to the site-specific portion of the final 
safety analysis report for the facility, at the intervals required by 10 
CFR 50.59(d)(2) and 10 CFR 50.71(e)(4), respectively, or at shorter 
intervals as specified in the license.

[72 FR 49517, Aug. 28, 2007, as amended at 76 FR 72085, Nov. 22, 2011; 
76 FR 78119, Dec. 16, 2011]



Sec. Appendix B to Part 52--Design Certification Rule for the System 80 
                                + Design

                             I. Introduction

    Appendix B constitutes design certification for the System 80 + \1\ 
standard plant design, in accordance with 10 CFR part 52, subpart B. The 
applicant for certification of the System 80 + design was Combustion 
Engineering, Inc. (ABB-CE), which is now Westinghouse Electric Company 
LLC.
---------------------------------------------------------------------------

    \1\ ``System 80 + '' is a trademark of Westinghouse Electric Company 
LLC.
---------------------------------------------------------------------------

                             II. Definitions

    A. Generic design control document (generic DCD) means the document 
containing the Tier 1 and Tier 2 information and generic technical 
specifications that is incorporated by reference into this appendix.
    B. Generic technical specifications means the information, required 
by 10 CFR 50.36 and 50.36a, for the portion of the plant that is within 
the scope of this appendix.
    C. Plant-specific DCD means the document, maintained by an applicant 
or licensee who references this appendix, consisting of

[[Page 125]]

the information in the generic DCD, as modified and supplemented by the 
plant-specific departures and exemptions made under Section VIII of this 
appendix.
    D. Tier 1 means the portion of the design-related information 
contained in the generic DCD that is approved and certified by this 
appendix (hereinafter Tier 1 information). The design descriptions, 
interface requirements, and site parameters are derived from Tier 2 
information. Tier 1 information includes:
    1. Definitions and general provisions;
    2. Design descriptions;
    3. Inspections, tests, analyses, and acceptance criteria (ITAAC);
    4. Significant site parameters; and
    5. Significant interface requirements.
    E. Tier 2 means the portion of the design-related information 
contained in the generic DCD that is approved but not certified by this 
appendix (Tier 2 information). Compliance with Tier 2 is required, but 
generic changes to and plant-specific departures from Tier 2 are 
governed by Section VIII of this appendix. Compliance with Tier 2 
provides a sufficient, but not the only acceptable, method for complying 
with Tier 1. Compliance methods differing from Tier 2 must satisfy the 
change process in Section VIII of this appendix. Regardless of these 
differences, an applicant or licensee must meet the requirement in 
Section III.B of this appendix to reference Tier 2 when referencing Tier 
1. Tier 2 information includes:
    1. Information required by Sec. Sec. 52.47(a) and 52.47(c), with 
the exception of generic technical specifications and conceptual design 
information;
    2. Supporting information on the inspections, tests, and analyses 
that will be performed to demonstrate that the acceptance criteria in 
the ITAAC have been met; and
    3. Combined license (COL) action items (COL license information), 
which identify certain matters that must be addressed in the site-
specific portion of the final safety analysis report (FSAR) by an 
applicant who references this appendix. These items constitute 
information requirements but are not the only acceptable set of 
information in the FSAR. An applicant may depart from or omit these 
items, provided that the departure or omission is identified and 
justified in the FSAR. After issuance of a construction permit or COL, 
these items are not requirements for the licensee unless such items are 
restated in the FSAR.
    F. Tier 2* means the portion of the Tier 2 information, designated 
as such in the generic DCD, which is subject to the change process in 
Section VIII.B.6 of this appendix. This designation expires for some 
Tier 2* information under Section VIII.B.6 of this appendix.
    G. Departure from a method of evaluation described in the plant-
specific DCD used in establishing the design bases or in the safety 
analyses means:
    (1) Changing any of the elements of the method described in the 
plant-specific DCD unless the results of the analysis are conservative 
or essentially the same; or
    (2) Changing from a method described in the plant-specific DCD to 
another method unless that method has been approved by NRC for the 
intended application.
    H. All other terms in this appendix have the meaning set out in 10 
CFR 50.2 or 52.1, or Section 11 of the Atomic Energy Act of 1954, as 
amended, as applicable.

                         III. Scope and Contents

    A. Tier 1, Tier 2, and the generic technical specifications in the 
System 80 + Design Control Document, ABB-CE, with revisions dated 
January 1997, are approved for incorporation by reference by the 
Director of the Office of the Federal Register in accordance with 5 
U.S.C. 552(a) and 1 CFR part 51. Copies of the generic DCD may be 
obtained from the National Technical Information Service, 5285 Port 
Royal Road, Springfield, Virginia 22161. A copy is available for 
examination and copying at the NRC Public Document Room located at One 
White Flint North, 11555 Rockville Pike (first floor), Rockville, 
Maryland 20852. Copies are also available for examination at the NRC 
Library located at Two White Flint North, 11545 Rockville Pike, 
Rockville, Maryland 20852 and the Office of the Federal Register, 800 
North Capitol Street, NW., Suite 700, Washington, DC.
    B. An applicant or licensee referencing this appendix, in accordance 
with Section IV of this appendix, shall incorporate by reference and 
comply with the requirements of this appendix, including Tier 1, Tier 2, 
and the generic technical specifications except as otherwise provided in 
this appendix. Conceptual design information, as set forth in the 
generic DCD, and the Technical Support Document for the System 80 + 
design are not part of this appendix.
    C. If there is a conflict between Tier 1 and Tier 2 of the DCD, then 
Tier 1 controls.
    D. If there is a conflict between the generic DCD and either the 
application for design certification of the System 80 + design or NUREG-
1462, ``Final Safety Evaluation Report Related to the Certification of 
the System 80 + Design,'' (FSER) and Supplement No. 1, then the generic 
DCD controls.
    E. Design activities for structures, systems, and components that 
are wholly outside the scope of this appendix may be performed using 
site characteristics, provided the design activities do not affect the 
DCD or conflict with the interface requirements.

[[Page 126]]

              IV. Additional Requirements and Restrictions

    A. An applicant for a combined license that wishes to reference this 
appendix shall, in addition to complying with the requirements of 10 CFR 
52.77, 52.79, and 52.80, comply with the following requirements:
    1. Incorporate by reference, as part of its application, this 
appendix;
    2. Include, as part of its application:
    a. A plant-specific DCD containing the same type of information and 
using the same organization and numbering as the generic DCD for the 
System 80 + design, as modified and supplemented by the applicant's 
exemptions and departures;
    b. The reports on departures from and updates to the plant-specific 
DCD required by paragraph X.B of this appendix;
    c. Plant-specific technical specifications, consisting of the 
generic and site-specific technical specifications, that are required by 
10 CFR 50.36 and 50.36a;
    d. Information demonstrating compliance with the site parameters and 
interface requirements;
    e. Information that addresses the COL action items; and
    f. Information required by 10 CFR 52.47 that is not within the scope 
of this appendix.
    3. Include, in the plant-specific DCD, the proprietary information 
referenced in the System 80 + DCD.
    B. The Commission reserves the right to determine in what manner 
this appendix may be referenced by an applicant for a construction 
permit or operating license under 10 CFR part 50.

                        V. Applicable Regulations

    A. Except as indicated in paragraph B of this section, the 
regulations that apply to the System 80 + design are in 10 CFR parts 20, 
50, 73, and 100, codified as of May 9, 1997, that are applicable and 
technically relevant, as described in the FSER (NUREG-1462) and 
Supplement No. 1.
    B. The System 80 + design is exempt from portions of the following 
regulations:
    1. Paragraph (f)(2)(iv) of 10 CFR 50.34--Separate Plant Safety 
Parameter Display Console;
    2. Paragraphs (f)(2) (vii), (viii), (xxvi), and (xxviii) of 10 CFR 
50.34--Accident Source Terms;
    3. Paragraph (f)(2)(viii) of 10 CFR 50.34--Post-Accident Sampling 
for Hydrogen, Boron, Chloride, and Dissolved Gases;
    4. Paragraph (f)(3)(iv) of 10 CFR 50.34--Dedicated Containment 
Penetration; and
    5. Paragraphs III.A.1(a) and III.C.3(b) of Appendix J to 10 CFR 50--
Containment Leakage Testing.

                          VI. Issue Resolution

    A. The Commission has determined that the structures, systems, 
components, and design features of the System 80 + design comply with 
the provisions of the Atomic Energy Act of 1954, as amended, and the 
applicable regulations identified in Section V of this appendix; and 
therefore, provide adequate protection to the health and safety of the 
public. A conclusion that a matter is resolved includes the finding that 
additional or alternative structures, systems, components, design 
features, design criteria, testing, analyses, acceptance criteria, or 
justifications are not necessary for the System 80 + design.
    B. The Commission considers the following matters resolved within 
the meaning of 10 CFR 52.63(a)(5) in subsequent proceedings for issuance 
of a combined license, amendment of a combined license, or renewal of a 
combined license, proceedings held under 10 CFR 52.103, and enforcement 
proceedings involving plants referencing this appendix:
    1. All nuclear safety issues, except for the generic technical 
specifications and other operational requirements, associated with the 
information in the FSER and Supplement No. 1, Tier 1, Tier 2 (including 
referenced information which the context indicates is intended as 
requirements), and the rulemaking record for certification of the System 
80 + design;
    2. All nuclear safety and safeguards issues associated with the 
information in proprietary and safeguards documents, referenced and in 
context, are intended as requirements in the generic DCD for the System 
80 + design;
    3. All generic changes to the DCD under and in compliance with the 
change processes in Sections VIII.A.1 and VIII.B.1 of this appendix;
    4. All exemptions from the DCD under and in compliance with the 
change processes in Sections VIII.A.4 and VIII.B.4 of this appendix, but 
only for that plant;
    5. All departures from the DCD that are approved by license 
amendment, but only for that plant;
    6. Except as provided in paragraph VIII.B.5.f of this appendix, all 
departures from Tier 2 under and in compliance with the change processes 
in paragraph VIII.B.5 of this appendix that do not require prior NRC 
approval, but only for that plant;
    7. All environmental issues concerning severe accident mitigation 
design alternatives associated with the information in the NRC's final 
environmental assessment for the System 80 + design and the technical 
support document for the System 80 + design, dated January 1995, for 
plants referencing this appendix whose site parameters are within those 
specified in the technical support document.

[[Page 127]]

    C. The Commission does not consider operational requirements for an 
applicant or licensee who references this appendix to be matters 
resolved within the meaning of 10 CFR 52.63(a)(5). The Commission 
reserves the right to require operational requirements for an applicant 
or licensee who references this appendix by rule, regulation, order, or 
license condition.
    D. Except in accordance with the change processes in Section VIII of 
this appendix, the Commission may not require an applicant or licensee 
who references this appendix to:
    1. Modify structures, systems, components, or design features as 
described in the generic DCD;
    2. Provide additional or alternative structures, systems, 
components, or design features not discussed in the generic DCD; or
    3. Provide additional or alternative design criteria, testing, 
analyses, acceptance criteria, or justification for structures, systems, 
components, or design features discussed in the generic DCD.
    E.1. Persons who wish to review proprietary information or other 
secondary references in the DCD for the System 80 + design, in order to 
request or participate in the hearing required by 10 CFR 52.85 or the 
hearing provided under 10 CFR 52.103, or to request or participate in 
any other hearing relating to this appendix in which interested persons 
have adjudicatory hearing rights, shall first request access to such 
information from Westinghouse. The request must state with 
particularity:
    a. The nature of the proprietary or other information sought;
    b. The reason why the information currently available to the public 
at the NRC Web site, http://www.nrc.gov, and/or at the NRC Public 
Document Room, is insufficient;
    c. The relevance of the requested information to the hearing 
issue(s) which the person proposes to raise; and
    d. A showing that the requesting person has the capability to 
understand and utilize the requested information.
    2. If a person claims that the information is necessary to prepare a 
request for hearing, the request must be filed no later than 15 days 
after publication in the Federal Register of the notice required either 
by 10 CFR 52.85 or 10 CFR 52.103. If Westinghouse declines to provide 
the information sought, Westinghouse shall send a written response 
within ten (10) days of receiving the request to the requesting person 
setting forth with particularity the reasons for its refusal. The person 
may then request the Commission (or presiding officer, if a proceeding 
has been established) to order disclosure. The person shall include 
copies of the original request (and any subsequent clarifying 
information provided by the requesting party to the applicant) and the 
applicant's response. The Commission and presiding officer shall base 
their decisions solely on the person's original request (including any 
clarifying information provided by the requesting person to 
Westinghouse), and Westinghouse's response. The Commission and presiding 
officer may order Westinghouse to provide access to some or all of the 
requested information, subject to an appropriate non-disclosure 
agreement.

                     VII. Duration of This Appendix

    This appendix may be referenced for a period of 15 years from June 
20, 1997, except as provided for in 10 CFR 52.55(b) and 52.57(b). This 
appendix remains valid for an applicant or licensee who references this 
appendix until the application is withdrawn or the license expires, 
including any period of extended operation under a renewed license.

               VIII. Processes for Changes and Departures

    A. Tier 1 information.
    1. Generic changes to Tier 1 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 1 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs A.3 or A.4 of this section.
    3. Departures from Tier 1 information that are required by the 
Commission through plant-specific orders are governed by the 
requirements in 10 CFR 52.63(a)(4).
    4. Exemptions from Tier 1 information are governed by the 
requirements in 10 CFR 52.63(b)(1) and 52.98(f). The Commission will 
deny a request for an exemption from Tier 1, if it finds that the design 
change will result in a significant decrease in the level of safety 
otherwise provided by the design.

                          B. Tier 2 Information

    1. Generic changes to Tier 2 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 2 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs B.3, B.4, B.5, or B.6 of this section.
    3. The Commission may not require new requirements on Tier 2 
information by plant-specific order while this appendix is in effect 
under Sec. Sec. 52.55 or 52.61, unless:
    a. A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time this 
appendix was approved, as set forth in Section V of this appendix, or to 
assure adequate protection of the public health and

[[Page 128]]

safety or the common defense and security; and
    b. Special circumstances as defined in 10 CFR 52.7 are present.
    4. An applicant or licensee who references this appendix may request 
an exemption from Tier 2 information. The Commission may grant such a 
request only if it determines that the exemption will comply with the 
requirements of 10 CFR 52.7. The Commission will deny a request for an 
exemption from Tier 2, if it finds that the design change will result in 
a significant decrease in the level of safety otherwise provided by the 
design. The grant of an exemption to an applicant must be subject to 
litigation in the same manner as other issues material to the license 
hearing. The grant of an exemption to a licensee must be subject to an 
opportunity for a hearing in the same manner as license amendments.
    5.a. An applicant or licensee who references this appendix may 
depart from Tier 2 information, without prior NRC approval, unless the 
proposed departure involves a change to or departure from Tier 1 
information, Tier 2* information, or the technical specifications, or 
requires a license amendment under paragraphs B.5.b or B.5.c of this 
section. When evaluating the proposed departure, an applicant or 
licensee shall consider all matters described in the plant-specific DCD.
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-specific 
DCD, requires a license amendment if it would--
    (1) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the plant-specific 
DCD;
    (2) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a structure, system, or component (SSC) 
important to safety previously evaluated in the plant-specific DCD;
    (3) Result in more than a minimal increase in the consequences of an 
accident previously evaluated in the plant-specific DCD;
    (4) Result in more than a minimal increase in the consequences of a 
malfunction of an SSC important to safety previously evaluated in the 
plant-specific DCD;
    (5) Create a possibility for an accident of a different type than 
any evaluated previously in the plant-specific DCD;
    (6) Create a possibility for a malfunction of an SSC important to 
safety with a different result than any evaluated previously in the 
plant-specific DCD;
    (7) Result in a design basis limit for a fission product barrier as 
described in the plant-specific DCD being exceeded or altered; or
    (8) Result in a departure from a method of evaluation described in 
the plant-specific DCD used in establishing the design bases or in the 
safety analyses.
    c. A proposed departure from Tier 2 affecting resolution of an ex-
vessel severe accident design feature identified in the plant-specific 
DCD, requires a license amendment if:
    (1) There is a substantial increase in the probability of an ex-
vessel severe accident such that a particular ex-vessel severe accident 
previously reviewed and determined to be not credible could become 
credible; or
    (2) There is a substantial increase in the consequences to the 
public of a particular ex-vessel severe accident previously reviewed.
    d. If a departure requires a license amendment under paragraph B.5.b 
or B.5.c of this section, it is governed by 10 CFR 50.90.
    e. A departure from Tier 2 information that is made under paragraph 
B.5 of this section does not require an exemption from this appendix.
    f. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an applicant or licensee who references 
this appendix has not complied with paragraph VIII.B.5 of this appendix 
when departing from Tier 2 information, may petition the NRC to admit 
into the proceeding such a contention. In addition to compliance with 
the general requirements of 10 CFR 2.309, the petition must demonstrate 
that the departure does not comply with paragraph VIII.B.5 of this 
appendix. Further, the petition must demonstrate that the change bears 
on an asserted noncompliance with an ITAAC acceptance criterion in the 
case of a 10 CFR 52.103 preoperational hearing, or that the change bears 
directly on the amendment request in the case of a hearing on a license 
amendment. Any other party may file a response. If, on the basis of the 
petition and any response, the presiding officer determines that a 
sufficient showing has been made, the presiding officer shall certify 
the matter directly to the Commission for determination of the 
admissibility of the contention. The Commission may admit such a 
contention if it determines the petition raises a genuine issue of 
material fact regarding compliance with paragraph VIII.B.5 of this 
appendix.
    6.a. An applicant who references this appendix may not depart from 
Tier 2* information, which is designated with italicized text or 
brackets and an asterisk in the generic DCD, without NRC approval. The 
departure will not be considered a resolved issue, within the meaning of 
Section VI of this appendix and 10 CFR 52.63(a)(5).
    b. A licensee who references this appendix may not depart from the 
following Tier 2* matters without prior NRC approval. A request for a 
departure will be treated as a request for a license amendment under 10 
CFR 50.90.
    (1) Maximum fuel rod average burnup.

[[Page 129]]

    (2) Control room human factors engineering.
    c. A licensee who references this appendix may not, before the plant 
first achieves full power following the finding required by 10 CFR 
52.103(g), depart from the following Tier 2* matters except in 
accordance with paragraph B.6.b of this section. After the plant first 
achieves full power, the following Tier 2* matters revert to Tier 2 
status and are thereafter subject to the departure provisions in 
paragraph B.5 of this section.
    (1) ASME Boiler & Pressure Vessel Code, Section III.
    (2) ACI 349 and ANSI/AISC-690.
    (3) Motor-operated valves.
    (4) Equipment seismic qualification methods.
    (5) Piping design acceptance criteria.
    (6) Fuel and control rod design, except burnup limit.
    (7) Instrumentation and controls setpoint methodology.
    (8) Instrumentation and controls hardware and software changes.
    (9) Instrumentation and controls environmental qualification.
    (10) Seismic design criteria for non-seismic Category I structures.
    d. Departures from Tier 2* information that are made under paragraph 
B.6 of this section do not require an exemption from this appendix.
    C. Operational requirements.
    1. Generic changes to generic technical specifications and other 
operational requirements that were completely reviewed and approved in 
the design certification rulemaking and do not require a change to a 
design feature in the generic DCD are governed by the requirements in 10 
CFR 50.109. Generic changes that do require a change to a design feature 
in the generic DCD are governed by the requirements in paragraphs A or B 
of this section.
    2. Generic changes to generic TS and other operational requirements 
are applicable to all applicants who reference this appendix, except 
those for which the change has been rendered technically irrelevant by 
action taken under paragraphs C.3 or C.4 of this section.
    3. The Commission may require plant-specific departures on generic 
technical specifications and other operational requirements that were 
completely reviewed and approved, provided a change to a design feature 
in the generic DCD is not required and special circumstances as defined 
in 10 CFR 2.335 are present. The Commission may modify or supplement 
generic technical specifications and other operational requirements that 
were not completely reviewed and approved or require additional 
technical specifications and other operational requirements on a plant-
specific basis, provided a change to a design feature in the generic DCD 
is not required.
    4. An applicant who references this appendix may request an 
exemption from the generic technical specifications or other operational 
requirements. The Commission may grant such a request only if it 
determines that the exemption will comply with the requirements of 10 
CFR 52.7. The grant of an exemption must be subject to litigation in the 
same manner as other issues material to the license hearing.
    5. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an operational requirement approved in the 
DCD or a technical specification derived from the generic technical 
specifications must be changed may petition to admit into the proceeding 
such a contention. Such a petition must comply with the general 
requirements of 10 CFR 2.309 and must demonstrate why special 
circumstances as defined in 10 CFR 2.335 are present, or for compliance 
with the Commission's regulations in effect at the time this appendix 
was approved, as set forth in Section V of this appendix. Any other 
party may file a response thereto. If, on the basis of the petition and 
any response, the presiding officer determines that a sufficient showing 
has been made, the presiding officer shall certify the matter directly 
to the Commission for determination of the admissibility of the 
contention. All other issues with respect to the plant-specific 
technical specifications or other operational requirements are subject 
to a hearing as part of the license proceeding.
    6. After issuance of a license, the generic technical specifications 
have no further effect on the plant-specific technical specifications 
and changes to the plant-specific technical specifications will be 
treated as license amendments under 10 CFR 50.90.

    IX. Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

    A.1 An applicant or licensee who references this appendix shall 
perform and demonstrate conformance with the ITAAC before fuel load. 
With respect to activities subject to an ITAAC, an applicant for a 
license may proceed at its own risk with design and procurement 
activities, and a licensee may proceed at its own risk with design, 
procurement, construction, and preoperational activities, even though 
the NRC may not have found that any particular ITAAC has been met.
    2. The licensee who references this appendix shall notify the NRC 
that the required inspections, tests, and analyses in the ITAAC have 
been successfully completed and that the corresponding acceptance 
criteria have been met.
    3. In the event that an activity is subject to an ITAAC, and the 
applicant or licensee who references this appendix has not demonstrated 
that the ITAAC has been met, the

[[Page 130]]

applicant or licensee may either take corrective actions to successfully 
complete that ITAAC, request an exemption from the ITAAC in accordance 
with Section VIII of this appendix and 10 CFR 52.97(b), or petition for 
rulemaking to amend this appendix by changing the requirements of the 
ITAAC, under 10 CFR 2.802 and 52.97(b). Such rulemaking changes to the 
ITAAC must meet the requirements of Section VIII.A.1 of this appendix.
    B.1 The NRC shall ensure that the required inspections, tests, and 
analyses in the ITAAC are performed. The NRC shall verify that the 
inspections, tests, and analyses referenced by the licensee have been 
successfully completed and, based solely thereon, find the prescribed 
acceptance criteria have been met. At appropriate intervals during 
construction, the NRC shall publish notices of the successful completion 
of ITAAC in the Federal Register.
    2. In accordance with 10 CFR 52.103(g), the Commission shall find 
that the acceptance criteria in the ITAAC for the license are met before 
fuel load.
    3. After the Commission has made the finding required by 10 CFR 
52.103(g), the ITAAC do not, by virtue of their inclusion within the 
DCD, constitute regulatory requirements either for licensees or for 
renewal of the license; except for specific ITAAC, which are the subject 
of a Sec. 52.103(a) hearing, their expiration will occur upon final 
Commission action in such proceeding. However, subsequent modifications 
must comply with the Tier 1 and Tier 2 design descriptions in the plant-
specific DCD unless the licensee has complied with the applicable 
requirements of 10 CFR 52.98 and Section VIII of this appendix.

                        X. Records and Reporting

    A. Records.
    1. The applicant for this appendix shall maintain a copy of the 
generic DCD that includes all generic changes to Tier 1, Tier 2, and the 
generic TS and other operational requirements. The applicant shall 
maintain the proprietary and safeguards information referenced in the 
generic DCD for the period that this appendix may be referenced, as 
specified in Section VII of this appendix.
    2. An applicant or licensee who references this appendix shall 
maintain the plant-specific DCD to accurately reflect both generic 
changes to the generic DCD and plant-specific departures made under 
Section VIII of this appendix throughout the period of application and 
for the term of the license (including any period of renewal).
    3. An applicant or licensee who references this appendix shall 
prepare and maintain written evaluations which provide the bases for the 
determinations required by Section VIII of this appendix. These 
evaluations must be retained throughout the period of application and 
for the term of the license (including any period of renewal).
    B. Reporting.
    1. An applicant or licensee who references this appendix shall 
submit a report to the NRC containing a brief description of any plant-
specific departures from the DCD, including a summary of the evaluation 
of each. This report must be filed in accordance with the filing 
requirements applicable to reports in 10 CFR 52.3.
    2. An applicant or licensee who references this appendix shall 
submit updates to its DCD, which reflect the generic changes to and 
plant-specific departures from the generic DCD made under Section VIII 
of this appendix. These updates must be filed under the filing 
requirements applicable to final safety analysis report updates in 10 
CFR 52.3 and 50.71(e).
    3. The reports and updates required by paragraphs X.B.1 and X.B.2 
must be submitted as follows:
    a. On the date that an application for a license referencing this 
appendix is submitted, the application must include the report and any 
updates to the generic DCD.
    b. During the interval from the date of application for a license to 
the date the Commission makes the finding required by 10 CFR 52.103(g), 
the report must be submitted semi-annually. Updates to the plant-
specific DCD must be submitted annually and may be submitted along with 
amendments to the application.
    c. After the Commission makes the finding required by 10 CFR 
52.103(g), the reports and updates to the plant-specific DCD must be 
submitted, along with updates to the site-specific portion of the final 
safety analysis report for the facility, at the intervals required by 10 
CFR 50.59(d)(2) and 50.71(e)(4), respectively, or at shorter intervals 
as specified in the license.

[72 FR 49517, Aug. 28, 2007, as amended at 76 FR 72085, Nov. 22, 2011]



  Sec. Appendix C to Part 52--Design Certification Rule for the AP600 
                                 Design

                             I. Introduction

    Appendix C constitutes the standard design certification for the 
AP600 \1\ design, in accordance with 10 CFR part 52, subpart B. The 
applicant for certification of the AP600 design is Westinghouse Electric 
Company LLC.
---------------------------------------------------------------------------

    \1\ AP600 is a trademark of Westinghouse Electric Company LLC.
---------------------------------------------------------------------------

                             II. Definitions

    A. Generic design control document (generic DCD) means the document 
containing the Tier 1 and Tier 2 information and generic

[[Page 131]]

technical specifications that is incorporated by reference into this 
appendix.
    B. Generic technical specifications means the information, required 
by 10 CFR 50.36 and 50.36a, for the portion of the plant that is within 
the scope of this appendix.
    C. Plant-specific DCD means the document, maintained by an applicant 
or licensee who references this appendix, consisting of the information 
in the generic DCD, as modified and supplemented by the plant-specific 
departures and exemptions made under Section VIII of this appendix.
    D. Tier 1 means the portion of the design-related information 
contained in the generic DCD that is approved and certified by this 
appendix (hereinafter Tier 1 information). The design descriptions, 
interface requirements, and site parameters are derived from Tier 2 
information. Tier 1 information includes:
    1. Definitions and general provisions;
    2. Design descriptions;
    3. Inspections, tests, analyses, and acceptance criteria (ITAAC);
    4. Significant site parameters; and
    5. Significant interface requirements.
    E. Tier 2 means the portion of the design-related information 
contained in the generic DCD that is approved but not certified by this 
appendix (Tier 2 information). Compliance with Tier 2 is required, but 
generic changes to and plant-specific departures from Tier 2 are 
governed by Section VIII of this appendix. Compliance with Tier 2 
provides a sufficient, but not the only acceptable, method for complying 
with Tier 1. Compliance methods differing from Tier 2 must satisfy the 
change process in Section VIII of this appendix. Regardless of these 
differences, an applicant or licensee must meet the requirement in 
Section III.B of this appendix to reference Tier 2 when referencing Tier 
1. Tier 2 information includes:
    1. Information required by Sec. Sec. 52.47(a) and 52.47(c), with 
the exception of generic technical specifications and conceptual design 
information;
    2. Supporting information on the inspections, tests, and analyses 
that will be performed to demonstrate that the acceptance criteria in 
the ITAAC have been met; and
    3. Combined license (COL) action items (COL license information), 
which identify certain matters that must be addressed in the site-
specific portion of the final safety analysis report (FSAR) by an 
applicant who references this appendix. These items constitute 
information requirements but are not the only acceptable set of 
information in the FSAR. An applicant may depart from or omit these 
items, provided that the departure or omission is identified and 
justified in the FSAR. After issuance of a construction permit or COL, 
these items are not requirements for the licensee unless such items are 
restated in the FSAR.
    4. The investment protection short-term availability controls in 
Section 16.3 of the DCD.
    F. Tier 2* means the portion of the Tier 2 information, designated 
as such in the generic DCD, which is subject to the change process in 
Section VIII.B.6 of this appendix. This designation expires for some 
Tier 2* information under Section VIII.B.6.
    G. Departure from a method of evaluation described in the plant-
specific DCD used in establishing the design bases or in the safety 
analyses means:
    (1) Changing any of the elements of the method described in the 
plant-specific DCD unless the results of the analysis are conservative 
or essentially the same; or
    (2) Changing from a method described in the plant-specific DCD to 
another method unless that method has been approved by NRC for the 
intended application.
    H. All other terms in this appendix have the meaning set out in 10 
CFR 50.2 or 52.1, or Section 11 of the Atomic Energy Act of 1954, as 
amended, as applicable.

                         III. Scope and Contents

    A. Tier 1, Tier 2 (including the investment protection short-term 
availability controls in Section 16.3), and the generic technical 
specifications in the AP600 DCD (12/99 revision) are approved for 
incorporation by reference by the Director of the Office of the Federal 
Register on January 24, 2000, in accordance with 5 U.S.C. 552(a) and 1 
CFR part 51. Copies of the generic DCD may be obtained from Ronald P. 
Vijuk, Manager, Passive Plant Engineering, Westinghouse Electric 
Company, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355. A copy of 
the generic DCD is available for examination and copying at the NRC 
Public Document Room located at One White Flint North, 11555 Rockville 
Pike (first floor), Rockville, Maryland 20852. Copies are also available 
for examination at the NRC Library located at Two White Flint North, 
11545 Rockville Pike, Rockville, Maryland 20852; and the Office of the 
Federal Register, 800 North Capitol Street, NW., Suite 700, Washington, 
DC.
    B. An applicant or licensee referencing this appendix, in accordance 
with Section IV of this appendix, shall incorporate by reference and 
comply with the requirements of this appendix, including Tier 1, Tier 2 
(including the investment protection short-term availability controls in 
Section 16.3), and the generic technical specifications except as 
otherwise provided in this appendix. Conceptual design information in 
the generic DCD and the evaluation of severe accident mitigation design 
alternatives in Appendix 1B of the generic DCD are not part of this 
appendix.
    C. If there is a conflict between Tier 1 and Tier 2 of the DCD, then 
Tier 1 controls.
    D. If there is a conflict between the generic DCD and either the 
application for design

[[Page 132]]

certification of the AP600 design or NUREG-1512, ``Final Safety 
Evaluation Report Related to Certification of the AP600 Standard 
Design,'' (FSER), then the generic DCD controls.
    E. Design activities for structures, systems, and components that 
are wholly outside the scope of this appendix may be performed using 
site characteristics, provided the design activities do not affect the 
DCD or conflict with the interface requirements.

              IV. Additional Requirements and Restrictions

    A. An applicant for a combined license that wishes to reference this 
appendix shall, in addition to complying with the requirements of 10 CFR 
52.77, 52.79, and 52.80, comply with the following requirements:
    1. Incorporate by reference, as part of its application, this 
appendix;
    2. Include, as part of its application:
    a. A plant-specific DCD containing the same type of information and 
utilizing the same organization and numbering as the generic DCD for the 
AP600 design, as modified and supplemented by the applicant's exemptions 
and departures;
    b. The reports on departures from and updates to the plant-specific 
DCD required by paragraph X.B of this appendix;
    c. Plant-specific technical specifications, consisting of the 
generic and site-specific technical specifications, that are required by 
10 CFR 50.36 and 50.36a;
    d. Information demonstrating compliance with the site parameters and 
interface requirements;
    e. Information that addresses the COL action items; and
    f. Information required by 10 CFR 52.47 that is not within the scope 
of this appendix.
    3. Include, in the plant-specific DCD, the proprietary information 
and safeguards information referenced in the AP600 DCD.
    B. The Commission reserves the right to determine in what manner 
this appendix may be referenced by an applicant for a construction 
permit or operating license under 10 CFR part 50.

                        V. Applicable Regulations

    A. Except as indicated in paragraph B of this section, the 
regulations that apply to the AP600 design are in 10 CFR parts 20, 50, 
73, and 100, codified as of December 16, 1999, that are applicable and 
technically relevant, as described in the FSER (NUREG-1512) and the 
supplementary information for this section.
    B. The AP600 design is exempt from portions of the following 
regulations:
    1. Paragraph (a)(1) of 10 CFR 50.34--whole body dose criterion;
    2. Paragraph (f)(2)(iv) of 10 CFR 50.34--Plant Safety Parameter 
Display Console;
    3. Paragraphs (f)(2)(vii), (viii), (xxvi), and (xxviii) of 10 CFR 
50.34--Accident Source Term in TID 14844;
    4. Paragraph (a)(2) of 10 CFR 50.55a--ASME Boiler and Pressure 
Vessel Code;
    5. Paragraph (c)(1) of 10 CFR 50.62--Auxiliary (or emergency) 
feedwater system;
    6. Appendix A to 10 CFR part 50, GDC 17--Offsite Power Sources; and
    7. Appendix A to 10 CFR part 50, GDC 19--whole body dose criterion.

                          VI. Issue Resolution

    A. The Commission has determined that the structures, systems, 
components, and design features of the AP600 design comply with the 
provisions of the Atomic Energy Act of 1954, as amended, and the 
applicable regulations identified in Section V of this appendix; and 
therefore, provide adequate protection to the health and safety of the 
public. A conclusion that a matter is resolved includes the finding that 
additional or alternative structures, systems, components, design 
features, design criteria, testing, analyses, acceptance criteria, or 
justifications are not necessary for the AP600 design.
    B. The Commission considers the following matters resolved within 
the meaning of 10 CFR 52.63(a)(5) in subsequent proceedings for issuance 
of a combined license, amendment of a combined license, or renewal of a 
combined license, proceedings held under 10 CFR 52.103, and enforcement 
proceedings involving plants referencing this appendix:
    1. All nuclear safety issues, except for the generic technical 
specifications and other operational requirements, associated with the 
information in the FSER and Supplement No. 1, Tier 1, Tier 2 (including 
referenced information which the context indicates is intended as 
requirements and the investment protection short-term availability 
controls in Section 16.3), and the rulemaking record for certification 
of the AP600 design;
    2. All nuclear safety and safeguards issues associated with the 
information in proprietary and safeguards documents, referenced and in 
context, are intended as requirements in the generic DCD for the AP600 
design;
    3. All generic changes to the DCD under and in compliance with the 
change processes in Sections VIII.A.1 and VIII.B.1 of this appendix;
    4. All exemptions from the DCD under and in compliance with the 
change processes in Sections VIII.A.4 and VIII.B.4 of this appendix, but 
only for that plant;
    5. All departures from the DCD that are approved by license 
amendment, but only for that plant;
    6. Except as provided in paragraph VIII.B.5.f of this appendix, all 
departures from Tier 2 under and in compliance with the change processes 
in paragraph VIII.B.5 of this appendix that do not require prior NRC 
approval, but only for that plant;

[[Page 133]]

    7. All environmental issues concerning severe accident mitigation 
design alternatives associated with the information in the NRC's 
environmental assessment for the AP600 design and appendix 1B of the 
generic DCD, for plants referencing this appendix whose site parameters 
are within those specified in the severe accident mitigation design 
alternatives evaluation.
    C. The Commission does not consider operational requirements for an 
applicant or licensee who references this appendix to be matters 
resolved within the meaning of 10 CFR 52.63(a)(5). The Commission 
reserves the right to require operational requirements for an applicant 
or licensee who references this appendix by rule, regulation, order, or 
license condition.
    D. Except in accordance with the change processes in Section VIII of 
this appendix, the Commission may not require an applicant or licensee 
who references this appendix to:
    1. Modify structures, systems, components, or design features as 
described in the generic DCD;
    2. Provide additional or alternative structures, systems, 
components, or design features not discussed in the generic DCD; or
    3. Provide additional or alternative design criteria, testing, 
analyses, acceptance criteria, or justification for structures, systems, 
components, or design features discussed in the generic DCD.
    E.1. Persons who wish to review proprietary and safeguards 
information or other secondary references in the AP600 DCD, in order to 
request or participate in the hearing required by 10 CFR 52.85 or the 
hearing provided under 10 CFR 52.103, or to request or participate in 
any other hearing relating to this appendix in which interested persons 
have adjudicatory hearing rights, shall first request access to such 
information from Westinghouse. The request must state with 
particularity:
    a. The nature of the proprietary or other information sought;
    b. The reason why the information currently available to the public 
at the NRC Web site, http://www.nrc.gov, and/or at the NRC Public 
Document Room, is insufficient;
    c. The relevance of the requested information to the hearing 
issue(s) which the person proposes to raise; and
    d. A showing that the requesting person has the capability to 
understand and utilize the requested information.
    2. If a person claims that the information is necessary to prepare a 
request for hearing, the request must be filed no later than 15 days 
after publication in the Federal Register of the notice required either 
by 10 CFR 52.85 or 10 CFR 52.103. If Westinghouse declines to provide 
the information sought, Westinghouse shall send a written response 
within 10 days of receiving the request to the requesting person setting 
forth with particularity the reasons for its refusal. The person may 
then request the Commission (or presiding officer, if a proceeding has 
been established) to order disclosure. The person shall include copies 
of the original request (and any subsequent clarifying information 
provided by the requesting party to the applicant) and the applicant's 
response. The Commission and presiding officer shall base their 
decisions solely on the person's original request (including any 
clarifying information provided by the requesting person to 
Westinghouse), and Westinghouse's response. The Commission and presiding 
officer may order Westinghouse to provide access to some or all of the 
requested information, subject to an appropriate non-disclosure 
agreement.

                     VII. Duration of This Appendix

    This appendix may be referenced for a period of 15 years from 
January 24, 2000, except as provided for in 10 CFR 52.55(b) and 
52.57(b). This appendix remains valid for an applicant or licensee who 
references this appendix until the application is withdrawn or the 
license expires, including any period of extended operation under a 
renewed license.

               VIII. Processes for Changes and Departures

    A. Tier 1 information.
    1. Generic changes to Tier 1 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 1 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs A.3 or A.4 of this section.
    3. Departures from Tier 1 information that are required by the 
Commission through plant-specific orders are governed by the 
requirements in 10 CFR 52.63(a)(4).
    4. Exemptions from Tier 1 information are governed by the 
requirements in 10 CFR 52.63(b)(1) and 52.98(f). The Commission will 
deny a request for an exemption from Tier 1, if it finds that the design 
change will result in a significant decrease in the level of safety 
otherwise provided by the design.
    B. Tier 2 information.
    1. Generic changes to Tier 2 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 2 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs B.3, B.4, B.5, or B.6 of this section.
    3. The Commission may not require new requirements on Tier 2 
information by plant-

[[Page 134]]

specific order while this appendix is in effect under Sec. Sec. 52.55 
or 52.61, unless:
    a. A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time this 
appendix was approved, as set forth in Section V of this appendix, or to 
assure adequate protection of the public health and safety or the common 
defense and security; and
    b. Special circumstances as defined in 10 CFR 52.7 are present.
    4. An applicant or licensee who references this appendix may request 
an exemption from Tier 2 information. The Commission may grant such a 
request only if it determines that the exemption will comply with the 
requirements of 10 CFR 52.7. The Commission will deny a request for an 
exemption from Tier 2, if it finds that the design change will result in 
a significant decrease in the level of safety otherwise provided by the 
design. The grant of an exemption to an applicant must be subject to 
litigation in the same manner as other issues material to the license 
hearing. The grant of an exemption to a licensee must be subject to an 
opportunity for a hearing in the same manner as license amendments.
    5.a. An applicant or licensee who references this appendix may 
depart from Tier 2 information, without prior NRC approval, unless the 
proposed departure involves a change to or departure from Tier 1 
information, Tier 2* information, or the technical specifications, or 
requires a license amendment under paragraphs B.5.b or B.5.c of this 
section. When evaluating the proposed departure, an applicant or 
licensee shall consider all matters described in the plant-specific DCD.
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-specific 
DCD, requires a license amendment if it would:
    (1) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the plant-specific 
DCD;
    (2) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a structure, system, or component (SSC) 
important to safety previously evaluated in the plant-specific DCD;
    (3) Result in more than a minimal increase in the consequences of an 
accident previously evaluated in the plant-specific DCD;
    (4) Result in more than a minimal increase in the consequences of a 
malfunction of an SSC important to safety previously evaluated in the 
plant-specific DCD;
    (5) Create a possibility for an accident of a different type than 
any evaluated previously in the plant-specific DCD;
    (6) Create a possibility for a malfunction of an SSC important to 
safety with a different result than any evaluated previously in the 
plant-specific DCD;
    (7) Result in a design basis limit for a fission product barrier as 
described in the plant-specific DCD being exceeded or altered; or
    (8) Result in a departure from a method of evaluation described in 
the plant-specific DCD used in establishing the design bases or in the 
safety analyses.
    c. A proposed departure from Tier 2 affecting resolution of an ex-
vessel severe accident design feature identified in the plant-specific 
DCD, requires a license amendment if:
    (1) There is a substantial increase in the probability of an ex-
vessel severe accident such that a particular ex-vessel severe accident 
previously reviewed and determined to be not credible could become 
credible; or
    (2) There is a substantial increase in the consequences to the 
public of a particular ex-vessel severe accident previously reviewed.
    d. If a departure requires a license amendment under paragraphs 
B.5.b or B.5.c of this section, it is governed by 10 CFR 50.90.
    e. A departure from Tier 2 information that is made under paragraph 
B.5 of this section does not require an exemption from this appendix.
    f. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an applicant or licensee who references 
this appendix has not complied with paragraph VIII.B.5 of this appendix 
when departing from Tier 2 information, may petition the NRC to admit 
into the proceeding such a contention. In addition to compliance with 
the general requirements of 10 CFR 2.309, the petition must demonstrate 
that the departure does not comply with paragraph VIII.B.5 of this 
appendix. Further, the petition must demonstrate that the change bears 
on an asserted noncompliance with an ITAAC acceptance criterion in the 
case of a 10 CFR 52.103 preoperational hearing, or that the change bears 
directly on the amendment request in the case of a hearing on a license 
amendment. Any other party may file a response. If, on the basis of the 
petition and any response, the presiding officer determines that a 
sufficient showing has been made, the presiding officer shall certify 
the matter directly to the Commission for determination of the 
admissibility of the contention. The Commission may admit such a 
contention if it determines the petition raises a genuine issue of 
material fact regarding compliance with paragraph VIII.B.5 of this 
appendix.
    6a. An applicant who references this appendix may not depart from 
Tier 2* information, which is designated with italicized text or 
brackets and an asterisk in the generic DCD, without NRC approval. The 
departure will not be considered a resolved issue, within the

[[Page 135]]

meaning of Section VI of this appendix and 10 CFR 52.63(a)(5).
    b. A licensee who references this appendix may not depart from the 
following Tier 2* matters without prior NRC approval. A request for a 
departure will be treated as a request for a license amendment under 10 
CFR 50.90.
    (1) Maximum fuel rod average burn-up.
    (2) Fuel principal design requirements.
    (3) Fuel criteria evaluation process.
    (4) Fire areas.
    (5) Human factors engineering.
    c. A licensee who references this appendix may not, before the plant 
first achieves full power following the finding required by 10 CFR 
52.103(g), depart from the following Tier 2* matters except in 
accordance with paragraph B.6.b of this section. After the plant first 
achieves full power, the following Tier 2* matters revert to Tier 2 
status and are thereafter subject to the departure provisions in 
paragraph B.5 of this section.
    (1) Nuclear Island structural dimensions.
    (2) ASME Boiler and Pressure Vessel Code, Section III, and Code 
Case--284.
    (3) Design Summary of Critical Sections.
    (4) ACI 318, ACI 349, and ANSI/AISC--690.
    (5) Definition of critical locations and thicknesses.
    (6) Seismic qualification methods and standards.
    (7) Nuclear design of fuel and reactivity control system, except 
burn-up limit.
    (8) Motor-operated and power-operated valves.
    (9) Instrumentation and control system design processes, methods, 
and standards.
    (10) PRHR natural circulation test (first plant only).
    (11) ADS and CMT verification tests (first three plants only).
    d. Departures from Tier 2* information that are made under paragraph 
B.6 of this section do not require an exemption from this appendix.
    C. Operational requirements.
    1. Generic changes to generic technical specifications and other 
operational requirements that were completely reviewed and approved in 
the design certification rulemaking and do not require a change to a 
design feature in the generic DCD are governed by the requirements in 10 
CFR 50.109. Generic changes that do require a change to a design feature 
in the generic DCD are governed by the requirements in paragraphs A or B 
of this section.
    2. Generic changes to generic TS and other operational requirements 
are applicable to all applicants who reference this appendix, except 
those for which the change has been rendered technically irrelevant by 
action taken under paragraphs C.3 or C.4 of this section.
    3. The Commission may require plant-specific departures on generic 
technical specifications and other operational requirements that were 
completely reviewed and approved, provided a change to a design feature 
in the generic DCD is not required and special circumstances as defined 
in 10 CFR 2.335 are present. The Commission may modify or supplement 
generic technical specifications and other operational requirements that 
were not completely reviewed and approved or require additional 
technical specifications and other operational requirements on a plant-
specific basis, provided a change to a design feature in the generic DCD 
is not required.
    4. An applicant who references this appendix may request an 
exemption from the generic technical specifications or other operational 
requirements. The Commission may grant such a request only if it 
determines that the exemption will comply with the requirements of 10 
CFR 52.7. The grant of an exemption must be subject to litigation in the 
same manner as other issues material to the license hearing.
    5. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an operational requirement approved in the 
DCD or a technical specification derived from the generic technical 
specifications must be changed may petition to admit into the proceeding 
such a contention. Such petition must comply with the general 
requirements of 10 CFR 2.309 and must demonstrate why special 
circumstances as defined in 10 CFR 2.335 are present, or for compliance 
with the Commission's regulations in effect at the time this appendix 
was approved, as set forth in Section V of this appendix. Any other 
party may file a response thereto. If, on the basis of the petition and 
any response, the presiding officer determines that a sufficient showing 
has been made, the presiding officer shall certify the matter directly 
to the Commission for determination of the admissibility of the 
contention. All other issues with respect to the plant-specific 
technical specifications or other operational requirements are subject 
to a hearing as part of the license proceeding.
    6. After issuance of a license, the generic technical specifications 
have no further effect on the plant-specific technical specifications 
and changes to the plant-specific technical specifications will be 
treated as license amendments under 10 CFR 50.90.

    IX. Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

    A.1 An applicant or licensee who references this appendix shall 
perform and demonstrate conformance with the ITAAC before fuel load. 
With respect to activities subject to an ITAAC, an applicant for a 
license may proceed at its own risk with design and procurement 
activities, and a licensee may proceed at its own risk with design, 
procurement,

[[Page 136]]

construction, and preoperational activities, even though the NRC may not 
have found that any particular ITAAC has been met.
    2. The licensee who references this appendix shall notify the NRC 
that the required inspections, tests, and analyses in the ITAAC have 
been successfully completed and that the corresponding acceptance 
criteria have been met.
    3. In the event that an activity is subject to an ITAAC, and the 
applicant or licensee who references this appendix has not demonstrated 
that the ITAAC has been met, the applicant or licensee may either take 
corrective actions to successfully complete that ITAAC, request an 
exemption from the ITAAC in accordance with Section VIII of this 
appendix and 10 CFR 52.97(b), or petition for rulemaking to amend this 
appendix by changing the requirements of the ITAAC, under 10 CFR 2.802 
and 52.97(b). Such rulemaking changes to the ITAAC must meet the 
requirements of paragraph VIII.A.1 of this appendix.
    B.1. The NRC shall ensure that the required inspections, tests, and 
analyses in the ITAAC are performed. The NRC shall verify that the 
inspections, tests, and analyses referenced by the licensee have been 
successfully completed and, based solely thereon, find the prescribed 
acceptance criteria have been met. At appropriate intervals during 
construction, the NRC shall publish notices of the successful completion 
of ITAAC in the Federal Register.
    2. In accordance with 10 CFR 52.103(g), the Commission shall find 
that the acceptance criteria in the ITAAC for the license are met before 
fuel load.
    3. After the Commission has made the finding required by 10 CFR 
52.103(g), the ITAAC do not, by virtue of their inclusion within the 
DCD, constitute regulatory requirements either for licensees or for 
renewal of the license; except for specific ITAAC, which are the subject 
of a Sec. 52.103(a) hearing, their expiration will occur upon final 
Commission action in such proceeding. However, subsequent modifications 
must comply with the Tier 1 and Tier 2 design descriptions in the plant-
specific DCD unless the licensee has complied with the applicable 
requirements of 10 CFR 52.98 and Section VIII of this appendix.

                        X. Records and Reporting

    A. Records.
    1. The applicant for this appendix shall maintain a copy of the 
generic DCD that includes all generic changes to Tier 1, Tier 2, and the 
generic TS and other operational requirements. The applicant shall 
maintain the proprietary and safeguards information referenced in the 
generic DCD for the period that this appendix may be referenced, as 
specified in Section VII of this appendix.
    2. An applicant or licensee who references this appendix shall 
maintain the plant-specific DCD to accurately reflect both generic 
changes to the generic DCD and plant-specific departures made under 
Section VIII of this appendix throughout the period of application and 
for the term of the license (including any period of renewal).
    3. An applicant or licensee who references this appendix shall 
prepare and maintain written evaluations which provide the bases for the 
determinations required by Section VIII of this appendix. These 
evaluations must be retained throughout the period of application and 
for the term of the license (including any period of renewal).
    B. Reporting.
    1. An applicant or licensee who references this appendix shall 
submit a report to the NRC containing a brief description of any plant-
specific departures from the DCD, including a summary of the evaluation 
of each. This report must be filed in accordance with the filing 
requirements applicable to reports in 10 CFR 52.3.
    2. An applicant or licensee who references this appendix shall 
submit updates to its DCD, which reflect the generic changes to and 
plant-specific departures from the generic DCD made under Section VIII 
of this appendix. These updates must be filed under the filing 
requirements applicable to final safety analysis report updates in 10 
CFR 52.3 and 50.71(e).
    3. The reports and updates required by paragraphs X.B.1 and X.B.2 
must be submitted as follows:
    a. On the date that an application for a license referencing this 
appendix is submitted, the application must include the report and any 
updates to the generic DCD.
    b. During the interval from the date of application for a license to 
the date the Commission makes the finding required by 10 CFR 52.103(g), 
the report must be submitted semi-annually. Updates to the plant-
specific DCD must be submitted annually and may be submitted along with 
amendments to the application.
    c. After the Commission makes the finding required by 10 CFR 
52.103(g), the reports and updates to the plant-specific DCD must be 
submitted, along with updates to the site-specific portion of the final 
safety analysis report for the facility, at the intervals required by 10 
CFR 50.59(d)(2) and 50.71(e), respectively, or at shorter intervals as 
specified in the license.

[72 FR 49517, Aug. 28, 2007, as amended at 76 FR 72085, Nov. 22, 2011]

[[Page 137]]



  Sec. Appendix D to Part 52--Design Certification Rule for the AP1000 
                                 Design

                             I. Introduction

    Appendix D constitutes the standard design certification for the 
AP1000 \1\ design, in accordance with 10 CFR part 52, subpart B. The 
applicant for certification of the AP1000 design is Westinghouse 
Electric Company LLC.
---------------------------------------------------------------------------

    \1\ AP1000 is a trademark of Westinghouse Electric Company LLC.
---------------------------------------------------------------------------

                             II. Definitions

    A. Generic design control document (generic DCD) means the document 
containing the Tier 1 and Tier 2 information and generic technical 
specifications that is incorporated by reference into this appendix.
    B. Generic technical specifications means the information required 
by 10 CFR 50.36 and 50.36a for the portion of the plant that is within 
the scope of this appendix.
    C. Plant-specific DCD means the document maintained by an applicant 
or licensee who references this appendix consisting of the information 
in the generic DCD as modified and supplemented by the plant-specific 
departures and exemptions made under Section VIII of this appendix.
    D. Tier 1 means the portion of the design-related information 
contained in the generic DCD that is approved and certified by this 
appendix (Tier 1 information). The design descriptions, interface 
requirements, and site parameters are derived from Tier 2 information. 
Tier 1 information includes:
    1. Definitions and general provisions;
    2. Design descriptions;
    3. Inspections, tests, analyses, and acceptance criteria (ITAAC);
    4. Significant site parameters; and
    5. Significant interface requirements.
    E. Tier 2 means the portion of the design-related information 
contained in the generic DCD that is approved but not certified by this 
appendix (Tier 2 information). Compliance with Tier 2 is required, but 
generic changes to and plant-specific departures from Tier 2 are 
governed by Section VIII of this appendix. Compliance with Tier 2 
provides a sufficient, but not the only acceptable, method for complying 
with Tier 1. Compliance methods differing from Tier 2 must satisfy the 
change process in Section VIII of this appendix. Regardless of these 
differences, an applicant or licensee must meet the requirement in 
Section III.B of this appendix to reference Tier 2 when referencing Tier 
1. Tier 2 information includes:
    1. Information required by Sec. Sec. 52.47(a) and 52.47(c), with 
the exception of generic technical specifications and conceptual design 
information;
    2. Supporting information on the inspections, tests, and analyses 
that will be performed to demonstrate that the acceptance criteria in 
the ITAAC have been met; and
    3. Combined license (COL) action items (COL license information), 
which identify certain matters that must be addressed in the site-
specific portion of the final safety analysis report (FSAR) by an 
applicant who references this appendix. These items constitute 
information requirements but are not the only acceptable set of 
information in the FSAR. An applicant may depart from or omit these 
items, provided that the departure or omission is identified and 
justified in the FSAR. After issuance of a construction permit or COL, 
these items are not requirements for the licensee unless such items are 
restated in the FSAR.
    4. The investment protection short-term availability controls in 
Section 16.3 of the DCD.
    F. Tier 2* means the portion of the Tier 2 information, designated 
as such in the generic DCD, which is subject to the change process in 
Section VIII.B.6 of this appendix. This designation expires for some 
Tier 2* information under paragraph VIII.B.6.
    G. Departure from a method of evaluation described in the plant-
specific DCD used in establishing the design bases or in the safety 
analyses means:
    1. Changing any of the elements of the method described in the 
plant-specific DCD unless the results of the analysis are conservative 
or essentially the same; or
    2. Changing from a method described in the plant-specific DCD to 
another method unless that method has been approved by the NRC for the 
intended application.
    H. All other terms in this appendix have the meaning set out in 10 
CFR 50.2, or 52.1, or Section 11 of the Atomic Energy Act of 1954, as 
amended, as applicable.

                         III. Scope and Contents

    A. Tier 1, Tier 2 (including the investment protection short-term 
availability controls in Section 16.3), and the generic TSs in the 
AP1000 Design Control Document, Revision 19, (Public Version) (AP1000 
DCD), APP-GW-GL-702, dated June 13, 2011, are approved for incorporation 
by reference by the Director of the Office of the Federal Register under 
5 U.S.C. 552(a) and 1 CFR part 51. Copies of the generic DCD may be 
obtained from Stanley E. Ritterbusch, Manager, AP1000 Design 
Certification, Westinghouse Electric Company, 1000 Westinghouse Drive, 
Cranberry Township, Pennsylvania 16066, telephone (412) 374-3037. A copy 
of the generic DCD is also available for examination and copying at the 
NRC's PDR, Room O-1F21, One White Flint North, 11555 Rockville Pike, 
Rockville, Maryland 20852. Copies are available for examination at the 
NRC Library, Two White Flint North, 11545 Rockville Pike, Rockville,

[[Page 138]]

Maryland 20852, telephone (301) 415-5610, email 
[email protected]. The DCD can also be viewed online in the NRC 
Library at http://www.nrc.gov/reading-rm/adams.html by searching under 
ADAMS Accession No. ML11171A500. All approved material is available for 
inspection at the National Archives and Records Administration (NARA). 
For information on the availability of this material at NARA, call (202) 
741-6030 or go to http://www.archives.gov/federal-register/cfr/ibr-
locations.html.
    B. An applicant or licensee referencing this appendix, in accordance 
with Section IV of this appendix, shall incorporate by reference and 
comply with the requirements of this appendix, including Tier 1, Tier 2 
(including the investment protection short-term availability controls in 
Section 16.3 of the DCD), and the generic TS except as otherwise 
provided in this appendix. Conceptual design information in the generic 
DCD and the evaluation of severe accident mitigation design alternatives 
in appendix 1B of the generic DCD are not part of this appendix.
    C. If there is a conflict between Tier 1 and Tier 2 of the DCD, then 
Tier 1 controls.
    D.1. If there is a conflict between the generic DCD and either the 
application for the initial design certification of the AP1000 design or 
NUREG-1793, ``Final Safety Evaluation Report Related to Certification of 
the Westinghouse Standard Design,'' and Supplement No. 1, then the 
generic DCD controls.
    2. If there is a conflict between the generic DCD and either the 
application for Amendment 1 to the design certification of the AP1000 
design or NUREG-1793, ``Final Safety Evaluation Report Related to 
Certification of the Westinghouse Standard Design,'' Supplement No. 2, 
then the generic DCD controls.
    E. Design activities for structures, systems, and components that 
are wholly outside the scope of this appendix may be performed using 
site characteristics, provided the design activities do not affect the 
DCD or conflict with the interface requirements.

              IV. Additional Requirements and Restrictions

    A. An applicant for a combined license that wishes to reference this 
appendix shall, in addition to complying with the requirements of 10 CFR 
52.77, 52.79, and 52.80, comply with the following requirements:
    1. Incorporate by reference, as part of its application, this 
appendix.
    2. Include, as part of its application:
    a. A plant-specific DCD containing the same type of information and 
using the same organization and numbering as the generic DCD for the 
AP1000 design, as modified and supplemented by the applicant's 
exemptions and departures;
    b. The reports on departures from and updates to the plant-specific 
DCD required by paragraph X.B of this appendix;
    c. Plant-specific TS, consisting of the generic and site-specific TS 
that are required by 10 CFR 50.36 and 50.36a;
    d. Information demonstrating compliance with the site parameters and 
interface requirements;
    e. Information that addresses the COL action items; and
    f. Information required by 10 CFR 52.47(a) that is not within the 
scope of this appendix.
    3. Include, in the plant-specific DCD, the sensitive unclassified 
non-safeguards information (including proprietary information) and 
safeguards information referenced in the AP1000 DCD.
    4. Include, as part of its application, a demonstration that an 
entity other than Westinghouse is qualified to supply the AP1000 design, 
unless Westinghouse supplies the design for the applicant's use.
    B. The Commission reserves the right to determine in what manner 
this appendix may be referenced by an applicant for a construction 
permit or operating license under 10 CFR part 50.

                        V. Applicable Regulations

    A.1. Except as indicated in paragraph B of this section, the 
regulations that apply to the AP1000 design are in 10 CFR parts 20, 50, 
73, and 100, codified as of January 23, 2006, that are applicable and 
technically relevant, as described in the FSER (NUREG-1793) and 
Supplement No. 1.
    2. The regulations that apply to those portions of the AP1000 design 
approved by Amendment 1 are in 10 CFR parts 20, 50, 73, and 100, 
codified as of December 30, 2011, that are applicable and technically 
relevant, as described in the Supplement No. 2 of the FSER (NUREG-1793).
    B. The AP1000 design is exempt from portions of the following 
regulations:
    1. Paragraph (f)(2)(iv) of 10 CFR 50.34--Plant Safety Parameter 
Display Console;
    2. Paragraph (c)(1) of 10 CFR 50.62--Auxiliary (or emergency) 
feedwater system; and
    3. Appendix A to 10 CFR part 50, GDC 17--Second offsite power supply 
circuit.

                          VI. Issue Resolution

    A. The Commission has determined that the structures, systems, 
components, and design features of the AP1000 design comply with the 
provisions of the Atomic Energy Act of 1954, as amended, and the 
applicable regulations identified in Section V of this appendix; and 
therefore, provide adequate protection to the health and safety of the 
public. A conclusion that a matter is resolved includes the finding that 
additional or alternative structures, systems, components, design 
features, design criteria, testing,

[[Page 139]]

analyses, acceptance criteria, or justifications are not necessary for 
the AP1000 design.
    B. The Commission considers the following matters resolved within 
the meaning of 10 CFR 52.63(a)(5) in subsequent proceedings for issuance 
of a COL, amendment of a COL, or renewal of a COL, proceedings held 
under 10 CFR 52.103, and enforcement proceedings involving plants 
referencing this appendix:
    1. All nuclear safety issues, except for the generic TS and other 
operational requirements, associated with the information in the FSER 
and Supplement Nos. 1 and 2, Tier 1, Tier 2 (including referenced 
information, which the context indicates is intended as requirements, 
and the investment protection short-term availability controls in 
Section 16.3 of the DCD), and the rulemaking records for initial 
certification and Amendment 1 of the AP1000 design;
    2. All nuclear safety and safeguards issues associated with the 
referenced sensitive unclassified non-safeguards information (including 
proprietary information) and safeguards information which, in context, 
are intended as requirements in the generic DCD for the AP1000 design;
    3. All generic changes to the DCD under and in compliance with the 
change processes in Sections VIII.A.1 and VIII.B.1 of this appendix;
    4. All exemptions from the DCD under and in compliance with the 
change processes in Sections VIII.A.4 and VIII.B.4 of this appendix, but 
only for that plant;
    5. All departures from the DCD that are approved by license 
amendment, but only for that plant;
    6. Except as provided in paragraph VIII.B.5.f of this appendix, all 
departures from Tier 2 under and in compliance with the change processes 
in paragraph VIII.B.5 of this appendix that do not require prior NRC 
approval, but only for that plant;
    7. All environmental issues concerning severe accident mitigation 
design alternatives associated with the information in the NRC's EA for 
the AP1000 design, Appendix 1B of Revision 15 of the generic DCD, the 
NRC's final EA for Amendment 1 to the AP1000 design, and Appendix 1B of 
Revision 19 of the generic DCD, for plants referencing this appendix 
whose site parameters are within those specified in the severe accident 
mitigation design alternatives evaluation.
    C. The Commission does not consider operational requirements for an 
applicant or licensee who references this appendix to be matters 
resolved within the meaning of 10 CFR 52.63(a)(5). The Commission 
reserves the right to require operational requirements for an applicant 
or licensee who references this appendix by rule, regulation, order, or 
license condition.
    D. Except under the change processes in Section VIII of this 
appendix, the Commission may not require an applicant or licensee who 
references this appendix to:
    1. Modify structures, systems, components, or design features as 
described in the generic DCD;
    2. Provide additional or alternative structures, systems, 
components, or design features not discussed in the generic DCD; or
    3. Provide additional or alternative design criteria, testing, 
analyses, acceptance criteria, or justification for structures, systems, 
components, or design features discussed in the generic DCD.
    E. The NRC will specify at an appropriate time the procedures to be 
used by an interested person who wishes to review portions of the design 
certification or references containing safeguards information or 
sensitive unclassified non-safeguards information (including proprietary 
information, such as trade secrets or financial information obtained 
from a person that are privileged or confidential (10 CFR 2.390 and 10 
CFR part 9)), for the purpose of participating in the hearing required 
by 10 CFR 52.85, the hearing provided under 10 CFR 52.103, or in any 
other proceeding relating to this appendix in which interested persons 
have a right to request an adjudicatory hearing.

                     VII. Duration of This Appendix

    This appendix may be referenced for a period of 15 years from 
February 27, 2006, except as provided for in 10 CFR 52.55(b) and 
52.57(b). This appendix remains valid for an applicant or licensee who 
references this appendix until the application is withdrawn or the 
license expires, including any period of extended operation under a 
renewed license.

               VIII. Processes for Changes and Departures

    A. Tier 1 information.
    1. Generic changes to Tier 1 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 1 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs A.3 or A.4 of this section.
    3. Departures from Tier 1 information that are required by the 
Commission through plant-specific orders are governed by the 
requirements in 10 CFR 52.63(a)(4).
    4. Exemptions from Tier 1 information are governed by the 
requirements in 10 CFR 52.63(b)(1) and 52.98(f). The Commission will 
deny a request for an exemption from Tier 1, if it finds that the design 
change will result in a significant decrease in the level of safety 
otherwise provided by the design.
    B. Tier 2 information.

[[Page 140]]

    1. Generic changes to Tier 2 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 2 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs B.3, B.4, B.5, or B.6 of this section.
    3. The Commission may not require new requirements on Tier 2 
information by plant-specific order while this appendix is in effect 
under 10 CFR 52.55 or 52.61, unless:
    a. A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time this 
appendix was approved, as set forth in Section V of this appendix, or to 
ensure adequate protection of the public health and safety or the common 
defense and security; and
    b. Special circumstances as defined in 10 CFR 50.12(a) are present.
    4. An applicant or licensee who references this appendix may request 
an exemption from Tier 2 information. The Commission may grant such a 
request only if it determines that the exemption will comply with the 
requirements of 10 CFR 50.12(a). The Commission will deny a request for 
an exemption from Tier 2, if it finds that the design change will result 
in a significant decrease in the level of safety otherwise provided by 
the design. The grant of an exemption to an applicant must be subject to 
litigation in the same manner as other issues material to the license 
hearing. The grant of an exemption to a licensee must be subject to an 
opportunity for a hearing in the same manner as license amendments.
    5.a. An applicant or licensee who references this appendix may 
depart from Tier 2 information, without prior NRC approval, unless the 
proposed departure involves a change to or departure from Tier 1 
information, Tier 2* information, or the TS, or requires a license 
amendment under paragraphs B.5.b or B.5.c of this section. When 
evaluating the proposed departure, an applicant or licensee shall 
consider all matters described in the plant-specific DCD.
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-specific 
DCD or one affecting information required by 10 CFR52.47(a)(28) to 
address 10 CFR 50.150, requires a license amendment if it would:
    (1) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the plant-specific 
DCD;
    (2) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a structure, system, or component (SSC) 
important to safety and previously evaluated in the plant-specific DCD;
    (3) Result in more than a minimal increase in the consequences of an 
accident previously evaluated in the plant-specific DCD;
    (4) Result in more than a minimal increase in the consequences of a 
malfunction of an SSC important to safety previously evaluated in the 
plant-specific DCD;
    (5) Create a possibility for an accident of a different type than 
any evaluated previously in the plant-specific DCD;
    (6) Create a possibility for a malfunction of an SSC important to 
safety with a different result than any evaluated previously in the 
plant-specific DCD;
    (7) Result in a design basis limit for a fission product barrier as 
described in the plant-specific DCD being exceeded or altered; or
    (8) Result in a departure from a method of evaluation described in 
the plant-specific DCD used in establishing the design bases or in the 
safety analyses.
    c. A proposed departure from Tier 2 affecting resolution of an ex-
vessel severe accident design feature identified in the plant-specific 
DCD, requires a license amendment if:
    (1) There is a substantial increase in the probability of an ex-
vessel severe accident such that a particular ex-vessel severe accident 
previously reviewed and determined to be not credible could become 
credible; or
    (2) There is a substantial increase in the consequences to the 
public of a particular ex-vessel severe accident previously reviewed.
    d. If an applicant or licensee proposes to depart from the 
information required by 10 CFR 52.47(a)(28) to be included in the FSAR 
for the standard design certification, then the applicant or licensee 
shall consider the effect of the changed feature or capability on the 
original assessment required by 10 CFR 50.150(a). The applicant or 
licensee must also document how the modified design features and 
functional capabilities continue to meet the assessment requirements in 
10 CFR 50.150(a)(1) in accordance with Section X of this appendix.
    e. If a departure requires a license amendment under paragraph B.5.b 
or B.5.c of this section, it is governed by 10 CFR 50.90.
    f. A departure from Tier 2 information that is made under paragraph 
B.5 of this section does not require an exemption from this appendix.
    g. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under 10 CFR 
52.103(a), who believes that an applicant or licensee who references 
this appendix has not complied with paragraph VIII.B.5 of this appendix 
when departing from Tier 2 information, may petition to admit into the 
proceeding such a contention. In addition to compliance with the general 
requirements of 10 CFR 2.309, the petition must demonstrate that the 
departure does not comply with paragraph VIII.B.5 of this appendix. 
Further,

[[Page 141]]

the petition must demonstrate that the change bears on an asserted 
noncompliance with an ITAAC acceptance criterion in the case of a 10 CFR 
52.103 preoperational hearing, or that the change bears directly on the 
amendment request in the case of a hearing on a license amendment. Any 
other party may file a response. If, on the basis of the petition and 
any response, the presiding officer determines that a sufficient showing 
has been made, the presiding officer shall certify the matter directly 
to the Commission for determination of the admissibility of the 
contention. The Commission may admit such a contention if it determines 
the petition raises a genuine issue of material fact regarding 
compliance with paragraph VIII.B.5 of this appendix.
    6.a. An applicant who references this appendix may not depart from 
Tier 2* information, which is designated with italicized text or 
brackets and an asterisk in the generic DCD, without NRC approval. The 
departure will not be considered a resolved issue, within the meaning of 
Section VI of this appendix and 10 CFR 52.63(a)(5).
    b. A licensee who references this appendix may not depart from the 
following Tier 2* matters without prior NRC approval. A request for a 
departure will be treated as a request for a license amendment under 10 
CFR 50.90.
    (1) Maximum fuel rod average burn-up.
    (2) Fuel principal design requirements.
    (3) Fuel criteria evaluation process.
    (4) Fire areas.
    (5) Reactor coolant pump type.
    (6) Small-break loss-of-coolant accident (LOCA) analysis 
methodology.
    (7) Screen design criteria.
    (8) Heat sink data for containment pressure analysis.
    c. A licensee who references this appendix may not, before the plant 
first achieves full power following the finding required by 10 CFR 
52.103(g), depart from the following Tier 2* matters except under 
paragraph B.6.b of this section. After the plant first achieves full 
power, the following Tier 2* matters revert to Tier 2 status and are 
subject to the departure provisions in paragraph B.5 of this section.
    (1) Nuclear Island structural dimensions.
    (2) American Society of Mechanical Engineers Boiler & Pressure 
Vessel Code (ASME Code) piping design and welding restrictions, and ASME 
Code Cases.
    (3) Design Summary of Critical Sections.
    (4) American Concrete Institute (ACI) 318, ACI 349, American 
National Standards Institute/American Institute of Steel Construction 
(ANSI/AISC)-690, and American Iron and Steel Institute (AISI), 
``Specification for the Design of Cold Formed Steel Structural Members, 
Part 1 and 2,'' 1996 Edition and 2000 Supplement.
    (5) Definition of critical locations and thicknesses.
    (6) Seismic qualification methods and standards.
    (7) Nuclear design of fuel and reactivity control system, except 
burn-up limit.
    (8) Motor-operated and power-operated valves.
    (9) Instrumentation and control system design processes, methods, 
and standards.
    (10) Passive residual heat removal (PRHR) natural circulation test 
(first plant only).
    (11) Automatic depressurization system (ADS) and core make-up tank 
(CMT) verification tests (first three plants only).
    (12) Polar crane parked orientation.
    (13) Piping design acceptance criteria.
    (14) Containment vessel design parameters, including ASME Code, 
Section III, Subsection NE.
    (15) Human factors engineering.
    (16) Steel composite structural module details.
    d. Departures from Tier 2* information that are made under paragraph 
B.6 of this section do not require an exemption from this appendix.
    C. Operational requirements.
    1. Generic changes to generic TS and other operational requirements 
that were completely reviewed and approved in the design certification 
rulemaking and do not require a change to a design feature in the 
generic DCD are governed by the requirements in 10 CFR 50.109. Generic 
changes that require a change to a design feature in the generic DCD are 
governed by the requirements in paragraphs A or B of this section.
    2. Generic changes to generic TS and other operational requirements 
are applicable to all applicants who reference this appendix, except 
those for which the change has been rendered technically irrelevant by 
action taken under paragraphs C.3 or C.4 of this section.
    3. The Commission may require plant-specific departures on generic 
TS and other operational requirements that were completely reviewed and 
approved, provided a change to a design feature in the generic DCD is 
not required and special circumstances as defined in 10 CFR 2.335 are 
present. The Commission may modify or supplement generic TS and other 
operational requirements that were not completely reviewed and approved 
or require additional TS and other operational requirements on a plant-
specific basis, provided a change to a design feature in the generic DCD 
is not required.
    4. An applicant who references this appendix may request an 
exemption from the generic technical specifications or other operational 
requirements. The Commission may grant such a request only if it 
determines that the exemption will comply with the requirements of 10 
CFR 52.7. The grant of an

[[Page 142]]

exemption must be subject to litigation in the same manner as other 
issues material to the license hearing.
    5. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license, or for operation under 10 CFR 
52.103(a), who believes that an operational requirement approved in the 
DCD or a TS derived from the generic TS must be changed may petition to 
admit such a contention into the proceeding. The petition must comply 
with the general requirements of 10 CFR 2.309 and must demonstrate why 
special circumstances as defined in 10 CFR 2.335 are present, or 
demonstrate compliance with the Commission's regulations in effect at 
the time this appendix was approved, as set forth in Section V of this 
appendix. Any other party may file a response to the petition. If, on 
the basis of the petition and any response, the presiding officer 
determines that a sufficient showing has been made, the presiding 
officer shall certify the matter directly to the Commission for 
determination of the admissibility of the contention. All other issues 
with respect to the plant-specific TS or other operational requirements 
are subject to a hearing as part of the license proceeding.
    6. After issuance of a license, the generic TS have no further 
effect on the plant-specific TS. Changes to the plant-specific TS will 
be treated as license amendments under 10 CFR 50.90.

    IX. Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

    A.1. An applicant or licensee who references this appendix shall 
perform and demonstrate conformance with the ITAAC before fuel load. 
With respect to activities subject to an ITAAC, an applicant for a 
license may proceed at its own risk with design and procurement 
activities. A licensee may also proceed at its own risk with design, 
procurement, construction, and preoperational activities, even though 
the NRC may not have found that any particular ITAAC has been met.
    2. The licensee who references this appendix shall notify the NRC 
that the required inspections, tests, and analyses in the ITAAC have 
been successfully completed and that the corresponding acceptance 
criteria have been met.
    3. If an activity is subject to an ITAAC and the applicant or 
licensee who references this appendix has not demonstrated that the 
ITAAC has been met, the applicant or licensee may either take corrective 
actions to successfully complete that ITAAC, request an exemption from 
the ITAAC under Section VIII of this appendix and 10 CFR 52.97(b), or 
petition for rulemaking to amend this appendix by changing the 
requirements of the ITAAC, under 10 CFR 2.802 and 52.97(b). Such 
rulemaking changes to the ITAAC must meet the requirements of paragraph 
VIII.A.1 of this appendix.
    B.1. The NRC shall ensure that the required inspections, tests, and 
analyses in the ITAAC are performed. The NRC shall verify that the 
inspections, tests, and analyses referenced by the licensee have been 
successfully completed and, based solely thereon, find that the 
prescribed acceptance criteria have been met. At appropriate intervals 
during construction, the NRC shall publish notices of the successful 
completion of ITAAC in the Federal Register.
    2. In accordance with 10 CFR 52.103(g), the Commission shall find 
that the acceptance criteria in the ITAAC for the license are met before 
fuel load.
    3. After the Commission has made the finding required by 10 CFR 
52.103(g), the ITAAC do not, by virtue of their inclusion within the 
DCD, constitute regulatory requirements either for licensees or for 
renewal of the license; except for specific ITAAC, which are the subject 
of a Sec. 52.103(a) hearing, their expiration will occur upon final 
Commission action in such a proceeding. However, subsequent 
modifications must comply with the Tier 1 and Tier 2 design descriptions 
in the plant-specific DCD unless the licensee has complied with the 
applicable requirements of 10 CFR 52.98 and Section VIII of this 
appendix.

                        X. Records and Reporting

    A. Records
    1. The applicant for this appendix shall maintain a copy of the 
generic DCD that includes all generic changes it makes to Tier 1 and 
Tier 2, and the generic TS and other operational requirements. The 
applicant shall maintain sensitive unclassified non-safeguards 
information (including proprietary information) and safeguards 
information referenced in the generic DCD for the period that this 
appendix may be referenced, as specified in Section VII of this 
appendix.
    2. An applicant or licensee who references this appendix shall 
maintain the plant-specific DCD to accurately reflect both generic 
changes to the generic DCD and plant-specific departures made under 
Section VIII of this appendix throughout the period of application and 
for the term of the license (including any period of renewal).
    3. An applicant or licensee who references this appendix shall 
prepare and maintain written evaluations which provide the bases for the 
determinations required by Section VIII of this appendix. These 
evaluations must be retained throughout the period of application and 
for the term of the license (including any period of renewal).
    4.a. The applicant for the AP1000 design shall maintain a copy of 
the AIA performed to comply with the requirements of 10 CFR 50.150(a) 
for the term of the certification (including any period of renewal).

[[Page 143]]

    b. An applicant or licensee who references this appendix shall 
maintain a copy of the AIA performed to comply with the requirements of 
10 CFR 50.150(a) throughout the pendency of the application and for the 
term of the license (including any period of renewal).
    B. Reporting
    1. An applicant or licensee who references this appendix shall 
submit a report to the NRC containing a brief description of any plant-
specific departures from the DCD, including a summary of the evaluation 
of each. This report must be filed in accordance with the filing 
requirements applicable to reports in 10 CFR 52.3.
    2. An applicant or licensee who references this appendix shall 
submit updates to its DCD, which reflect the generic changes to and 
plant-specific departures from the generic DCD made under Section VIII 
of this appendix. These updates must be filed under the filing 
requirements applicable to final safety analysis report updates in 10 
CFR 52.3 and 50.71(e).
    3. The reports and updates required by paragraphs X.B.1 and X.B.2 
must be submitted as follows:
    a. On the date that an application for a license referencing this 
appendix is submitted, the application must include the report and any 
updates to the generic DCD.
    b. During the interval from the date of application for a license to 
the date the Commission makes its findings required by 10 CFR 52.103(g), 
the report must be submitted semi-annually. Updates to the plant-
specific DCD must be submitted annually and may be submitted along with 
amendments to the application.
    c. After the Commission makes the finding required by 10 CFR 
52.103(g), the reports and updates to the plant-specific DCD must be 
submitted, along with updates to the site-specific portion of the final 
safety analysis report for the facility, at the intervals required by 10 
CFR 50.59(d)(2) and 50.71(e)(4), respectively, or at shorter intervals 
as specified in the license.

[72 FR 49517, Aug. 28, 2007, as amended at 76 FR 82102, Dec. 30, 2011]



  Sec. Appendix E to Part 52--Design Certification Rule for the ESBWR 
                                 Design

                             I. Introduction

    Appendix E constitutes the standard design certification for the 
Economic Simplified Boiling-Water Reactor (ESBWR) design, in accordance 
with 10 CFR part 52, subpart B. The applicant for certification of the 
ESBWR design is GE-Hitachi Nuclear Energy.

                             II. Definitions

    A. Generic design control document (generic DCD) means the document 
containing the Tier 1 and Tier 2 information and generic technical 
specifications that is incorporated by reference into this appendix.
    B. Generic technical specifications (generic TS) means the 
information required by 10 CFR 50.36 and 50.36a for the portion of the 
plant that is within the scope of this appendix.
    C. Plant-specific DCD means that portion of the combined license 
(COL) final safety analysis report (FSAR) that sets forth both the 
generic DCD information and any plant-specific changes to generic DCD 
information.
    D. Tier 1 means the portion of the design-related information 
contained in the generic DCD that is approved and certified by this 
appendix (Tier 1 information). The design descriptions, interface 
requirements, and site parameters are derived from Tier 2 information. 
Tier 1 information includes:
    1. Definitions and general provisions;
    2. Design descriptions;
    3. Inspections, tests, analyses, and acceptance criteria (ITAACs);
    4. Significant site parameters; and
    5. Significant interface requirements.
    E. Tier 2 means the portion of the design-related information 
contained in the generic DCD that is approved but not certified by this 
appendix (Tier 2 information). Compliance with Tier 2 is required, but 
generic changes to and plant-specific departures from Tier 2 are 
governed by Section VIII of this appendix. Compliance with Tier 2 
provides a sufficient, but not the only acceptable, method for complying 
with Tier 1. Compliance methods differing from Tier 2 must satisfy the 
change process in Section VIII of this appendix. Regardless of these 
differences, an applicant or licensee must meet the requirement in 
paragraph III.B of this appendix to reference Tier 2 when referencing 
Tier 1. Tier 2 information includes:
    1. Information required by Sec. Sec. 52.47(a) and 52.47(c), with 
the exception of generic TS and conceptual design information;
    2. Supporting information on the inspections, tests, and analyses 
that will be performed to demonstrate that the acceptance criteria in 
the ITAACs have been met;
    3. COL action items (COL license information), which identify 
certain matters that must be addressed in the site-specific portion of 
the FSAR by an applicant who references this appendix. These items 
constitute information requirements but are not the only acceptable set 
of information in the FSAR. An applicant may depart from or omit these 
items, provided that the departure or omission is identified and 
justified in the FSAR. After issuance of a construction permit or COL, 
these items are not requirements for

[[Page 144]]

the licensee unless such items are restated in the FSAR; and
    4. The availability controls in Appendix 19ACM of the DCD.
    F. Tier 2* means the portion of the Tier 2 information, designated 
as such in the generic DCD, which is subject to the change process in 
paragraph VIII.B.6 of this appendix. This designation expires for some 
Tier 2* information under paragraph VIII.B.6 of this appendix.
    G. Departure from a method of evaluation described in the plant-
specific DCD used in establishing the design bases or in the safety 
analyses means:
    1. Changing any of the elements of the method described in the 
plant-specific DCD unless the results of the analysis are conservative 
or essentially the same; or
    2. Changing from a method described in the plant-specific DCD to 
another method unless that method has been approved by the NRC for the 
intended application.
    H. All other terms in this appendix have the meaning set out in 10 
CFR 50.2, 10 CFR 52.1, or Section 11 of the Atomic Energy Act of 1954, 
as amended, as applicable.

                         III. Scope and Contents

    A. Incorporation by reference approval. The documents in Table 1 are 
approved for incorporation by reference by the Director of the Office of 
the Federal Register under 5 U.S.C. 552(a) and 1 CFR part 51. You may 
obtain copies of the generic DCD from Jerald G. Head, Senior Vice 
President, Regulatory Affairs, GE-Hitachi Nuclear Energy, 3901 Castle 
Hayne Road, MC A-18, Wilmington, NC 28401, telephone: 1-910-819-5692. 
You can view the generic DCD online in the NRC Library at http://
www.nrc.gov/reading-rm/adams.html. In ADAMS, search under the ADAMS 
Accession No. listed in Table 1. If you do not have access to ADAMS or 
if you have problems accessing documents located in ADAMS, contact the 
NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 1-
301-415-3747, or by email at [email protected]. These documents can 
also be viewed at the Federal rulemaking Web site, http://
www.regulations.gov, by searching for documents filed under Docket ID 
NRC-2010-0135. Copies of these documents are available for examination 
and copying at the NRC's PDR located at Room O-1F21, One White Flint 
North, 11555 Rockville Pike, Rockville, Maryland 20852. Copies are also 
available for examination at the NRC Library located at Two White Flint 
North, 11545 Rockville Pike, Rockville, Maryland 20852, telephone: 301-
415-5610, email: [email protected]. All approved material is 
available for inspection at the National Archives and Records 
Administration (NARA). For information on the availability of this 
material at NARA, call 1-202-741-6030 or go to http://www.archives.gov/
federal-register/cfr/ibrlocations.html.

                           Table 1--Documents Approved for Incorporation by Reference
----------------------------------------------------------------------------------------------------------------
             Document No.                       Document title                     ADAMS Accession No.
----------------------------------------------------------------------------------------------------------------
GE Hitachi:
    26A6642AB Rev. 10.................  ESBWR Design Control Document,  ML14104A929 (package)
                                         Revision 10, Tier 1, dated
                                         April 2014.
    26A6642AB Rev. 10.................  ESBWR Design Control Document,  ML14104A929 (package)
                                         Revision 10, Tier 2, dated
                                         April 2014.
Bechtel Power Corporation:
    BC-TOP-3-A........................  ``Tornado and Extreme Wind      ML14093A218
                                         Design Criteria for Nuclear
                                         Power Plants,'' Topical
                                         Report, Revision 3, August
                                         1974.
    BC-TOP-9A.........................  ``Design of Structures for      ML14093A217
                                         Missile Impact,'' Topical
                                         Report, Revision 2, September
                                         1974.
General Electric:
    GEZ-4982A.........................  General Electric Large Steam    ML14093A215
                                         Turbine Generator Quality
                                         Control Program, The STG
                                         Global Supply Chain Quality
                                         Management System (MFGGLO-GEZ-
                                         0010) Revision 1.2, February
                                         7, 2006.
GE Nuclear Energy:
    NEDO-11209-04A....................  ``GE Nuclear Energy Quality     ML14093A209
                                         Assurance Program
                                         Description,'' Class 1,
                                         Revision 8, March 31, 1989.
    NEDO-31960-A......................  ``BWR Owners' Group Long-Term   ML14093A212
                                         Stability Solutions Licensing
                                         Methodology,'' Class I,
                                         November 1995.
    NEDO-31960-A--Supplement 1........  ``BWR Owners' Group Long-Term   ML14093A211
                                         Stability Solutions Licensing
                                         Methodology,'' Class I,
                                         November 1995.
    NEDO-32465-A......................  GE Nuclear Energy and BWR       ML14093A210
                                         Owners' Group, ``Reactor
                                         Stability Detect and Suppress
                                         Solutions Licensing Basis
                                         Methodology for Reload
                                         Applications,'' Class I,
                                         August 1996.
GE-Hitachi Nuclear Energy:
    NEDO-33181........................  ``NP-2010 COL Demonstration     ML14248A297
                                         Project Quality Assurance
                                         Plan,'' Revision 6, August
                                         2009.
    NEDO-33219........................  ``ESBWR Human Factors           ML100350104
                                         Engineering Functional
                                         Requirements Analysis
                                         Implementation Plan,''
                                         Revision 4, Class I, February
                                         2010.

[[Page 145]]

 
    NEDO-33260........................  ``Quality Assurance             ML14248A648
                                         Requirements for Suppliers of
                                         Equipment and Services to the
                                         GEH ESBWR Project,'' Revision
                                         5, Class I, April 2008.
    NEDO-33262........................  ``ESBWR Human Factors           ML100340030
                                         Engineering Operating
                                         Experience Review
                                         Implementation Plan,''
                                         Revision 3, Class I, January
                                         2010.
    NEDO-33266........................  ``ESBWR Human Factors           ML100350167
                                         Engineering Staffing and
                                         Qualifications Implementation
                                         Plan,'' Revision 3, Class I,
                                         January 2010.
    NEDO-33267........................  ``ESBWR Human Factors           ML100330609
                                         Engineering Human Reliability
                                         Analysis Implementation
                                         Plan,'' Revision 4, Class I,
                                         January 2010.
    NEDO-33277........................  ``ESBWR Human Factors           ML100270770
                                         Engineering Human Performance
                                         Monitoring Implementation
                                         Plan,'' Revision 4, Class I,
                                         January 2010.
    NEDO-33278........................  ``ESBWR Human Factors           ML100270468
                                         Engineering Design
                                         Implementation Plan,''
                                         Revision 4, Class I, January
                                         2010.
    NEDO-33289........................  ``ESBWR Reliability Assurance   ML14248A662
                                         Program,'' Revision 2, Class
                                         II, September 2008.
    NEDO-33337........................  ``ESBWR Initial Core Transient  ML091130628
                                         Analyses,'' Revision 1, Class
                                         I, April 2009.
    NEDO-33338........................  ``ESBWR Feedwater Temperature   ML091380173
                                         Operating Domain Transient
                                         and Accident Analysis,''
                                         Revision 1, Class I, May 2009.
    NEDO-33373-A......................  ``Dynamic, Load-Drop, and       ML102990226 (part 1)
                                         Thermal-Hydraulic Analyses     ML102990228 (part 2)
                                         for ESBWR Fuel Racks,''
                                         Revision 5, Class I, October
                                         2010.
    NEDO-33411........................  ``Risk Significance of          ML100610417
                                         Structures, Systems and
                                         Components for the Design
                                         Phase of the ESBWR,''
                                         Revision 2, Class I, February
                                         2010.
----------------------------------------------------------------------------------------------------------------

    B. An applicant or licensee referencing this appendix, in accordance 
with Section IV of this appendix, shall incorporate by reference and 
comply with the requirements of this appendix, including Tier 1, Tier 2 
(including the availability controls in Appendix 19ACM of the DCD), and 
the generic TS except as otherwise provided in this appendix. Conceptual 
design information in the generic DCD and the evaluation of severe 
accident mitigation design alternatives in NEDO-33306, Revision 4, 
``ESBWR Severe Accident Mitigation Design Alternatives,'' are not part 
of this appendix.
    C. If there is a conflict between Tier 1 and Tier 2 of the DCD, then 
Tier 1 controls.
    D. If there is a conflict between the generic DCD and either the 
application for design certification of the ESBWR design or NUREG-1966, 
``Final Safety Evaluation Report Related to Certification of the ESBWR 
Standard Design,'' (FSER) and Supplement No. 1 to NUREG-1966, then the 
generic DCD controls.
    E. Design activities for structures, systems, and components that 
are wholly outside the scope of this appendix may be performed using 
site characteristics, provided the design activities do not affect the 
DCD or conflict with the interface requirements.

              IV. Additional Requirements and Restrictions

    A. An applicant for a COL who references this appendix shall, in 
addition to complying with the requirements of Sec. Sec. 52.77, 52.79, 
and 52.80, comply with the following requirements:
    1. Incorporate by reference, as part of its application, this 
appendix.
    2. Include, as part of its application:
    a. A plant-specific DCD containing the same type of information and 
using the same organization and numbering as the generic DCD for the 
ESBWR design, either by including or incorporating by reference the 
generic DCD information, and as modified and supplemented by the 
applicant's exemptions and departures;
    b. The reports on departures from and updates to the plant-specific 
DCD required by paragraph X.B of this appendix;
    c. Plant-specific TS, consisting of the generic and site-specific TS 
that are required by 10 CFR 50.36 and 50.36a;
    d. Information demonstrating that the site characteristics fall 
within the site parameters and that the interface requirements have been 
met;
    e. Information that addresses the COL action items;
    f. Information required by Sec. 52.47(a) that is not within the 
scope of this appendix;
    g. Information demonstrating that hurricane loads on those 
structures, systems, and

[[Page 146]]

components described in Section 3.3.2 of the generic DCD are either 
bounded by the total tornado loads analyzed in Section 3.3.2 of the 
generic DCD or will meet applicable NRC requirements with consideration 
of hurricane loads in excess of the total tornado loads; and hurricane-
generated missile loads on those structures, systems, and components 
described in Section 3.5.2 of the generic DCD are either bounded by 
tornado-generated missile loads analyzed in Section 3.5.1.4 of the 
generic DCD or will meet applicable NRC requirements with consideration 
of hurricane-generated missile loads in excess of the tornado-generated 
missile loads; and
    h. Information demonstrating that the spent fuel pool level 
instrumentation is designed to allow the connection of an independent 
power source, and that the instrumentation will maintain its design 
accuracy following a power interruption or change in power source 
without requiring recalibration.
    3. Include, in the plant-specific DCD, the sensitive, unclassified, 
non-safeguards information (including proprietary information and 
security-related information) and safeguards information referenced in 
the ESBWR generic DCD.
    4. Include, as part of its application, a demonstration that an 
entity other than GE-Hitachi Nuclear Energy is qualified to supply the 
ESBWR design unless GE-Hitachi Nuclear Energy supplies the design for 
the applicant's use.
    B. The Commission reserves the right to determine in what manner 
this appendix may be referenced by an applicant for a construction 
permit or operating license under 10 CFR part 50.

                        V. Applicable Regulations

    A. Except as indicated in paragraph B of this section, the 
regulations that apply to the ESBWR design are in 10 CFR parts 20, 50, 
73, and 100, codified as of October 6, 2014, that are applicable and 
technically relevant, as described in the FSER (NUREG-1966) and 
Supplement No. 1.
    B. The ESBWR design is exempt from portions of the following 
regulations:
    1. Paragraph (f)(2)(iv) of 10 CFR 50.34--Contents of Applications: 
Technical Information--codified as of October 6, 2014.

                          VI. Issue Resolution

    A. The Commission has determined that the structures, systems, 
components, and design features of the ESBWR design comply with the 
provisions of the Atomic Energy Act of 1954, as amended, and the 
applicable regulations identified in Section V of this appendix; and 
therefore, provide adequate protection to the health and safety of the 
public. A conclusion that a matter is resolved includes the finding that 
additional or alternative structures, systems, components, design 
features, design criteria, testing, analyses, acceptance criteria, or 
justifications are not necessary for the ESBWR design.
    B. The Commission considers the following matters resolved within 
the meaning of Sec. 52.63(a)(5) in subsequent proceedings for issuance 
of a COL, amendment of a COL, or renewal of a COL, proceedings held 
under Sec. 52.103, and enforcement proceedings involving plants 
referencing this appendix:
    1. All nuclear safety issues associated with the information in the 
FSER and Supplement No. 1; Tier 1, Tier 2 (including referenced 
information, which the context indicates is intended as requirements, 
and the availability controls in Appendix 19ACM of the DCD), the 20 
documents referenced in Table 1 of paragraph III.A, and the rulemaking 
record for certification of the ESBWR design, with the exception of: 
generic TS and other operational requirements such as human factors 
engineering procedure development and training program development in 
Sections 18.9 and 18.10 of the generic DCD; hurricane loads on those 
structures, systems, and components described in Section 3.3.2 of the 
generic DCD that are not bounded by the total tornado loads analyzed in 
Section 3.3.2 of the generic DCD; hurricane-generated missile loads on 
those structures, systems, and components described in Section 3.5.2 of 
the generic DCD that are not bounded by tornado-generated missile loads 
analyzed in Section 3.5.1.4 of the generic DCD; and spent fuel pool 
level instrumentation design in regard to the connection of an 
independent power source, and how the instrumentation will maintain its 
design accuracy following a power interruption or change in power source 
without recalibration;
    2. All nuclear safety and safeguards issues associated with the 
referenced information in the 50 non-public documents in Tables 1.6-1 
and 1.6-2 of Tier 2 of the DCD which contain sensitive unclassified non-
safeguards information (including proprietary information and security-
related information) and safeguards information and which, in context, 
are intended as requirements in the generic DCD for the ESBWR design, 
with the exception of human factors engineering procedure development 
and training program development in Chapters 18.9 and 18.10 of the 
generic DCD;
    3. All generic changes to the DCD under and in compliance with the 
change processes in paragraphs VIII.A.1 and VIII.B.1 of this appendix;
    4. All exemptions from the DCD under and in compliance with the 
change processes in paragraphs VIII.A.4 and VIII.B.4 of this appendix, 
but only for that plant;

[[Page 147]]

    5. All departures from the DCD that are approved by license 
amendment, but only for that plant;
    6. Except as provided in paragraph VIII.B.5.f of this appendix, all 
departures from Tier 2 under and in compliance with the change processes 
in paragraph VIII.B.5 of this appendix that do not require prior NRC 
approval, but only for that plant;
    7. All environmental issues concerning severe accident mitigation 
design alternatives associated with the information in the NRC's 
Environmental Assessment for the ESBWR design (ADAMS Accession No. 
ML111730382) and NEDO-33306, Revision 4, ``ESBWR Severe Accident 
Mitigation Design Alternatives,'' (ADAMS Accession No. ML102990433) for 
plants referencing this appendix whose site characteristics fall within 
those site parameters specified in NEDO-33306.
    C. The Commission does not consider operational requirements for an 
applicant or licensee who references this appendix to be matters 
resolved within the meaning of Sec. 52.63(a)(5). The Commission 
reserves the right to require operational requirements for an applicant 
or licensee who references this appendix by rule, regulation, order, or 
license condition.
    D. Except under the change processes in Section VIII of this 
appendix, the Commission may not require an applicant or licensee who 
references this appendix to:
    1. Modify structures, systems, components, or design features as 
described in the generic DCD;
    2. Provide additional or alternative structures, systems, 
components, or design features not discussed in the generic DCD; or
    3. Provide additional or alternative design criteria, testing, 
analyses, acceptance criteria, or justification for structures, systems, 
components, or design features discussed in the generic DCD.
    E. The NRC will specify at an appropriate time the procedures to be 
used by an interested person who seeks to review portions of the design 
certification or references containing safeguards information or 
sensitive unclassified non-safeguards information (including proprietary 
information, such as trade secrets and commercial or financial 
information obtained from a person that are privileged or confidential 
(10 CFR 2.390 and 10 CFR part 9), and security-related information), for 
the purpose of participating in the hearing required by Sec. 52.85, the 
hearing provided under Sec. 52.103, or in any other proceeding relating 
to this appendix in which interested persons have a right to request an 
adjudicatory hearing.

                     VII. Duration of This Appendix

    This appendix may be referenced for a period of 15 years from 
November 14, 2014, except as provided for in Sec. Sec. 52.55(b) and 
52.57(b). This appendix remains valid for an applicant or licensee who 
references this appendix until the application is withdrawn or the 
license expires, including any period of extended operation under a 
renewed license.

               VIII. Processes for Changes and Departures

                          A. Tier 1 information

    1. Generic changes to Tier 1 information are governed by the 
requirements in Sec. 52.63(a)(1).
    2. Generic changes to Tier 1 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs A.3 or A.4 of this section.
    3. Departures from Tier 1 information that are required by the 
Commission through plant-specific orders are governed by the 
requirements in Sec. 52.63(a)(4).
    4. Exemptions from Tier 1 information are governed by the 
requirements in Sec. Sec. 52.63(b)(1) and 52.98(f). The Commission will 
deny a request for an exemption from Tier 1, if it finds that the design 
change will result in a significant decrease in the level of safety 
otherwise provided by the design.

                          B. Tier 2 information

    1. Generic changes to Tier 2 information are governed by the 
requirements in 10 CFR 52.63(a)(1).
    2. Generic changes to Tier 2 information are applicable to all 
applicants or licensees who reference this appendix, except those for 
which the change has been rendered technically irrelevant by action 
taken under paragraphs B.3, B.4, B.5, or B.6 of this section.
    3. The Commission may not require new requirements on Tier 2 
information by plant-specific order while this appendix is in effect 
under 10 CFR 52.55 or 52.61, unless:
    a. A modification is necessary to secure compliance with the 
Commission's regulations applicable and in effect at the time this 
appendix was approved, as set forth in Section V of this appendix, or to 
ensure adequate protection of the public health and safety or the common 
defense and security; and
    b. Special circumstances as defined in 10 CFR 50.12(a) are present.
    4. An applicant or licensee who references this appendix may request 
an exemption from Tier 2 information. The Commission may grant such a 
request only if it determines that the exemption will comply with the 
requirements of 10 CFR 50.12(a). The

[[Page 148]]

Commission will deny a request for an exemption from Tier 2, if it finds 
that the design change will result in a significant decrease in the 
level of safety otherwise provided by the design. The grant of an 
exemption to an applicant must be subject to litigation in the same 
manner as other issues material to the license hearing. The grant of an 
exemption to a licensee must be subject to an opportunity for a hearing 
in the same manner as license amendments.
    5.a. An applicant or licensee who references this appendix may 
depart from Tier 2 information, without prior NRC approval, unless the 
proposed departure involves a change to or departure from Tier 1 
information, Tier 2* information, or the TS, or requires a license 
amendment under paragraph B.5.b or B.5.c of this section. When 
evaluating the proposed departure, an applicant or licensee shall 
consider all matters described in the plant-specific DCD.
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-specific 
DCD or one affecting information required by Sec. 52.47(a)(28) to 
address aircraft impacts, requires a license amendment if it would:
    (1) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the plant-specific 
DCD;
    (2) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a structure, system, or component (SSC) 
important to safety and previously evaluated in the plant-specific DCD;
    (3) Result in more than a minimal increase in the consequences of an 
accident previously evaluated in the plant-specific DCD;
    (4) Result in more than a minimal increase in the consequences of a 
malfunction of an SSC important to safety previously evaluated in the 
plant-specific DCD;
    (5) Create a possibility for an accident of a different type than 
any evaluated previously in the plant-specific DCD;
    (6) Create a possibility for a malfunction of an SSC important to 
safety with a different result than any evaluated previously in the 
plant-specific DCD;
    (7) Result in a design-basis limit for a fission product barrier as 
described in the plant-specific DCD being exceeded or altered; or
    (8) Result in a departure from a method of evaluation described in 
the plant-specific DCD used in establishing the design bases or in the 
safety analyses.
    c. A proposed departure from Tier 2 affecting resolution of an ex-
vessel severe accident design feature identified in the plant-specific 
DCD, requires a license amendment if:
    (1) There is a substantial increase in the probability of an ex-
vessel severe accident such that a particular ex-vessel severe accident 
previously reviewed and determined to be not credible could become 
credible; or
    (2) There is a substantial increase in the consequences to the 
public of a particular ex-vessel severe accident previously reviewed.
    d. A proposed departure from Tier 2 information required by Sec. 
52.47(a)(28) to address aircraft impacts shall consider the effect of 
the changed design feature or functional capability on the original 
aircraft impact assessment required by 10 CFR 50.150(a). The applicant 
or licensee shall describe in the plant-specific DCD how the modified 
design features and functional capabilities continue to meet the 
aircraft impact assessment requirements in 10 CFR 50.150(a)(1).
    e. If a departure requires a license amendment under paragraph B.5.b 
or B.5.c of this section, it is governed by 10 CFR 50.90.
    f. A departure from Tier 2 information that is made under paragraph 
B.5 of this section does not require an exemption from this appendix.
    g. A party to an adjudicatory proceeding for either the issuance, 
amendment, or renewal of a license or for operation under Sec. 
52.103(a), who believes that an applicant or licensee who references 
this appendix has not complied with paragraph VIII.B.5 of this appendix 
when departing from Tier 2 information, may petition to admit into the 
proceeding such a contention. In addition to compliance with the general 
requirements of 10 CFR 2.309, the petition must demonstrate that the 
departure does not comply with paragraph VIII.B.5 of this appendix. 
Further, the petition must demonstrate that the change bears on an 
asserted noncompliance with an ITAAC acceptance criterion in the case of 
a Sec. 52.103 preoperational hearing, or that the change bears directly 
on the amendment request in the case of a hearing on a license 
amendment. Any other party may file a response. If, on the basis of the 
petition and any response, the presiding officer determines that a 
sufficient showing has been made, the presiding officer shall certify 
the matter directly to the Commission for determination of the 
admissibility of the contention. The Commission may admit such a 
contention if it determines the petition raises a genuine issue of 
material fact regarding compliance with paragraph VIII.B.5 of this 
appendix.
    6.a. An applicant who references this appendix may not depart from 
Tier 2* information, which is designated with italicized text or 
brackets and an asterisk in the generic DCD, without NRC approval. The 
departure will not be considered a resolved issue, within the meaning of 
Section VI of this appendix and Sec. 52.63(a)(5).
    b. A licensee who references this appendix may not depart from the 
following Tier 2*

[[Page 149]]

matters without prior NRC approval. A request for a departure will be 
treated as a request for a license amendment under 10 CFR 50.90.
    (1) Fuel mechanical and thermal-mechanical design evaluation 
reports, including fuel burnup limits.
    (2) Control rod mechanical and nuclear design reports.
    (3) Fuel nuclear design report.
    (4) Critical power correlation.
    (5) Fuel licensing acceptance criteria.
    (6) Control rod licensing acceptance criteria.
    (7) Mechanical and structural design of spent fuel storage racks.
    (8) Steam dryer pressure load analysis methodology.
    c. A licensee who references this appendix may not, before the plant 
first achieves full power following the finding required by Sec. 
52.103(g), depart from the following Tier 2* matters except under 
paragraph B.6.b of this section. After the plant first achieves full 
power, the following Tier 2* matters revert to Tier 2 status and are 
subject to the departure provisions in paragraph B.5 of this section.
    (1) ASME Boiler and Pressure Vessel Code, Section III, Subsections 
NE (Division 1) and CC (Division 2) for containment vessel design.
    (2) American Concrete Institute 349 and American National Standards 
Institute/American Institute of Steel Construction--N690.
    (3) Power-operated valves.
    (4) Equipment seismic qualification methods.
    (5) Piping design acceptance criteria.
    (6) Instrument setpoint methodology.
    (7) Safety-Related Distribution Control and Information System 
performance specification and architecture.
    (8) Safety System Logic and Control hardware and software.
    (9) Human factors engineering design and implementation.
    (10) First of a kind testing for reactor stability (first plant 
only).
    (11) Reactor precritical heatup with reactor water cleanup/shutdown 
cooling (first plant only).
    (12) Isolation condenser system heatup and steady state operation 
(first plant only).
    (13) Power maneuvering in the feedwater temperature operating domain 
(first plant only).
    (14) Load maneuvering capability (first plant only).
    (15) Defense-in-depth stability solution evaluation test (first 
plant only).
    d. Departures from Tier 2* information that are made under paragraph 
B.6 of this section do not require an exemption from this appendix.
    C. Operational requirements.
    1. Generic changes to generic TS and other operational requirements 
that were completely reviewed and approved in the design certification 
rulemaking and do not require a change to a design feature in the 
generic DCD are governed by the requirements in 10 CFR 50.109. Generic 
changes that require a change to a design feature in the generic DCD are 
governed by the requirements in paragraphs A or B of this section.
    2. Generic changes to generic TS and other operational requirements 
are applicable to all applicants who reference this appendix, except 
those for which the change has been rendered technically irrelevant by 
action taken under paragraphs C.3 or C.4 of this section.
    3. The Commission may require plant-specific departures on generic 
TS and other operational requirements that were completely reviewed and 
approved, provided a change to a design feature in the generic DCD is 
not required and special circumstances as defined in 10 CFR 2.335 are 
present. The Commission may modify or supplement generic TS and other 
operational requirements that were not completely reviewed and approved 
or require additional TS and other operational requirements on a plant-
specific basis, provided a change to a design feature in the generic DCD 
is not required.
    4. An applicant who references this appendix may request an 
exemption from the generic TS or other operational requirements. The 
Commission may grant such a request only if it determines that the 
exemption will comply with the requirements of Sec. 52.7. The grant of 
an exemption must be subject to litigation in the same manner as other 
issues material to the license hearing.
    5. A party to an adjudicatory proceeding for the issuance, 
amendment, or renewal of a license, or for operation under Sec. 
52.103(a), who believes that an operational requirement approved in the 
DCD or a TS derived from the generic TS must be changed may petition to 
admit such a contention into the proceeding. The petition must comply 
with the general requirements of 10 CFR 2.309 and must demonstrate why 
special circumstances as defined in 10 CFR 2.335 are present, or 
demonstrate compliance with the Commission's regulations in effect at 
the time this appendix was approved, as set forth in Section V of this 
appendix. Any other party may file a response to the petition. If, on 
the basis of the petition and any response, the presiding officer 
determines that a sufficient showing has been made, the presiding 
officer shall certify the matter directly to the Commission for 
determination of the admissibility of the contention. All other issues 
with respect to the plant-specific TS or other operational requirements 
are subject to a hearing as part of the license proceeding.

[[Page 150]]

    6. After issuance of a license, the generic TS have no further 
effect on the plant-specific TS. Changes to the plant-specific TS will 
be treated as license amendments under 10 CFR 50.90.

                             IX. [Reserved]

                        X. Records and Reporting

                               A. Records

    1. The applicant for this appendix shall maintain a copy of the 
generic DCD that includes all generic changes it makes to Tier 1 and 
Tier 2, and the generic TS and other operational requirements. The 
applicant shall maintain the sensitive unclassified non-safeguards 
information (including proprietary information and security-related 
information) and safeguards information referenced in the generic DCD 
for the period that this appendix may be referenced, as specified in 
Section VII of this appendix.
    2. An applicant or licensee who references this appendix shall 
maintain the plant-specific DCD to accurately reflect both generic 
changes to the generic DCD and plant-specific departures made under 
Section VIII of this appendix throughout the period of application and 
for the term of the license (including any period of renewal).
    3. An applicant or licensee who references this appendix shall 
prepare and maintain written evaluations that provide the bases for the 
determinations required by Section VIII of this appendix. These 
evaluations must be retained throughout the period of application and 
for the term of the license (including any period of renewal).
    4.a. The applicant for the ESBWR design shall maintain a copy of the 
aircraft impact assessment performed to comply with the requirements of 
10 CFR 50.150(a) for the term of the certification (including any period 
of renewal).
    b. An applicant or licensee who references this appendix shall 
maintain a copy of the aircraft impact assessment performed to comply 
with the requirements of 10 CFR 50.150(a) throughout the pendency of the 
application and for the term of the license (including any period of 
renewal).

                              B. Reporting

    1. An applicant or licensee who references this appendix shall 
submit a report to the NRC containing a brief description of any plant-
specific departures from the DCD, including a summary of the evaluation 
of each. This report must be filed in accordance with the filing 
requirements applicable to reports in Sec. 52.3.
    2. An applicant or licensee who references this appendix shall 
submit updates to its plant-specific DCD that reflect the generic 
changes to and plant-specific departures from the generic DCD made under 
Section VIII of this appendix. These updates shall be filed under the 
filing requirements applicable to final safety analysis report updates 
in 10 CFR 52.3 and 50.71(e).
    3. The reports and updates required by paragraphs X.B.1 and X.B.2 of 
this appendix must be submitted as follows:
    a. On the date that an application for a license referencing this 
appendix is submitted, the application must include the report and any 
updates to the generic DCD.
    b. During the interval from the date of application for a license to 
the date the Commission makes its finding required by Sec. 52.103(g), 
the report must be submitted semi-annually. Updates to the plant-
specific DCD must be submitted annually and may be submitted along with 
amendments to the application.
    c. After the Commission makes the finding required by Sec. 
52.103(g), the reports and updates to the plant-specific DCD must be 
submitted, along with updates to the site-specific portion of the final 
safety analysis report for the facility, at the intervals required by 10 
CFR 50.59(d)(2) and 50.71(e)(4), respectively, or at shorter intervals 
as specified in the license.

[79 FR 61983, Oct. 15, 2014]



                Sec. Appendixes F-M to Part 52 [Reserved]



   Sec. Appendix N to Part 52--Standardization of Nuclear Power Plant 
   Designs: Combined Licenses To Construct and Operate Nuclear Power 
             Reactors of Identical Design at Multiple Sites

    The Commission's regulations in part 2 of this chapter specifically 
provide for the holding of hearings on particular issues separately from 
other issues involved in hearings in licensing proceedings, and for the 
consolidation of adjudicatory proceedings and of the presentations of 
parties in adjudicatory proceedings such as licensing proceedings 
(Sec. Sec. 2.316 and 2.317 of this chapter).
    This appendix sets out the particular requirements and provisions 
applicable to situations in which applications for combined licenses 
under subpart C of this part are filed by one or more applicants for 
licenses to construct and operate nuclear power reactors of identical 
design (``common design'') to be located at multiple sites. \1\
---------------------------------------------------------------------------

    \1\ If the design for the power reactor(s) proposed in a particular 
application is not identical to the others, that application may not be 
processed under this appendix and subpart D of part 2 of this chapter.
---------------------------------------------------------------------------

    1. Except as otherwise specified in this appendix or as the context 
otherwise indicates,

[[Page 151]]

the provisions of subpart C of this part and subpart D of part 2 of this 
chapter apply to combined license applications subject to this appendix.
    2. Each combined license application submitted pursuant to this 
appendix must be submitted as specified in Sec. 52.75 and 10 CFR 2.101. 
Each application must state that the applicant wishes to have the 
application considered under 10 CFR part 52, appendix N, and must list 
each of the applications to be treated together under this appendix.
    3. Each application must include the information required by 
Sec. Sec. 52.77, 52.79, and 52.80(a), provided however, that the 
application must identify the common design, and, if applicable, 
reference a standard design certification under subpart B of this part, 
or the use of a reactor manufactured under subpart F of this part. The 
final safety analysis report for each application must either 
incorporate by reference or include the final safety analysis of the 
common design, including, if applicable, the final safety analysis 
report for the referenced design certification or the manufactured 
reactor. \2\
---------------------------------------------------------------------------

    \2\ As used in this appendix, the design of a nuclear power reactor 
included in a single referenced safety analysis report means the design 
of those structures, systems, and components important to radiological 
health and safety and the common defense and security.
---------------------------------------------------------------------------

    4. Each combined license application submitted pursuant to this 
appendix must contain an environmental report as required by Sec. 
52.80(b), and which complies with the applicable provisions of 10 CFR 
part 51, provided, however, that the application may incorporate by 
reference a single environmental report on the environmental impacts of 
the common design.
    5. Upon a determination that each application is acceptable for 
docketing under 10 CFR 2.101, each application will be docketed and a 
notice of docketing for each application will be published in the 
Federal Register, in accordance with 10 CFR 2.104, provided, however, 
that the notice must state that the application will be processed under 
the provisions of 10 CFR part 52, appendix N, and subpart D of part 2 of 
this chapter. As the discretion of the Commission, a single notice of 
docketing for multiple applications may be published in the Federal 
Register.
    6. The NRC staff shall prepare draft and final environmental impact 
statements for each of the applications under part 51 of this chapter. 
Scoping under 10 CFR 51.28 and 51.29 for each of the combined license 
applications may be conducted simultaneously and joint scoping may be 
conducted with respect to the environmental issues relevant to the 
common design.
    If the applications reference a standard design certification, then 
the environmental impact statement for each of the applications must 
incorporate by reference the design certification environmental 
assessment. If the applications do not reference a standard design 
certification, then the NRC staff shall prepare draft and final 
supplemental environmental impact statements which address severe 
accident mitigation design alternatives for the common design, which 
must be incorporated by reference into the environmental impact 
statement prepared for each application. Scoping under 10 CFR 51.28 and 
51.29 for the supplemental environmental impact statement may be 
conducted simultaneously, and may be part of the scoping for each of the 
combined license applications.
    7. The ACRS shall report on each of the applications as required by 
Sec. 52.87. Each report must be limited to those safety matters for 
each application which are not relevant to the common design. In 
addition, the ACRS shall separately report on the safety of the common 
design, provided, however, that the report need not address the safety 
of a referenced standard design certification or reactor manufactured 
under subpart F of this part.
    8. The Commission shall designate a presiding officer to conduct the 
proceeding with respect to the health and safety, common defense and 
security, and environmental matters relating to the common design. The 
hearing will be governed by the applicable provisions of subparts A, C, 
G, L, N, and O of part 2 of this chapter relating to applications for 
combined licenses. The presiding officer shall issue a partial initial 
decision on the common design.

                           PART 53 [RESERVED]



PART 54_REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR 
POWER PLANTS--Table of Contents



                           General Provisions

Sec.
54.1 Purpose.
54.3 Definitions.
54.4 Scope.
54.5 Interpretations.
54.7 Written communications.
54.9 Information collection requirements: OMB approval.
54.11 Public inspection of applications.
54.13 Completeness and accuracy of information.
54.15 Specific exemptions.
54.17 Filing of application.
54.19 Contents of application--general information.

[[Page 152]]

54.21 Contents of application--technical information.
54.22 Contents of application--technical specifications.
54.23 Contents of application--environmental information.
54.25 Report of the Advisory Committee on Reactor Safeguards.
54.27 Hearings.
54.29 Standards for issuance of a renewed license.
54.30 Matters not subject to a renewal review.
54.31 Issuance of a renewed license.
54.33 Continuation of CLB and conditions of renewed license.
54.35 Requirements during term of renewed license.
54.37 Additional records and recordkeeping requirements.
54.41 Violations.
54.43 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 102, 103, 104, 161, 181, 
182, 183, 186, 189, 223, 234 (42 U.S.C. 2132, 2133, 2134, 2136, 2137, 
2201, 2231, 2232, 2233, 2236, 2239, 2273, 2282); Energy Reorganization 
Act of 1974, secs. 201, 202, 206 (42 U.S.C. 5841, 5842, 5846); 44 U.S.C. 
3504 note.
    Section 54.17 also issued under E.O. 12829, 58 FR 3479, 3 CFR, 1993 
Comp., p. 570; E.O. 13526, 75 FR 707, 3 CFR, 2009 Comp., p. 298; E.O. 
12968, 60 FR 40245, 3 CFR, 1995 Comp., p. 391.

    Source: 60 FR 22491, May 8, 1995, unless otherwise noted.

                           General Provisions



Sec. 54.1  Purpose.

    This part governs the issuance of renewed operating licenses and 
renewed combined licenses for nuclear power plants licensed pursuant to 
Sections 103 or 104b of the Atomic Energy Act of 1954, as amended, and 
Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242).

[72 FR 49560, Aug. 28, 2007]



Sec. 54.3  Definitions.

    (a) As used in this part,
    Current licensing basis (CLB) is the set of NRC requirements 
applicable to a specific plant and a licensee's written commitments for 
ensuring compliance with and operation within applicable NRC 
requirements and the plant-specific design basis (including all 
modifications and additions to such commitments over the life of the 
license) that are docketed and in effect. The CLB includes the NRC 
regulations contained in 10 CFR parts 2, 19, 20, 21, 26, 30, 40, 50, 51, 
52, 54, 55, 70, 72, 73, 100 and appendices thereto; orders; license 
conditions; exemptions; and technical specifications. It also includes 
the plant-specific design-basis information defined in 10 CFR 50.2 as 
documented in the most recent final safety analysis report (FSAR) as 
required by 10 CFR 50.71 and the licensee's commitments remaining in 
effect that were made in docketed licensing correspondence such as 
licensee responses to NRC bulletins, generic letters, and enforcement 
actions, as well as licensee commitments documented in NRC safety 
evaluations or licensee event reports.
    Integrated plant assessment (IPA) is a licensee assessment that 
demonstrates that a nuclear power plant facility's structures and 
components requiring aging management review in accordance with Sec. 
54.21(a) for license renewal have been identified and that the effects 
of aging on the functionality of such structures and components will be 
managed to maintain the CLB such that there is an acceptable level of 
safety during the period of extended operation.
    Nuclear power plant means a nuclear power facility of a type 
described in 10 CFR 50.21(b) or 50.22.
    Renewed combined license means a combined license originally issued 
under part 52 of this chapter for which an application for renewal is 
filed in accordance with 10 CFR 52.107 and issued under this part.
    Time-limited aging analyses, for the purposes of this part, are 
those licensee calculations and analyses that:
    (1) Involve systems, structures, and components within the scope of 
license renewal, as delineated in Sec. 54.4(a);
    (2) Consider the effects of aging;
    (3) Involve time-limited assumptions defined by the current 
operating term, for example, 40 years;
    (4) Were determined to be relevant by the licensee in making a 
safety determination;
    (5) Involve conclusions or provide the basis for conclusions related 
to the capability of the system, structure, and component to perform its 
intended functions, as delineated in Sec. 54.4(b); and

[[Page 153]]

    (6) Are contained or incorporated by reference in the CLB.
    (b) All other terms in this part have the same meanings as set out 
in 10 CFR 50.2 or Section 11 of the Atomic Energy Act, as applicable.

[60 FR 22491, May 8, 1995, as amended at 72 FR 49560, Aug. 28, 2007]



Sec. 54.4  Scope.

    (a) Plant systems, structures, and components within the scope of 
this part are--
    (1) Safety-related systems, structures, and components which are 
those relied upon to remain functional during and following design-basis 
events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following 
functions--
    (i) The integrity of the reactor coolant pressure boundary;
    (ii) The capability to shut down the reactor and maintain it in a 
safe shutdown condition; or
    (iii) The capability to prevent or mitigate the consequences of 
accidents which could result in potential offsite exposures comparable 
to those referred to in Sec. 50.34(a)(1), Sec. 50.67(b)(2), or Sec. 
100.11 of this chapter, as applicable.
    (2) All nonsafety-related systems, structures, and components whose 
failure could prevent satisfactory accomplishment of any of the 
functions identified in paragraphs (a)(1) (i), (ii), or (iii) of this 
section.
    (3) All systems, structures, and components relied on in safety 
analyses or plant evaluations to perform a function that demonstrates 
compliance with the Commission's regulations for fire protection (10 CFR 
50.48), environmental qualification (10 CFR 50.49), pressurized thermal 
shock (10 CFR 50.61), anticipated transients without scram (10 CFR 
50.62), and station blackout (10 CFR 50.63).
    (b) The intended functions that these systems, structures, and 
components must be shown to fulfill in Sec. 54.21 are those functions 
that are the bases for including them within the scope of license 
renewal as specified in paragraphs (a) (1)-(3) of this section.

[60 FR 22491, May 8, 1995, as amended at 61 FR 65175, Dec. 11, 1996; 64 
FR 72002, Dec. 23, 1999]



Sec. 54.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 54.7  Written communications.

    All applications, correspondence, reports, and other written 
communications shall be filed in accordance with applicable portions of 
10 CFR 50.4.



Sec. 54.9  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501, et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0155.
    (b) The approved information requirements contained in this part 
appear in Sec. Sec. 54.13, 54.15, 54.17, 54.19, 54.21, 54.22, 54.23, 
54.33, and 54.37.

[60 FR 22491, May 8, 1995, as amended at 62 FR 52188, Oct. 6, 1997; 67 
FR 67100, Nov. 4, 2002]



Sec. 54.11  Public inspection of applications.

    Applications and documents submitted to the Commission in connection 
with renewal applications may be made available for public inspection in 
accordance with the provisions of the regulations contained in 10 CFR 
part 2.



Sec. 54.13  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
renewed license or information required by statute or by the 
Commission's regulations, orders, or license conditions to be maintained 
by the applicant must

[[Page 154]]

be complete and accurate in all material respects.
    (b) Each applicant shall notify the Commission of information 
identified by the applicant as having, for the regulated activity, a 
significant implication for public health and safety or common defense 
and security. An applicant violates this paragraph only if the applicant 
fails to notify the Commission of information that the applicant has 
identified as having a significant implication for public health and 
safety or common defense and security. Notification must be provided to 
the Administrator of the appropriate regional office within 2 working 
days of identifying the information. This requirement is not applicable 
to information that is already required to be provided to the Commission 
by other reporting or updating requirements.



Sec. 54.15  Specific exemptions.

    Exemptions from the requirements of this part may be granted by the 
Commission in accordance with 10 CFR 50.12.



Sec. 54.17  Filing of application.

    (a) The filing of an application for a renewed license must be in 
accordance with subpart A of 10 CFR part 2 and 10 CFR 50.4 and 50.30.
    (b) Any person who is a citizen, national, or agent of a foreign 
country, or any corporation, or other entity which the Commission knows 
or has reason to know is owned, controlled, or dominated by an alien, a 
foreign corporation, or a foreign government, is ineligible to apply for 
and obtain a renewed license.
    (c) An application for a renewed license may not be submitted to the 
Commission earlier than 20 years before the expiration of the operating 
license or combined license currently in effect.
    (d) An applicant may combine an application for a renewed license 
with applications for other kinds of licenses.
    (e) An application may incorporate by reference information 
contained in previous applications for licenses or license amendments, 
statements, correspondence, or reports filed with the Commission, 
provided that the references are clear and specific.
    (f) If the application contains Restricted Data or other defense 
information, it must be prepared in such a manner that all Restricted 
Data and other defense information are separated from unclassified 
information in accordance with 10 CFR 50.33(j).
    (g) As part of its application, and in any event before the receipt 
of Restricted Data or classified National Security Information or the 
issuance of a renewed license, the applicant shall agree in writing that 
it will not permit any individual to have access to or any facility to 
possess Restricted Data or classified National Security Information 
until the individual and/or facility has been approved for such access 
under the provisions of 10 CFR parts 25 and/or 95. The agreement of the 
applicant in this regard shall be deemed part of the renewed license, 
whether so stated therein or not.

[60 FR 22491, May 8, 1995, as amended at 62 FR 17690, Apr. 11, 1997; 72 
FR 49560, Aug. 28, 2007]



Sec. 54.19  Contents of application--general information.

    (a) Each application must provide the information specified in 10 
CFR 50.33 (a) through (e), (h), and (i). Alternatively, the application 
may incorporate by reference other documents that provide the 
information required by this section.
    (b) Each application must include conforming changes to the standard 
indemnity agreement, 10 CFR 140.92, Appendix B, to account for the 
expiration term of the proposed renewed license.



Sec. 54.21  Contents of application--technical information.

    Each application must contain the following information:
    (a) An integrated plant assessment (IPA). The IPA must--
    (1) For those systems, structures, and components within the scope 
of this part, as delineated in Sec. 54.4, identify and list those 
structures and components subject to an aging management review. 
Structures and components subject to an aging management review shall 
encompass those structures and components--
    (i) That perform an intended function, as described in Sec. 54.4, 
without

[[Page 155]]

moving parts or without a change in configuration or properties. These 
structures and components include, but are not limited to, the reactor 
vessel, the reactor coolant system pressure boundary, steam generators, 
the pressurizer, piping, pump casings, valve bodies, the core shroud, 
component supports, pressure retaining boundaries, heat exchangers, 
ventilation ducts, the containment, the containment liner, electrical 
and mechanical penetrations, equipment hatches, seismic Category I 
structures, electrical cables and connections, cable trays, and 
electrical cabinets, excluding, but not limited to, pumps (except 
casing), valves (except body), motors, diesel generators, air 
compressors, snubbers, the control rod drive, ventilation dampers, 
pressure transmitters, pressure indicators, water level indicators, 
switchgears, cooling fans, transistors, batteries, breakers, relays, 
switches, power inverters, circuit boards, battery chargers, and power 
supplies; and
    (ii) That are not subject to replacement based on a qualified life 
or specified time period.
    (2) Describe and justify the methods used in paragraph (a)(1) of 
this section.
    (3) For each structure and component identified in paragraph (a)(1) 
of this section, demonstrate that the effects of aging will be 
adequately managed so that the intended function(s) will be maintained 
consistent with the CLB for the period of extended operation.
    (b) CLB changes during NRC review of the application. Each year 
following submittal of the license renewal application and at least 3 
months before scheduled completion of the NRC review, an amendment to 
the renewal application must be submitted that identifies any change to 
the CLB of the facility that materially affects the contents of the 
license renewal application, including the FSAR supplement.
    (c) An evaluation of time-limited aging analyses. (1) A list of 
time-limited aging analyses, as defined in Sec. 54.3, must be provided. 
The applicant shall demonstrate that--
    (i) The analyses remain valid for the period of extended operation;
    (ii) The analyses have been projected to the end of the period of 
extended operation; or
    (iii) The effects of aging on the intended function(s) will be 
adequately managed for the period of extended operation.
    (2) A list must be provided of plant-specific exemptions granted 
pursuant to 10 CFR 50.12 and in effect that are based on time-limited 
aging analyses as defined in Sec. 54.3. The applicant shall provide an 
evaluation that justifies the continuation of these exemptions for the 
period of extended operation.
    (d) An FSAR supplement. The FSAR supplement for the facility must 
contain a summary description of the programs and activities for 
managing the effects of aging and the evaluation of time-limited aging 
analyses for the period of extended operation determined by paragraphs 
(a) and (c) of this section, respectively.



Sec. 54.22  Contents of application--technical specifications.

    Each application must include any technical specification changes or 
additions necessary to manage the effects of aging during the period of 
extended operation as part of the renewal application. The justification 
for changes or additions to the technical specifications must be 
contained in the license renewal application.



Sec. 54.23  Contents of application--environmental information.

    Each application must include a supplement to the environmental 
report that complies with the requirements of subpart A of 10 CFR part 
51.



Sec. 54.25  Report of the Advisory Committee on Reactor Safeguards.

    Each renewal application will be referred to the Advisory Committee 
on Reactor Safeguards for a review and report. Any report will be made 
part of the record of the application and made available to the public, 
except to the extent that security classification prevents disclosure.



Sec. 54.27  Hearings.

    A notice of an opportunity for a hearing will be published in the 
Federal Register in accordance with 10 CFR 2.105 and 2.309. In the 
absence of a request for a hearing filed within 60 days

[[Page 156]]

by a person whose interest may be affected, the Commission may issue a 
renewed operating license or renewed combined license without a hearing 
upon a 30-day notice and publication in the Federal Register of its 
intent to do so.

[77 FR 46600, Aug. 3, 2012]



Sec. 54.29  Standards for issuance of a renewed license.

    A renewed license may be issued by the Commission up to the full 
term authorized by Sec. 54.31 if the Commission finds that:
    (a) Actions have been identified and have been or will be taken with 
respect to the matters identified in paragraphs (a)(1) and (a)(2) of 
this section, such that there is reasonable assurance that the 
activities authorized by the renewed license will continue to be 
conducted in accordance with the CLB, and that any changes made to the 
plant's CLB in order to comply with this paragraph are in accord with 
the Act and the Commission's regulations. These matters are:
    (1) managing the effects of aging during the period of extended 
operation on the functionality of structures and components that have 
been identified to require review under Sec. 54.21(a)(1); and
    (2) time-limited aging analyses that have been identified to require 
review under Sec. 54.21(c).
    (b) Any applicable requirements of subpart A of 10 CFR part 51 have 
been satisfied.
    (c) Any matters raised under Sec. 2.335 have been addressed.

[60 FR 22491, May 8, 1995, as amended at 69 FR 2279, Jan. 14, 2004]



Sec. 54.30  Matters not subject to a renewal review.

    (a) If the reviews required by Sec. 54.21 (a) or (c) show that 
there is not reasonable assurance during the current license term that 
licensed activities will be conducted in accordance with the CLB, then 
the licensee shall take measures under its current license, as 
appropriate, to ensure that the intended function of those systems, 
structures or components will be maintained in accordance with the CLB 
throughout the term of its current license.
    (b) The licensee's compliance with the obligation under Paragraph 
(a) of this section to take measures under its current license is not 
within the scope of the license renewal review.



Sec. 54.31  Issuance of a renewed license.

    (a) A renewed license will be of the class for which the operating 
license or combined license currently in effect was issued.
    (b) A renewed license will be issued for a fixed period of time, 
which is the sum of the additional amount of time beyond the expiration 
of the operating license or combined license (not to exceed 20 years) 
that is requested in a renewal application plus the remaining number of 
years on the operating license or combined license currently in effect. 
The term of any renewed license may not exceed 40 years.
    (c) A renewed license will become effective immediately upon its 
issuance, thereby superseding the operating license or combined license 
previously in effect. If a renewed license is subsequently set aside 
upon further administrative or judicial appeal, the operating license or 
combined license previously in effect will be reinstated unless its term 
has expired and the renewal application was not filed in a timely 
manner.
    (d) A renewed license may be subsequently renewed in accordance with 
all applicable requirements.

[60 FR 22491, May 8, 1995, as amended at 72 FR 49560, Aug. 28, 2007]



Sec. 54.33  Continuation of CLB and conditions of renewed license.

    (a) Whether stated therein or not, each renewed license will contain 
and otherwise be subject to the conditions set forth in 10 CFR 50.54.
    (b) Each renewed license will be issued in such form and contain 
such conditions and limitations, including technical specifications, as 
the Commission deems appropriate and necessary to help ensure that 
systems, structures, and components subject to review in accordance with 
Sec. 54.21 will continue to perform their intended functions for the 
period of extended operation. In addition, the renewed license will be 
issued in such form and

[[Page 157]]

contain such conditions and limitations as the Commission deems 
appropriate and necessary to help ensure that systems, structures, and 
components associated with any time-limited aging analyses will continue 
to perform their intended functions for the period of extended 
operation.
    (c) Each renewed license will include those conditions to protect 
the environment that were imposed pursuant to 10 CFR 50.36b and that are 
part of the CLB for the facility at the time of issuance of the renewed 
license. These conditions may be supplemented or amended as necessary to 
protect the environment during the term of the renewed license and will 
be derived from information contained in the supplement to the 
environmental report submitted pursuant to 10 CFR part 51, as analyzed 
and evaluated in the NRC record of decision. The conditions will 
identify the obligations of the licensee in the environmental area, 
including, as appropriate, requirements for reporting and recordkeeping 
of environmental data and any conditions and monitoring requirements for 
the protection of the nonaquatic environment.
    (d) The licensing basis for the renewed license includes the CLB, as 
defined in Sec. 54.3(a); the inclusion in the licensing basis of 
matters such as licensee commitments does not change the legal status of 
those matters unless specifically so ordered pursuant to paragraphs (b) 
or (c) of this section.



Sec. 54.35  Requirements during term of renewed license.

    During the term of a renewed license, licensees shall be subject to 
and shall continue to comply with all Commission regulations contained 
in 10 CFR parts 2, 19, 20, 21, 26, 30, 40, 50, 51, 52, 54, 55, 70, 72, 
73, and 100, and the appendices to these parts that are applicable to 
holders of operating licenses or combined licenses, respectively.

[72 FR 49560, Aug. 28, 2007]



Sec. 54.37  Additional records and recordkeeping requirements.

    (a) The licensee shall retain in an auditable and retrievable form 
for the term of the renewed operating license or renewed combined 
license all information and documentation required by, or otherwise 
necessary to document compliance with, the provisions of this part.
    (b) After the renewed license is issued, the FSAR update required by 
10 CFR 50.71(e) must include any systems, structures, and components 
newly identified that would have been subject to an aging management 
review or evaluation of time-limited aging analyses in accordance with 
Sec. 54.21. This FSAR update must describe how the effects of aging 
will be managed such that the intended function(s) in Sec. 54.4(b) will 
be effectively maintained during the period of extended operation.

[60 FR 22491, May 8, 1995, as amended at 72 FR 49560, Aug. 28, 2007]



Sec. 54.41  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of the following acts--
    (1) The Atomic Energy Act of 1954, as amended.
    (2) Title II of the Energy Reorganization Act of 1974, as amended or
    (3) A regulation or order issued pursuant to those acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under Section 234 of the Atomic Energy Act--
    (1) For violations of the following--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
Section 186 of the Atomic Energy Act of 1954, as amended.



Sec. 54.43  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violations of, attempted 
violation of, or conspiracy to violate, any regulation

[[Page 158]]

issued under sections 161b, 161i, or 161o of the Act. For purposes of 
section 223, all the regulations in part 54 are issued under one or more 
of sections 161b, 161i, or 161o, except for the sections listed in 
paragraph (b) of this section.
    (b) The regulations in part 54 that are not issued under Sections 
161b, 161i, or 161o for the purposes of Section 223 are as follows: 
Sec. Sec. 54.1, 54.3, 54.4, 54.5, 54.7, 54.9, 54.11, 54.15, 54.17, 
54.19, 54.21, 54.22, 54.23, 54.25, 54.27, 54.29, 54.31, 54.41, and 
54.43.



PART 55_OPERATORS' LICENSES--Table of Contents



                      Subpart A_General Provisions

Sec.
55.1 Purpose.
55.2 Scope.
55.3 License requirements.
55.4 Definitions.
55.5 Communications.
55.6 Interpretations.
55.7 Additional requirements.
55.8 Information collection requirements: OMB approval.
55.9 Completeness and accuracy of information.

                          Subpart B_Exemptions

55.11 Specific exemptions.
55.13 General exemptions.

                     Subpart C_Medical Requirements

55.21 Medical examination.
55.23 Certification.
55.25 Incapacitation because of disability or illness.
55.27 Documentation.

                         Subpart D_Applications

55.31 How to apply.
55.33 Disposition of an initial application.
55.35 Re-applications.

           Subpart E_Written Examinations and Operating Tests

55.40 Implementation.
55.41 Written examination: Operators.
55.43 Written examination: Senior operators.
55.45 Operating tests.
55.46 Simulation facilities.
55.47 Waiver of examination and test requirements.
55.49 Integrity of examinations and tests.

                           Subpart F_Licenses

55.51 Issuance of licenses.
55.53 Conditions of licenses.
55.55 Expiration.
55.57 Renewal of licenses.
55.59 Requalification.

            Subpart G_Modification and Revocation of Licenses

55.61 Modification and revocation of licenses.

                          Subpart H_Enforcement

55.71 Violations.
55.73 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 107, 161, 181, 182, 183, 
186, 187, 223, 234 (42 U.S.C. 2137, 2201, 2231, 2232, 2233, 2236, 2237, 
2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202 (42 
U.S.C. 5841, 5842); Nuclear Waste Policy Act of 1982, sec. 306 (42 
U.S.C. 10226); 44 U.S.C. 3504 note.
    Section 55.61 also issued under Atomic Energy Act secs. 186, 187 (42 
U.S.C. 2236, 2237).

    Source: 52 FR 9460, Mar. 25, 1987, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 55 appear at 80 FR 
74980, Dec. 1, 2015.



                      Subpart A_General Provisions



Sec. 55.1  Purpose.

    The regulations in this part:
    (a) Establish procedures and criteria for the issuance of licenses 
to operators and senior operators of utilization facilities licensed 
under the Atomic Energy Act of 1954, as amended, or Section 202 of the 
Energy Reorganization Act of 1974, as amended, and part 50, part 52, or 
part 54 of this chapter,
    (b) Provide for the terms and conditions upon which the Commission 
will issue or modify these licenses, and
    (c) Provide for the terms and conditions to maintain and renew these 
licenses.

[52 FR 9460, Mar. 25, 1987, as amended at 72 FR 49560, Aug. 28, 2007]



Sec. 55.2  Scope.

    The regulations in this part apply to--
    (a) Any individual who manipulates the controls of any utilization 
facility licensed under parts 50, 52, or 54 of this chapter,
    (b) Any individual designated by a facility licensee to be 
responsible for directing any licensed activity of a licensed operator.

[[Page 159]]

    (c) Any facility license.

[52 FR 9460, Mar. 25, 1987, as amended at 59 FR 5938, Feb. 9, 1994; 72 
FR 49560, Aug. 28, 2007]



Sec. 55.3  License requirements.

    A person must be authorized by a license issued by the Commission to 
perform the function of an operator or a senior operator as defined in 
this part.



Sec. 55.4  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954, including any amendments to 
the Act.
    Actively performing the functions of an operator or senior operator 
means that an individual has a position on the shift crew that requires 
the individual to be licensed as defined in the facility's technical 
specifications, and that the individual carries out and is responsible 
for the duties covered by that position.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Controls when used with respect to a nuclear reactor means apparatus 
and mechanisms the manipulation of which directly affects the reactivity 
or power level of the reactor.
    Facility means any utilization facility as defined in part 50 of 
this chapter. In cases for which a license is issued for operation of 
two or more facilities, facility means all facilities identified in the 
license.
    Facility licensee means an applicant for or holder of a license for 
a facility.
    Licensee means an individual licensed operator or senior operator.
    Operator means any individual licensed under this part to manipulate 
a control of a facility.
    Performance testing means testing conducted to verify a simulation 
facility's performance as compared to actual or predicted reference 
plant performance.
    Physician means an individual licensed by a State or territory of 
the United States, the District of Columbia or the Commonwealth of 
Puerto Rico to dispense drugs in the practice of medicine.
    Plant-referenced simulator means a simulator modeling the systems of 
the reference plant with which the operator interfaces in the control 
room, including operating consoles, and which permits use of the 
reference plant's procedures.
    Reference plant means the specific nuclear power plant from which a 
simulation facility's control room configuration, system control 
arrangement, and design data are derived.
    Senior operator means any individual licensed under this part to 
manipulate the controls of a facility and to direct the licensed 
activities of licensed operators.
    Simulation facility means one or more of the following components, 
alone or in combination: used for either the partial conduct of 
operating tests for operators, senior operators, and license applicants, 
or to establish on-the-job training and experience prerequisites for 
operator license eligibility:
    (1) A plant-referenced simulator;
    (2) A Commission-approved simulator under Sec. 55.46(b); or
    (3) Another simulation device, including part-task and limited scope 
simulation devices, approved under Sec. 55.46(b).
    Systems approach to training means a training program that includes 
the following five elements:
    (1) Systematic analysis of the jobs to be performed.
    (2) Learning objectives derived from the analysis which describe 
desired performance after training.
    (3) Training design and implementation based on the learning 
objectives.
    (4) Evaluation of trainee mastery of the objectives during training.
    (5) Evaluation and revision of the training based on the performance 
of trained personnel in the job setting.
    United States, when used in a geographical sense, includes Puerto 
Rico and all territories and possessions of the United States.

[52 FR 9460, Mar. 25, 1987, as amended at 66 FR 52667, Oct. 17, 2001]



Sec. 55.5  Communications.

    (a) Except as provided under a regional licensing program identified 
in paragraph (b) of this section, an applicant or licensee or facility 
licensee shall submit any communication or report concerning the 
regulations in this

[[Page 160]]

part and shall submit any application filed under these regulations to 
the Commission as follows:
    (1) By mail addressed to--Director, Office of Nuclear Reactor 
Regulation or Director, Office of New Reactors, as appropriate, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001; or
    (2) By delivery in person to the NRC's offices at 11555 Rockville 
Pike, Rockville, Maryland, or
    (3) Where practicable, by electronic submission, for example, via 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.
    (b)(1) Except for test and research reactor facilities, the 
Director, Office of Nuclear Reactor Regulation or Director, Office of 
New Reactors, as appropriate, has delegated to the Regional 
Administrators of Regions I, II, III, and IV authority and 
responsibility under the regulations in this part for the issuance and 
renewal of licenses for operators and senior operators of nuclear power 
reactors licensed under 10 CFR part 50 or part 52 of this chapter and 
located in these regions.
    (2) Any application for a license or license renewal filed under the 
regulations in this part involving a nuclear power reactor licensed 
under 10 CFR part 50 or part 52 of this chapter and any related inquiry, 
communication, information, or report must be submitted to the Regional 
Administrator by an appropriate method listed in paragraph (a) of this 
section. The Regional Administrator or the Administrator's designee will 
transmit to the Director, Office of New Reactors or Director, Office of 
Nuclear Reactor Regulation, as appropriate, any matter that is not 
within the scope of the Regional Administrator's delegated authority.
    (i) If the nuclear power reactor is located in Region I, submissions 
must be made to the Regional Administrator of Region I. Submissions by 
mail or hand delivery must be addressed to the Administrator at U.S. 
Nuclear Regulatory Commission, 2100 Renaissance Boulevard, Suite 100, 
King of Prussia, PA 19406-2713; where email is appropriate it should be 
addressed to [email protected].
    (ii) If the nuclear power reactor is located in Region II, 
submissions must be made to the Regional Administrator of Region II. 
Submissions by mail or hand delivery must be addressed to the Regional 
Administrator at U.S. Nuclear Regulatory Commission, 245 Peachtree 
Center Avenue, NE., Suite 1200, Atlanta, Georgia 30303-1257. Where e-
mail is appropriate, it should be addressed to 
[email protected].
    (iii) If the nuclear power reactor is located in Region III, 
submissions must be made to the Regional Administrator of Region III. 
Submissions by mail or hand delivery must be addressed to the 
Administrator at U.S. Nuclear Regulatory Commission, 2443 Warrenville 
Road, Suite 210, Lisle, IL 60532-4352; where e-mail is appropriate it 
should be addressed to [email protected].
    (iv) If the nuclear power reactor is located in Region IV, 
submissions must be made to the Regional Administrator of Region IV. 
Submission by mail or hand delivery must be addressed to the 
Administrator at U.S. Nuclear Regulatory Commission, 1600 E. Lamar 
Blvd., Arlington, TX 76011-4511; where email is appropriate, it should 
be addressed to [email protected].
    (3) Any application for a license or license renewal filed under the 
regulations in this part and all other submissions involving a test and 
research reactor or non-power reactor facility licensed under 10 CFR 
part 50 and any related inquiry, communication, information, or report 
must be submitted to the Office of Nuclear Reactor Regulation, Director 
of the Division of Policy

[[Page 161]]

and Rulemaking at the NRC's headquarters, by an appropriate method 
listed in paragraph (a) of this section.

[52 FR 9460, Mar. 25, 1987]

    Editorial Note: For Federal Register citations affecting Sec. 55.5, 
see the List of CFR Sections Affected, which appears in the Finding Aids 
section of the printed volume and at www.fdsys.gov.



Sec. 55.6  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 55.7  Additional requirements.

    The Commission may, by rule, regulation, or order, impose upon any 
licensee such requirements, in addition to those established in the 
regulations in this part, as it deems appropriate or necessary to 
protect health and to minimize danger to life or property.



Sec. 55.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0018.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 55.11, 55.25, 55.27, 55.31, 55.35, 55.40, 
55.41, 55.43, 55.45, 55.47, 55.53, 55.57, and 55.59.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. These information collection requirements 
and the control numbers under which they are approved are as follows:
    (1) In Sec. Sec. 55.23, 55.25, 55.27, 55.31, NRC Form 396 is 
approved under control number 3150-0024.
    (2) In Sec. Sec. 55.31, 55.35, 55.47, and 55.57, NRC Form 398 is 
approved under control number 3150-0090.

[62 FR 52188, Oct. 6, 1997, as amended at 64 FR 19878, Apr. 23, 1999; 66 
FR 52667, Oct. 17, 2001; 67 FR 67100, Nov. 4, 2002]



Sec. 55.9  Completeness and accuracy of information.

    Information provided to the Commission by an applicant for a license 
or by a licensee or information required by statute or by the 
Commission's regulations, orders, or license conditions to be maintained 
by the applicant or the licensee shall be complete and accurate in all 
material respects.

[52 FR 49372, Dec. 31, 1987]



                          Subpart B_Exemptions



Sec. 55.11  Specific exemptions.

    The Commission may, upon application by an interested person, or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
will not endanger life or property and are otherwise in the public 
interest.



Sec. 55.13  General exemptions.

    The regulations in this part do not require a license for an 
individual who--
    (a) Under the direction and in the presence of a licensed operator 
or senior operator, manipulates the controls of--
    (1) A research or training reactor as part of the individual's 
training as a student, or
    (2) A facility as a part of the individual's training in a facility 
licensee's training program as approved by the Commission to qualify for 
an operator license under this part.
    (b) Under the direction and in the presence of a licensed senior 
operator, manipulates the controls of a facility to load or unload the 
fuel into, out of, or within the reactor vessel.

[[Page 162]]



                     Subpart C_Medical Requirements



Sec. 55.21  Medical examination.

    An applicant for a license shall have a medical examination by a 
physician. A licensee shall have a medical examination by a physician 
every two years. The physician shall determine that the applicant or 
licensee meets the requirements of Sec. 55.33(a)(1).



Sec. 55.23  Certification.

    To certify the medical fitness of the applicant, an authorized 
representative of the facility licensee shall complete and sign NRC Form 
396, ``Certification of Medical Examination by Facility Licensee,'' 
which can be obtained by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, 
by calling (301) 415-7232, or by visiting the NRC's Web site at http://
www.nrc.gov and selecting forms from the index found on the home page.
    (a) Form NRC-396 must certify that a physician has conducted the 
medical examination of the applicant as required in Sec. 55.21.
    (b) When the certification requests a conditional license based on 
medical evidence, the medical evidence must be submitted on NRC Form 396 
to the Commission and the Commission then makes a determination in 
accordance with Sec. 55.33.

[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 43421, Oct. 27, 1988; 68 
FR 58813, Oct. 10, 2003; 73 FR 30458, May 28, 2008]



Sec. 55.25  Incapacitation because of disability or illness.

    If, during the term of the license, the licensee develops a 
permanent physical or mental condition that causes the licensee to fail 
to meet the requirements of Sec. 55.21 of this part, the facility 
licensee shall notify the Commission, within 30 days of learning of the 
diagnosis, in accordance with Sec. 50.74(c). For conditions for which a 
conditional license (as described in Sec. 55.33(b) of this part) is 
requested, the facility licensee shall provide medical certification on 
Form NRC 396 to the Commission (as described in Sec. 55.23 of this 
part).

[60 FR 13617, Mar. 14, 1995]



Sec. 55.27  Documentation.

    The facility licensee shall document and maintain the results of 
medical qualifications data, test results, and each operator's or senior 
operator's medical history for the current license period and provide 
the documentation to the Commission upon request. The facility licensee 
shall retain this documentation while an individual performs the 
functions of an operator or senior operator.



                         Subpart D_Applications



Sec. 55.31  How to apply.

    (a) The applicant shall:
    (1) Complete NRC Form 398, ``Personal Qualification Statement--
Licensee,'' which can be obtained by writing the Office of the Chief 
Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, by calling (301) 415-7232, or by visiting the NRC's Web site 
at http://www.nrc.gov and selecting forms from the index found on the 
home page;
    (2) File an original of NRC Form 398, together with the information 
required in paragraphs (a)(3), (4), (5) and (6) of this section, with 
the appropriate Regional Administrator;
    (3) Submit a written request from an authorized representative of 
the facility licensee by which the applicant will be employed that the 
written examination and operating test be administered to the applicant;
    (4) Provide evidence that the applicant has successfully completed 
the facility licensee's requirements to be licensed as an operator or 
senior operator and of the facility licensee's need for an operator or a 
senior operator to perform assigned duties. An authorized representative 
of the facility licensee shall certify this evidence on Form NRC-398. 
This certification must include details of the applicant's 
qualifications, and details on courses of instruction administered by 
the facility licensee, and describe the nature of the training received 
at the facility, and the startup and shutdown experience received. In 
lieu of these details, the Commission may accept certification that the 
applicant has successfully completed a Commission-approved

[[Page 163]]

training program that is based on a systems approach to training and 
that uses a simulation facility acceptable to the Commission under Sec. 
55.45(b) of this part;
    (5) Provide evidence that the applicant, as a trainee, has 
successfully manipulated the controls of either the facility for which a 
license is sought or a plant-referenced simulator that meets the 
requirements of Sec. 55.46(c). At a minimum, five significant control 
manipulations must be performed that affect reactivity or power level. 
Control manipulations performed on the plant-referenced simulator may be 
chosen from a representative sampling of the control manipulations and 
plant evolutions described in Sec. 55.59(c)(3)(i)(A-F), (R), (T), (W), 
and (X) of this part, as applicable to the design of the plant for which 
the license application is submitted. For licensed operators applying 
for a senior operator license, certification that the operator has 
successfully operated the controls of the facility as a licensed 
operator shall be accepted; and
    (6) Provide certification by the facility licensee of medical 
condition and general health on Form NRC-396, to comply with Sec. Sec. 
55.21, 55.23 and 55.33(a)(1).
    (b) The Commission may at any time after the application has been 
filed, and before the license has expired, require futher information 
under oath or affirmation in order to enable it to determine whether to 
grant or deny the application or whether to revoke, modify, or suspend 
the license.
    (c) An applicant whose application has been denied because of a 
medical condition or general health may submit a further medical report 
at any time as a supplement to the application.
    (d) Each application and statement must contain complete and 
accurate disclosure as to all matters required to be disclosed. The 
applicant shall sign statements required by paragraphs (a) (1) and (2) 
of this section.

[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 43421, Oct. 27, 1988; 66 
FR 52667, Oct. 17, 2001; 68 FR 58813, Oct. 10, 2003; 73 FR 30458, May 
28, 2008]



Sec. 55.33  Disposition of an initial application.

    (a) Requirements for the approval of an initial application. The 
Commission will approve an initial application for a license pursuant to 
the regulations in this part, if it finds that--
    (1) Health. The applicants medical condition and general health will 
not adversely affect the performance of assigned operator job duties or 
cause operational errors endangering public health and safety. The 
Commission will base its finding upon the certification by the facility 
licensee as detailed in Sec. 55.23.
    (2) Written examination and operating test. The applicant has passed 
the requisite written examination and operating test in accordance with 
Sec. Sec. 55.41 and 55.45 or 55.43 and 55.45. These examinations and 
tests determine whether the applicant for an operator's license has 
learned to operate a facility competently and safely, and additionally, 
in the case of a senior operator, whether the applicant has learned to 
direct the licensed activities of licensed operators competently and 
safely.
    (b) Conditional license. If an applicant's general medical condition 
does not meet the minimum standards under Sec. 55.33(a)(1) of this 
part, the Commission may approve the application and include conditions 
in the license to accommodate the medical defect. The Commission will 
consider the recommendations and supporting evidence of the facility 
licensee and of the examining physician (provided on Form NRC-396) in 
arriving at its decision.



Sec. 55.35  Re-applications.

    (a) An applicant whose application for a license has been denied 
because of failure to pass the written examination or operating test, or 
both, may file a new application two months after the date of denial. 
The application must be submitted on Form NRC-398 and include a 
statement signed by an authorized representative of the facility 
licensee by whom the applicant will be employed that states in detail 
the extent of the applicant's additional training since the denial and 
certifies that

[[Page 164]]

the applicant is ready for re-examination. An applicant may file a third 
application six months after the date of denial of the second 
application, and may file further successive applications two years 
after the date of denial of each prior application. The applicant shall 
submit each successive application on Form NRC-398 and include a 
statement of additional training.
    (b) An applicant who has passed either the written examination or 
operating test and failed the other may request in a new application on 
Form NRC-398 to be excused from re-examination on the portions of the 
examination or test which the applicant has passed. The Commission may 
in its discretion grant the request, if it determines that sufficient 
justification is presented.



           Subpart E_Written Examinations and Operating Tests



Sec. 55.40  Implementation.

    (a) The Commission shall use the criteria in NUREG-1021, ``Operator 
Licensing Examination Standards for Power Reactors,'' \1\ in effect six 
months before the examination date to prepare the written examinations 
required by Sec. Sec. 55.41 and 55.43 and the operating tests required 
by Sec. 55.45. The Commission shall also use the criteria in NUREG-1021 
to evaluate the written examinations and operating tests prepared by 
power reactor facility licensees pursuant to paragraph (b) of this 
section.
---------------------------------------------------------------------------

    \1\ Copies of NUREGs may be purchased from the Superintendent of 
Documents, U.S. Government Publishing Office, P.O. Box 38082, 
Washington, DC 20402-9328. Copies are also available from the National 
Technical Information Service, 5301 Shawnee Road, Alexandria, VA 22312. 
A copy is available for inspection and/or copying in the NRC Public 
Document Room, One White Flint North, 11555 Rockville Pike (O-1 F21), 
Rockville, MD.
---------------------------------------------------------------------------

    (b) Power reactor facility licensees may prepare, proctor, and grade 
the written examinations required by Sec. Sec. 55.41 and 55.43 and may 
prepare the operating tests required by Sec. 55.45, subject to the 
following conditions:
    (1) Power reactor facility licensees shall prepare the required 
examinations and tests in accordance with the criteria in NUREG-1021 as 
described in paragraph (a) of this section;
    (2) Pursuant to Sec. 55.49, power reactor facility licensees shall 
establish, implement, and maintain procedures to control examination 
security and integrity;
    (3) An authorized representative of the power reactor facility 
licensee shall approve the required examinations and tests before they 
are submitted to the Commission for review and approval; and
    (4) Power reactor facility licensees must receive Commission 
approval of their proposed written examinations and operating tests.
    (c) In lieu of paragraph (b) of this section and upon written 
request from a power reactor facility licensee pursuant to Sec. 
55.31(a)(3), the Commission shall, for that facility licensee, prepare, 
proctor, and grade, the written examinations required by Sec. Sec. 
55.41 and 55.43 and the operating tests required by Sec. 55.45. In 
addition, the Commission may exercise its discretion and reject a power 
reactor facility licensee's determination to elect paragraph (b) of this 
section, in which case the Commission shall prepare, proctor, and grade 
the required written examinations and operating tests for that facility 
licensee.
    (d) The Commission shall use the criteria in NUREG-1478, ``Operator 
Licensing Examiner Standards for Research and Test Reactors,'' for all 
test and research reactors to prepare, proctor, and grade the written 
examinations required by Sec. Sec. 55.41 and 55.43 and the operating 
tests required by Sec. 55.45 for non-power reactor facility licensees.

[64 FR 19878, Apr. 23, 1999, as amended at 69 FR 76600, Dec. 22, 2004; 
79 FR 66604, Nov. 10, 2014; 80 FR 45844, Aug. 3, 2015; 80 FR 74980, Dec. 
1, 2015]



Sec. 55.41  Written examination: Operators.

    (a) Content. The written examination for an operator will contain a 
representative selection of questions on the knowledge, skills, and 
abilities needed to perform licensed operator duties. The knowledge, 
skills, and abilities will be identified, in part, from learning 
objectives derived from a

[[Page 165]]

systematic analysis of licensed operator duties performed by each 
facility licensee and contained in its training program and from 
information in the Final Safety Analysis Report, system description 
manuals and operating procedures, facility license and license 
amendments, Licensee Event Reports, and other materials requested from 
the facility licensee by the Commission.
    (b) The written examination for an operator for a facility will 
include a representative sample from among the following 14 items, to 
the extent applicable to the facility.
    (1) Fundamentals of reactor theory, including fission process, 
neutron multiplication, source effects, control rod effects, criticality 
indications, reactivity coefficients, and poison effects.
    (2) General design features of the core, including core structure, 
fuel elements, control rods, core instrumentation, and coolant flow.
    (3) Mechanical components and design features of the reactor primary 
system.
    (4) Secondary coolant and auxiliary systems that affect the 
facility.
    (5) Facility operating characteristics during steady state and 
transient conditions, including coolant chemistry, causes and effects of 
temperature, pressure and reactivity changes, effects of load changes, 
and operating limitations and reasons for these operating 
characteristics.
    (6) Design, components, and functions of reactivity control 
mechanisms and instrumentation.
    (7) Design, components, and functions of control and safety systems, 
including instrumentation, signals, interlocks, failure modes, and 
automatic and manual features.
    (8) Components, capacity, and functions of emergency systems.
    (9) Shielding, isolation, and containment design features, including 
access limitations.
    (10) Administrative, normal, abnormal, and emergency operating 
procedures for the facility.
    (11) Purpose and operation of radiation monitoring systems, 
including alarms and survey equipment.
    (12) Radiological safety principles and procedures.
    (13) Procedures and equipment available for handling and disposal of 
radioactive materials and effluents.
    (14) Principles of heat transfer thermodynamics and fluid mechanics.



Sec. 55.43  Written examination: Senior operators.

    (a) Content. The written examination for a senior operator will 
contain a representative selection of questions on the knowledge, 
skills, and abilities needed to perform licensed senior operator duties. 
The knowledge, skills, and abilities will be identified, in part, from 
learning objectives derived from a systematic analysis of licensed 
senior operator duties performed by each facility licensee and contained 
in its training program and from information in the Final Safety 
Analysis Report, system description manuals and operating procedures, 
facility license and license amendments, Licensee Event Reports, and 
other materials requested from the facility licensee by the Commission.
    (b) The written examination for a senior operator for a facility 
will include a representative sample from among the following seven 
items and the 14 items specified in Sec. 55.41 of this part, to the 
extent applicable to the facility:
    (1) Conditions and limitations in the facility license.
    (2) Facility operating limitations in the technical specifications 
and their bases.
    (3) Facility licensee procedures required to obtain authority for 
design and operating changes in the facility.
    (4) Radiation hazards that may arise during normal and abnormal 
situations, including maintenance activities and various contamination 
conditions.
    (5) Assessment of facility conditions and selection of appropriate 
procedures during normal, abnormal, and emergency situations.
    (6) Procedures and limitations involved in initial core loading, 
alterations in core configuration, control rod programming, and 
determination of various internal and external effects on core 
reactivity.
    (7) Fuel handling facilities and procedures.

[[Page 166]]



Sec. 55.45  Operating tests.

    (a) Content. The operating tests administered to applicants for 
operator and senior operator licenses in accordance with paragraph 
(b)(1) of this section are generally similar in scope. The content will 
be identified, in part, from learning objectives derived from a 
systematic analysis of licensed operator or senior operator duties 
performed by each facility licensee and contained in its training 
program and from information in the Final Safety Analysis Report, system 
description manuals and operating procedures, facility license and 
license amendments, Licensee Event Reports, and other materials 
requested from the facility licensee by the Commission. The operating 
test, to the extent applicable, requires the applicant to demonstrate an 
understanding of and the ability to perform the actions necessary to 
accomplish a representative sample from among the following 13 items.
    (1) Perform pre-startup procedures for the facility, including 
operating of those controls associated with plant equipment that could 
affect reactivity.
    (2) Manipulate the console controls as required to operate the 
facility between shutdown and designated power levels.
    (3) Identify annunciators and condition-indicating signals and 
perform appropriate remedial actions where appropriate.
    (4) Identify the instrumentation systems and the significance of 
facility instrument readings.
    (5) Observe and safely control the operating behavior 
characteristics of the facility.
    (6) Perform control manipulations required to obtain desired 
operating results during normal, abnormal, and emergency situations.
    (7) Safely operate the facility's heat removal systems, including 
primary coolant, emergency coolant, and decay heat removal systems, and 
identify the relations of the proper operation of these systems to the 
operation of the facility.
    (8) Safely operate the facility's auxiliary and emergency systems, 
including operation of those controls associated with plant equipment 
that could affect reactivity or the release of radioactive materials to 
the environment.
    (9) Demonstrate or describe the use and function of the facility's 
radiation monitoring systems, including fixed radiation monitors and 
alarms, portable survey instruments, and personnel monitoring equipment.
    (10) Demonstrate knowledge of significant radiation hazards, 
including permissible levels in excess of those authorized, and ability 
to perform other procedures to reduce excessive levels of radiation and 
to guard against personnel exposure.
    (11) Demonstrate knowledge of the emergency plan for the facility, 
including, as appropriate, the operator's or senior operator's 
responsibility to decide whether the plan should be executed and the 
duties under the plan assigned.
    (12) Demonstrate the knowledge and ability as appropriate to the 
assigned position to assume the responsibilities associated with the 
safe operation of the facility.
    (13) Demonstrate the applicant's ability to function within the 
control room team as appropriate to the assigned position, in such a way 
that the facility licensee's procedures are adhered to and that the 
limitations in its license and amendments are not violated.
    (b) Implementation--Administration. The operating test will be 
administered in a plant walkthrough and in either--
    (1) A simulation facility that the Commission has approved for use 
after application has been made by the facility licensee under Sec. 
55.46(b);
    (2) A plant-referenced simulator (Sec. 55.46(c)); or
    (3) The plant, if approved for use in the administration of the 
operating test by the Commission under Sec. 55.46(b).

[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 43421, Oct. 27, 1988; 62 
FR 59276, Nov. 3, 1997; 66 FR 52667, Oct. 17, 2001]



Sec. 55.46  Simulation facilities.

    (a) General. This section addresses the use of a simulation facility 
for the administration of the operating test and plant-referenced 
simulators to meet experience requirements for applicants for operator 
and senior operator licenses.

[[Page 167]]

    (b) Commission-approved simulation facilities and Commission 
approval of use of the plant in the administration of the operating 
test. (1) Facility licensees that propose to use a simulation facility, 
other than a plant-referenced simulator, or the plant in the 
administration of the operating test under Sec. Sec. 55.45(b)(1) or 
55.45(b)(3), shall request approval from the Commission. This request 
must include:
    (i) A description of the components of the simulation facility 
intended to be used, or the way the plant would be used for each part of 
the operating test, unless previously approved; and
    (ii) A description of the performance tests for the simulation 
facility as part of the request, and the results of these tests; and
    (iii) A description of the procedures for maintaining examination 
and test integrity consistent with the requirements of Sec. 55.49.
    (2) The Commission will approve a simulation facility or use of the 
plant for administration of operating tests if it finds that the 
simulation facility and its proposed use, or the proposed use of the 
plant, are suitable for the conduct of operating tests for the facility 
licensee's reference plant under Sec. 55.45(a).
    (c) Plant-referenced simulators. (1) A plant-referenced simulator 
used for the administration of the operating test or to meet experience 
requirements in Sec. 55.31(a)(5) must demonstrate expected plant 
response to operator input and to normal, transient, and accident 
conditions to which the simulator has been designed to respond. The 
plant-referenced simulator must be designed and implemented so that it:
    (i) Is sufficient in scope and fidelity to allow conduct of the 
evolutions listed in Sec. Sec. 55.45(a)(1) through (13), and 
55.59(c)(3)(i)(A) through (AA), as applicable to the design of the 
reference plant.
    (ii) Allows for the completion of control manipulations for operator 
license applicants.
    (2) Facility licensees that propose to use a plant-referenced 
simulator to meet the control manipulation requirements in Sec. 
55.31(a)(5) must ensure that:
    (i) The plant-referenced simulator utilizes models relating to 
nuclear and thermal-hydraulic characteristics that replicate the most 
recent core load in the nuclear power reference plant for which a 
license is being sought; and
    (ii) Simulator fidelity has been demonstrated so that significant 
control manipulations are completed without procedural exceptions, 
simulator performance exceptions, or deviation from the approved 
training scenario sequence.
    (3) A simulation facility consisting solely of a plant-referenced 
simulator must meet the requirements of paragraph (c)(1) of this section 
and the criteria in paragraphs (d)(1) and (4) of this section for the 
Commission to accept the plant-referenced simulator for conducting 
operating tests as described in Sec. 55.45(a) of this part, 
requalification training as described in Sec. 55.59(c)(3) of this part, 
or for performing control manipulations that affect reactivity to 
establish eligibility for an operator's license as described in Sec. 
55.31(a)(5).
    (d) Continued assurance of simulator fidelity. Facility licensees 
that maintain a simulation facility shall:
    (1) Conduct performance testing throughout the life of the 
simulation facility in a manner sufficient to ensure that paragraphs 
(c)(2)(ii), as applicable, and (d)(3) of this section are met. The 
results of performance tests must be retained for four years after the 
completion of each performance test or until superseded by updated test 
results;
    (2) Correct modeling and hardware discrepancies and discrepancies 
identified from scenario validation and from performance testing;
    (3) Make results of any uncorrected performance test failures that 
may exist at the time of the operating test or requalification program 
inspection available for NRC review, prior to or concurrent with 
preparations for each operating test or requalification program 
inspection; and
    (4) Maintain the provisions for license application, examination, 
and test integrity consistent with Sec. 55.49.

[66 FR 52667, Oct. 17, 2001]

[[Page 168]]



Sec. 55.47  Waiver of examination and test requirements.

    (a) On application, the Commission may waive any or all of the 
requirements for a written examination and operating test, if it finds 
that the applicant--
    (1) Has had extensive actual operating experience at a comparable 
facility, as determined by the Commission, within two years before the 
date of application;
    (2) Has discharged his or her responsibilities competently and 
safely and is capable of continuing to do so; and
    (3) Has learned the operating procedures for and is qualified to 
operate competently and safely the facility designated in the 
application.
    (b) The Commission may accept as proof of the applicant's past 
performance a certification of an authorized representative of the 
facility licensee or of a holder of an authorization by which the 
applicant was previously employed. The certification must contain a 
description of the applicant's operating experience, including an 
approximate number of hours the applicant operated the controls of the 
facility, the duties performed, and the extent of the applicant's 
responsibility.
    (c) The Commission may accept as proof of the applicant's current 
qualifications a certification of an authorized representative of the 
facility licensee or of a holder of an authorization where the 
applicant's services will be utilized.



Sec. 55.49  Integrity of examinations and tests.

    Applicants, licensees, and facility licensees shall not engage in 
any activity that compromises the integrity of any application, test, or 
examination required by this part. The integrity of a test or 
examination is considered compromised if any activity, regardless of 
intent, affected, or, but for detection, would have affected the 
equitable and consistent administration of the test or examination. This 
includes activities related to the preparation and certification of 
license applications and all activities related to the preparation, 
administration, and grading of the tests and examinations required by 
this part.

[64 FR 19878, Apr. 23, 1999]



                           Subpart F_Licenses



Sec. 55.51  Issuance of licenses.

    Operator and senior operator licenses. If the Commission determines 
that an applicant for an operator license or a senior operator license 
meets the requirements of the Act and its regulations, it will issue a 
license in the form and containing any conditions and limitations it 
considers appropriate and necessary.



Sec. 55.53  Conditions of licenses.

    Each license contains and is subject to the following conditions 
whether stated in the license or not:
    (a) Neither the license nor any right under the license may be 
assigned or otherwise transferred.
    (b) The license is limited to the facility for which it is issued.
    (c) The license is limited to those controls of the facility 
specified in the license.
    (d) The license is subject to, and the licensee shall observe, all 
applicable rules, regulations, and orders of the Commission.
    (e) If a licensee has not been actively performing the functions of 
an operator or senior operator, the licensee may not resume activities 
authorized by a license issued under this part except as permitted by 
paragraph (f) of this section. To maintain active status, the licensee 
shall actively perform the functions of an operator or senior operator 
on a minimum of seven 8-hour or five 12-hour shifts per calendar 
quarter. For test and research reactors, the licensee shall actively 
perform the functions of an operator or senior operator for a minimum of 
four hours per calendar quarter.
    (f) If paragraph (e) of this section is not met, before resumption 
of functions authorized by a license issued under this part, an 
authorized representative of the facility licensee shall certify the 
following:
    (1) That the qualifications and status of the licensee are current 
and valid; and

[[Page 169]]

    (2) That the licensee has completed a minimum of 40 hours of shift 
functions under the direction of an operator or senior operator as 
appropriate and in the position to which the individual will be 
assigned. The 40 hours must have included a complete tour of the plant 
and all required shift turnover procedures. For senior operators limited 
to fuel handling under paragraph (c) of this section, one shift must 
have been completed. For test and research reactors, a minimum of six 
hours must have been completed.
    (g) The licensee shall notify the Commission within 30 days about a 
conviction for a felony.
    (h) The licensee shall complete a requalification program as 
described by Sec. 55.59.
    (i) The licensee shall have a biennial medical examination.
    (j) The licensee shall not consume or ingest alcoholic beverages 
within the protected area of power reactors, or the controlled access 
area of non-power reactors. The licensee shall not use, possess, or sell 
any illegal drugs. The licensee shall not perform activities authorized 
by a license issued under this part while under the influence of alcohol 
or any prescription, over-the-counter, or illegal substance that could 
adversely affect his or her ability to safely and competently perform 
his or her licensed duties. For the purpose of this paragraph, with 
respect to alcoholic beverages and drugs, the term ``under the 
influence'' means the licensee exceeded, as evidenced by a confirmed 
test result, the lower of the cutoff levels for drugs or alcohol 
contained in subparts E, F, and G of part 26 of this chapter, or as 
established by the facility licensee. The term ``under the influence'' 
also means the licensee could be mentally or physically impaired as a 
result of substance use including prescription and over-the-counter 
drugs, as determined under the provisions, policies, and procedures 
established by the facility licensee for its fitness-for-duty program, 
in such a manner as to adversely affect his or her ability to safely and 
competently perform licensed duties.
    (k) Each licensee at power reactors shall participate in the drug 
and alcohol testing programs established pursuant to 10 CFR part 26. 
Each licensee at non-power reactors shall participate in any drug and 
alcohol testing program that may be established for that non-power 
facility.
    (l) The licensee shall comply with any other conditions that the 
Commission may impose to protect health or to minimize danger to life or 
property.

[52 FR 9460, Mar. 25, 1987, as amended at 56 FR 32070, July 15, 1991; 74 
FR 45545, Sept. 3, 2009; 79 FR 66604, Nov. 10, 2014]



Sec. 55.55  Expiration.

    (a) Each operator license and senior operator license expires six 
years after the date of issuance, upon termination of employment with 
the facility licensee, or upon determination by the facility licensee 
that the licensed individual no longer needs to maintain a license.
    (b) If a licensee files an application for renewal or an upgrade of 
an existing license on Form NRC-398 at least 30 days before the 
expiration of the existing license, it does not expire until disposition 
of the application for renewal or for an upgraded license has been 
finally determined by the Commission. Filing by mail will be deemed to 
be complete at the time the application is deposited in the mail.

[52 FR 9460, Mar. 25, 1987, as amended at 79 FR 66605, Nov. 10, 2014]



Sec. 55.57  Renewal of licenses.

    (a) The applicant for renewal of a license shall--
    (1) Complete and sign Form NRC-398 and include the number of the 
license for which renewal is sought.
    (2) File an original of NRC Form 398 with the appropriate Regional 
Administrator specified in Sec. 55.5(b).
    (3) Provide written evidence of the applicant's experience under the 
existing license and the approximate number of hours that the licensee 
has operated the facility.
    (4) Provide a statement by an authorized representative of the 
facility licensee that during the effective term of the current license 
the applicant has satisfactorily completed the requalification program 
for the facility for which operator or senior operator license renewal 
is sought.

[[Page 170]]

    (5) Provide evidence that the applicant has discharged the license 
responsibilities competently and safely. The Commission may accept as 
evidence of the applicant's having met this requirement a certificate of 
an authorized representative of the facility licensee or holder of an 
authorization by which the licensee has been employed.
    (6) Provide certification by the facility licensee of medical 
condition and general health on Form NRC-396, to comply with Sec. Sec. 
55.21, 55.23 and 55.27.
    (b) The license will be renewed if the Commission finds that--
    (1) The medical condition and the general health of the licensee 
continue to be such as not to cause operational errors that endanger 
public health and safety. The Commission will base this finding upon the 
certification by the facility licensee as described in Sec. 55.23.
    (2) The licensee--
    (i) Is capable of continuing to competently and safely assume 
licensed duties;
    (ii) Has successfully completed a requalification program that has 
been approved by the Commission as required by Sec. 55.59; and
    (iii) Has passed the requalification examinations and annual 
operating tests as required by Sec. 55.59.
    (3) There is a continued need for a licensee to operate or for a 
senior operator to direct operators at the facility designated in the 
application.
    (4) The past performance of the licensee has been satisfactory to 
the Commission. In making its finding, the Commission will include in 
its evaluation information such as notices of violations or letters of 
reprimand in the licensee's docket.

[52 FR 9460, Mar. 25, 1987, as amended at 59 FR 5938, Feb. 9, 1994; 68 
FR 58813, Oct. 10, 2003]



Sec. 55.59  Requalification.

    (a) Requalification requirements. Each licensee shall--
    (1) Successfully complete a requalification program developed by the 
facility licensee that has been approved by the Commission. This program 
shall be conducted for a continuous period not to exceed 24 months in 
duration.
    (2) Pass a comprehensive requalification written examination and an 
annual operating test.
    (i) The written examination will sample the items specified in 
Sec. Sec. 55.41 and 55.43 of this part, to the extent applicable to the 
facility, the licensee, and any limitation of the license under Sec. 
55.53(c) of this part.
    (ii) The operating test will require the operator or senior operator 
to demonstrate an understanding of and the ability to perform the 
actions necessary to accomplish a comprehensive sample of items 
specified in Sec. 55.45(a) (2) through (13) inclusive to the extent 
applicable to the facility.
    (iii) In lieu of the Commission accepting a certification by the 
facility licensee that the licensee has passed written examinations and 
operating tests administered by the facility licensee within its 
Commission-approved program developed by using a systems approach to 
training under paragraph (c) of this section, the Commission may 
administer a comprehensive requalification written examination and an 
annual operating test.
    (b) Additional training. If the requirements of paragraphs (a) (1) 
and (2) of this section are not met, the Commission may require the 
licensee to complete additional training and to submit evidence to the 
Commission of successful completion of this training before returning to 
licensed duties.
    (c) Requalification program requirements. A facility licensee shall 
have a requalification program reviewed and approved by the Commission 
and shall, upon request consistent with the Commission's inspection 
program needs, submit to the Commission a copy of its comprehensive 
requalification written examinations or annual operating tests. The 
requalification program must meet the requirements of paragraphs (c) (1) 
through (7) of this section. In lieu of paragraphs (c) (2), (3), and (4) 
of this section, the Commission may approve a program developed by using 
a systems approach to training.
    (1) Schedule. The requalification program must be conducted for a 
continuous period not to exceed two years, and upon conclusion must be 
promptly followed, pursuant to a continuous

[[Page 171]]

schedule, by successive requalification programs.
    (2) Lectures. The requalification program must include preplanned 
lectures on a regular and continuing basis throughout the license period 
in those areas where operator and senior operator written examinations 
and facility operating experience indicate that emphasis in scope and 
depth of coverage is needed in the following subjects:
    (i) Theory and principles of operation.
    (ii) General and specific plant operating characteristics.
    (iii) Plant instrumentation and control systems.
    (iv) Plant protection systems.
    (v) Engineered safety systems.
    (vi) Normal, abnormal, and emergency operating procedures.
    (vii) Radiation control and safety.
    (viii) Technical specifications.
    (ix) Applicable portions of title 10, chapter I, Code of Federal 
Regulations.
    (3) On-the-job training. The requalification program must include 
on-the-job training so that--
    (i) Each licensed operator of a utilization facility manipulates the 
plant controls and each licensed senior operator either manipulates the 
controls or directs the activities of individuals during plant control 
manipulations during the term of the licensed operator's or senior 
operator's license. For reactor operators and senior operators, these 
manipulations must consist of the following control manipulations and 
plant evolutions if they are applicable to the plant design. Items 
described in paragraphs (c)(3)(i) (A) through (L) of this section must 
be performed annually; all other items must be performed on a two-year 
cycle. However, the requalification programs must contain a commitment 
that each individual shall perform or participate in a combination of 
reactivity control manipulations based on the availability of plant 
equipment and systems. Those control manipulations which are not 
performed at the plant may be performed on a simulator. The use of the 
Technical Specifications should be maximized during the simulator 
control manipulations. Senior operator licensees are credited with these 
activities if they direct control manipulations as they are performed.
    (A) Plant or reactor startups to include a range that reactivity 
feedback from nuclear heat addition is noticeable and heatup rate is 
established.
    (B) Plant shutdown.
    (C) Manual control of steam generators or feedwater or both during 
startup and shutdown.
    (D) Boration or dilution during power operation.
    (E) Significant (=10 percent) power changes in manual rod 
control or recirculation flow.
    (F) Reactor power change of 10 percent or greater where load change 
is performed with load limit control or where flux, temperature, or 
speed control is on manual (for HTGR).
    (G) Loss of coolant, including--
    (1) Significant PWR steam generator leaks
    (2) Inside and outside primary containment
    (3) Large and small, including leak-rate determination
    (4) Saturated reactor coolant response (PWR).
    (H) Loss of instrument air (if simulated plant specific).
    (I) Loss of electrical power (or degraded power sources).
    (J) Loss of core coolant flow/natural circulation.
    (K) Loss of feedwater (normal and emergency).
    (L) Loss of service water, if required for safety.
    (M) Loss of shutdown cooling.
    (N) Loss of component cooling system or cooling to an individual 
component.
    (O) Loss of normal feedwater or normal feedwater system failure.
    (P) Loss of condenser vacuum.
    (Q) Loss of protective system channel.
    (R) Mispositioned control rod or rods (or rod drops).
    (S) Inability to drive control rods.
    (T) Conditions requiring use of emergency boration or standby liquid 
control system.
    (U) Fuel cladding failure or high activity in reactor coolant or 
offgas.
    (V) Turbine or generator trip.
    (W) Malfunction of an automatic control system that affects 
reactivity.

[[Page 172]]

    (X) Malfunction of reactor coolant pressure/volume control system.
    (Y) Reactor trip.
    (Z) Main steam line break (inside or outside containment).
    (AA) A nuclear instrumentation failure.
    (ii) Each licensed operator and senior operator has demonstrated 
satisfactory understanding of the operation of the apparatus and 
mechanisms associated with the control manipulations in paragraph 
(c)(3)(i) of this section, and knows the operating procedures in each 
area for which the operator or senior operator is licensed.
    (iii) Each licensed operator and senior operator is cognizant of 
facility design changes, procedure changes, and facility license 
changes.
    (iv) Each licensed operator and senior operator reviews the contents 
of all abnormal and emergency procedures on a regularly scheduled basis.
    (v) A simulator may be used in meeting the requirements of 
paragraphs (c) (3)(i) and (3)(ii) of this section, if it reproduces the 
general operating characteristics of the facility involved and the 
arrangement of the instrumentation and controls of the simulator is 
similar to that of the facility involved. If the simulator or simulation 
device is used to administer operating tests for a facility, as provided 
in Sec. 55.45(b)(1), the device approved to meet the requirements of 
Sec. 55.45(b)(1) must be used for credit to be given for meeting the 
requirements of paragraphs (c)(3)(i) (G through AA) of this section.
    (4) Evaluation. The requalification program must include--
    (i) Comprehensive requalification written examinations and annual 
operating tests which determine areas in which retraining is needed to 
upgrade licensed operator and senior operator knowledge.
    (ii) Written examinations which determine licensed operators' and 
senior operators' knowledge of subjects covered in the requalification 
program and provide a basis for evaluating their knowledge of abnormal 
and emergency procedures.
    (iii) Systematic observation and evaluation of the performance and 
competency of licensed operators and senior operators by supervisors 
and/or training staff members, including evaluation of actions taken or 
to be taken during actual or simulated abnormal and emergency 
procedures.
    (iv) Simulation of emergency or abnormal conditions that may be 
accomplished by using the control panel of the facility involved or by 
using a simulator. When the control panel of the facility is used for 
simulation, the actions taken or to be taken for the emergency or 
abnormal condition shall be discussed; actual manipulation of the plant 
controls is not required. If a simulator is used in meeting the 
requirements of paragraph (c)(4)(iii) of this section, it must 
accurately reproduce the operating characteristics of the facility 
involved and the arrangement of the instrumentation and controls of the 
simulator must closely parallel that of the facility involved. After the 
provisions of Sec. 55.46 have been implemented at a facility, the 
Commission approved or plant-referenced simulator must be used to comply 
with this paragraph.
    (v) Provisions for each licensed operator and senior operator to 
participate in an accelerated requalification program where performance 
evaluations conducted pursuant to paragraphs (c)(4) (i) through (iv) of 
this section clearly indicated the need.
    (5) Records. The requalification program documentation must include 
the following:
    (i) The facility licensee shall maintain records documenting the 
participation of each licensed operator and senior operator in the 
requalification program. The records must contain copies of written 
examinations administered, the answers given by the licensee, and the 
results of evaluations and documentation of operating tests and of any 
additional training administered in areas in which an operator or senior 
operator has exhibited deficiencies. The facility licensee shall retain 
these records until the operator's or senior operator's license is 
renewed.
    (ii) Each record required by this part must be legible throughout 
the retention period specified by each Commission regulation. The record 
may be the original or a reproduced copy or a microform provided that 
the copy or

[[Page 173]]

microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period.
    (iii) If there is a conflict between the Commission's regulations in 
this part, and any license condition, or other written Commission 
approval or authorization pertaining to the retention period for the 
same type of record, the retention period specified for these records by 
the regulations in this part apply unless the Commission, pursuant to 
Sec. 55.11, grants a specific exemption from this record retention 
requirement.
    (6) Alternative training programs. The requirements of this section 
may be met by requalification programs conducted by persons other than 
the facility licensee if the requalification programs are similar to the 
program described in paragraphs (c) (1) through (5) of this section and 
the alternative program has been approved by the Commission.
    (7) Applicability to research and test reactor facilities. To 
accommodate specialized modes of operation and differences in control, 
equipment, and operator skills and knowledge, the requalification 
program for each licensed operator and senior operator of a research 
reactor or test reactor facility must conform generally but need not be 
identical to the requalification program outlined in paragraphs (c) (1) 
through (6) of this section. Significant deviations from the 
requirements of paragraphs (c) (1) through (6) of this section will be 
permitted only if supported by written justification and approved by the 
Commission.

[52 FR 9460, Mar. 25, 1987, as amended at 59 FR 5938, Feb. 9, 1994; 66 
FR 52668, Oct. 17, 2001, 81 FR 86909, Dec. 2, 2016]



            Subpart G_Modification and Revocation of Licenses



Sec. 55.61  Modification and revocation of licenses.

    (a) The terms and conditions of all licenses are subject to 
amendment, revision, or modification by reason of rules, regulations, or 
orders issued in accordance with the Act or any amendments thereto.
    (b) Any license may be revoked, suspended, or modified, in whole or 
in part:
    (1) For any material false statement in the application or in any 
statement of fact required under section 182 of the Act,
    (2) Because of conditions revealed by the application or statement 
of fact or any report, record, inspection or other means that would 
warrant the Commission to refuse to grant a license on an original 
application,
    (3) For willful violation of, or failure to observe any of the terms 
and conditions of the Act, or the license, or of any rule, regulation, 
or order of the Commission, or
    (4) For any conduct determined by the Commission to be a hazard to 
safe operation of the facility.
    (5) For the sale, use or possession of illegal drugs, or refusal to 
participate in the facility drug and alcohol testing program, or a 
confirmed positive test for drugs, drug metabolites, or alcohol in 
violation of the conditions and cutoff levels established by Sec. 
55.53(j) or the consumption of alcoholic beverages within the protected 
area of power reactors or the controlled access area of non-power 
reactors, or a determination of unfitness for scheduled work as a result 
of the consumption of alcoholic beverages.

[52 FR 9460, Mar. 25, 1987, as amended at 56 FR 32070, July 15, 1991]



                          Subpart H_Enforcement



Sec. 55.71  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;

[[Page 174]]

    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55076, Nov. 24, 1992]



Sec. 55.73  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy of violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 55 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 55 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 55.1, 55.2, 55.4, 55.5, 55.6, 55.7, 55.8, 55.11. 55.13, 
55.31, 55.33, 55.35, 55.41, 55.43, 55.47, 55.51, 55.55, 55.57, 55.61, 
55.71, and 55.73.

[57 FR 55076, Nov. 24, 1992]



PART 60_DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC 
REPOSITORIES--Table of Contents



                      Subpart A_General Provisions

Sec.
60.1 Purpose and scope.
60.2 Definitions.
60.3 License required.
60.4 Communications and records.
60.5 Interpretations.
60.6 Exemptions.
60.7 License not required for certain preliminary activities.
60.8 Information collection requirements: Approval.
60.9 Employee protection.
60.10 Completeness and accuracy of information.
60.11 Deliberate misconduct.

                           Subpart B_Licenses

                          Preapplication Review

60.15 Site characterization.
60.16 Site characterization plan required.
60.17 Contents of site characterization plan.
60.18 Review of site characterization activities.

                          License Applications

60.21 Content of application.
60.22 Filing and distribution of application.
60.23 Elimination of repetition.
60.24 Updating of application and environmental impact statement.

                       Construction Authorization

60.31 Construction authorization.
60.32 Conditions of construction authorization.
60.33 Amendment of construction authorization.

                     License Issuance and Amendment

60.41 Standards for issuance of a license.
60.42 Conditions of license.
60.43 License specification.
60.44 Changes, tests, and experiments.
60.45 Amendment of license.
60.46 Particular activities requiring license amendment.

                      US/IAEA Safeguards Agreement

60.47 Facility information and verification.

                            Permanent Closure

60.51 License amendment for permanent closure.
60.52 Termination of license.

 Subpart C_Participation by State Governments and Affected Indian Tribes

60.61 Provision of information.
60.62 Site review.
60.63 Participation in license reviews.
60.64 Notice to States.
60.65 Representation.

           Subpart D_Records, Reports, Tests, and Inspections

60.71 Records and reports.
60.72 Construction records.
60.73 Reports of deficiencies.
60.74 Tests.
60.75 Inspections.
60.78 Material control and accounting records and reports.

                      Subpart E_Technical Criteria

60.101 Purpose and nature of findings.
60.102 Concepts.

[[Page 175]]

                         Performance Objectives

60.111 Performance of the geologic repository operations area through 
          permanent closure.
60.112 Overall system performance objective for the geologic repository 
          after permanent closure.
60.113 Performance of particular barriers after permanent closure.

                       Land Ownership and Control

60.121 Requirements for ownership and control interests in land.

                             Siting Criteria

60.122 Siting criteria.

       Design Criteria for the Geologic Repository Operations Area

60.130 General considerations.
60.131 General design criteria for the geologic repository operations 
          area.
60.132 Additional design criteria for surface facilities in the geologic 
          repository operations area.
60.133 Additional design criteria for the underground facility.
60.134 Design of seals for shafts and boreholes.

                  Design Criteria for the Waste Package

60.135 Criteria for the waste package and its components.

                       Preclosure Controlled Area

60.136 Preclosure controlled area.

                  Performance Confirmation Requirements

60.137 General requirements for performance confirmation.

               Subpart F_Performance Confirmation Program

60.140 General requirements.
60.141 Confirmation of geotechnical and design parameters.
60.142 Design testing.
60.143 Monitoring and testing waste packages.

                       Subpart G_Quality Assurance

60.150 Scope.
60.151 Applicability.
60.152 Implementation.

            Subpart H_Training and Certification of Personnel

60.160 General requirements.
60.161 Training and certification program.
60.162 Physical requirements.

Subpart I--Emergency Planning Criteria [Reserved]

                          Subpart J_Violations

60.181 Violations.
60.183 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 51, 53, 62, 63, 65, 81, 
161, 182, 183, 223, 234 (42 U.S.C. 2071, 2073, 2092, 2093, 2095, 2111, 
2201, 2232, 2233, 2273, 2282); Energy Reorganization Act of 1974, secs. 
201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); 42 U.S.C. 2021a; 
National Environmental Policy Act of 1969 (42 U.S.C. 4332); Nuclear 
Waste Policy Act of 1982, secs. 114, 117, 121 (42 U.S.C. 10134, 10137, 
10141), 44 U.S.C. 3504 note.

    Source: 46 FR 13980, Feb. 25, 1981, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 60.1  Purpose and scope.

    This part prescribes rules governing the licensing (including 
issuance of a construction authorization) of the U.S. Department of 
Energy to receive and possess source, special nuclear, and byproduct 
material at a geologic repository operations area sited, constructed, or 
operated in accordance with the Nuclear Waste Policy Act of 1982, as 
amended. This part does not apply to any activity licensed under another 
part of this chapter. This part does not apply to the licensing of the 
U.S. Department of Energy to receive and possess source, special 
nuclear, and byproduct material at a geologic repository operations area 
sited, constructed, or operated at Yucca Mountain, Nevada, in accordance 
with the Nuclear Waste Policy Act of 1992, as amended, and the Energy 
Policy Act of 1992, subject to part 63 of this chapter. This part also 
gives notice to all persons who knowingly provide to any licensee, 
applicant, contractor, or subcontractor, components, equipment, 
materials, or other goods or services, that relate to a licensee's or 
applicant's activities subject to this part, that they may be 
individually subject to NRC enforcement action for violation of Sec. 
60.11.

[69 FR 2279, Jan. 14, 2004]



Sec. 60.2  Definitions.

    As used in this part:
    Accessible environment means:
    (1) The atmosphere;

[[Page 176]]

    (2) The land surface;
    (3) Surface water;
    (4) Oceans; and
    (5) The portion of the lithosphere that is outside the postclosure 
controlled area.
    Affected Indian Tribe means any Indian Tribe (1) within whose 
reservation boundaries a repository for high-level radioactive waste or 
spent fuel is proposed to be located; or (2) whose Federally defined 
possessory or usage rights to other lands outside of the reservation's 
boundaries arising out of Congressionally ratified treaties or other 
Federal law may be substantially and adversely affected by the locating 
of such a facility; Provided, That the Secretary of the Interior finds, 
upon the petition of the appropriate governmental officials of the 
Tribe, that such effects are both substantial and adverse to the Tribe.
    Anticipated processes and events means those natural processes and 
events that are reasonably likely to occur during the period the 
intended performance objective must be achieved. To the extent 
reasonable in the light of the geologic record, it shall be assumed that 
those processes operating in the geologic setting during the Quaternary 
Period continue to operate but with the perturbations caused by the 
presence of emplaced radioactive waste superimposed thereon.
    Barrier means any material or structure that prevents or 
substantially delays movement of water or radionuclides.
    Candidate area means a geologic and hydrologic system within which a 
geologic repository may be located.
    Commencement of construction means clearing of land, surface or 
subsurface excavation, or other substantial action that would adversely 
affect the environment of a site, but does not include changes desirable 
for the temporary use of the land for public recreational uses, site 
characterization activities, other preconstruction monitoring and 
investigation necessary to establish background information related to 
the suitability of a site or to the protection of environmental values, 
or procurement or manufacture of components of the geologic repository 
operations area.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Containment means the confinement of radioactive waste within a 
designated boundary.
    Controlled area means a surface location, to be marked by suitable 
monuments, extending horizontally no more than 10 kilometers in any 
direction from the outer boundary of the underground facility, and the 
underlying subsurface, which area has been committed to use as a 
geologic repository and from which incompatible activities would be 
restricted following permanent closure.
    Design bases means that information that identifies the specific 
functions to be performed by a structure, system, or component of a 
facility and the specific values or ranges of values chosen for 
controlling parameters as reference bounds for design. These values may 
be restraints derived from generally accepted ``state-of-the-art'' 
practices for achieving functional goals or requirements derived from 
analysis (based on calculation or experiments) of the effects of a 
postulated event under which a structure, system, or component must meet 
its functional goals. The values for controlling parameters for external 
events include:
    (1) Estimates of severe natural events to be used for deriving 
design bases that will be based on consideration of historical data on 
the associated parameters, physical data, or analysis of upper limits of 
the physical processes involved; and
    (2) Estimates of severe external man-induced events, to be used for 
deriving design bases, that will be based on analysis of human activity 
in the region, taking into account the site characteristics and the 
risks associated with the event.
    Design basis events means:
    (1)(i) Those natural and human-induced events that are reasonably 
likely to occur regularly, moderately frequently, or one or more times 
before permanent closure of the geologic repository operations area; and
    (ii) Other natural and man-induced events that are considered 
unlikely, but sufficiently credible to warrant consideration, taking 
into account the

[[Page 177]]

potential for significant radiological impacts on public health and 
safety.
    (2) The events described in paragraph (1)(i) of this definition are 
referred to as ``Category 1'' design basis events. The events described 
in paragraph (1)(ii) of this definition are referred to as ``Category 
2'' design basis events.
    Director means the Director of the Nuclear Regulatory Commission's 
Office of Nuclear Material Safety and Safeguards.
    Disposal means the isolation of radioactive wastes from the 
accessible environment.
    Disturbed zone means that portion of the postclosure controlled 
area, the physical or chemical properties of which have changed as a 
result of underground facility construction or as a result of heat 
generated by the emplaced radioactive wastes, such that the resultant 
change of properties may have a significant effect on the performance of 
the geologic repository.
    DOE means the U.S. Department of Energy or its duly authorized 
representatives.
    Engineered barrier system means the waste packages and the 
underground facility.
    Geologic repository means a system which is intended to be used for, 
or may be used for, the disposal of radioactive wastes in excavated 
geologic media. A geologic repository includes: (1) The geologic 
repository operations area, and (2) the portion of the geologic setting 
that provides isolation of the radioactive waste.
    Geologic repository operations area means a high-level radioactive 
waste facility that is part of a geologic repository, including both 
surface and subsurface areas, where waste handling activities are 
conducted.
    Geologic setting means the geologic, hydrologic, and geochemical 
systems of the region in which a geologic repository operations area is 
or may be located.
    Groundwater means all water which occurs below the land surface.
    High-level radioactive waste or HLW means: (1) Irradiated reactor 
fuel, (2) liquid wastes resulting from the operation of the first cycle 
solvent extraction system, or equivalent, and the concentrated wastes 
from subsequent extraction cycles, or equivalent, in a facility for 
reprocessing irradiated reactor fuel, and (3) solids into which such 
liquid wastes have been converted.
    HLW facility means a facility subject to the licensing and related 
regulatory authority of the Commission pursuant to Sections 202(3) and 
202(4) of the Energy Reorganization Act of 1974 (88 Stat. 1244). \1\
---------------------------------------------------------------------------

    \1\ These are DOE ``facilities used primarily for the receipt and 
storage of high-level radioactive wastes resulting from activities 
licensed under such Act [the Atomic Energy Act]'' and ``Retrievable 
Surface Storage Facilities and other facilities authorized for the 
express purpose of subsequent long-term storage of high-level 
radioactive wastes generated by [DOE], which are not used for, or are 
part of, research and development activities.''
---------------------------------------------------------------------------

    Host rock means the geologic medium in which the waste is emplaced.
    Important to safety, with reference to structures, systems, and 
components, means those engineered features of the repository whose 
function is:
    (1) To provide reasonable assurance that high-level waste can be 
received, handled, packaged, stored, emplaced, and retrieved without 
exceeding the requirements of Sec. 60.111(a) for Category 1 design 
basis events; or
    (2) To prevent or mitigate Category 2 design basis events that could 
result in doses equal to or greater than the values specified in Sec. 
60.136 to any individual located on or beyond any point on the boundary 
of the preclosure controlled area.
    Isolation means inhibiting the transport of radioactive material so 
that amounts and concentrations of this material entering the accessible 
environment will be kept within prescribed limits.
    NRC Public Document Room means the facility at One White Flint 
North, 11555 Rockville Pike, Room 0-1F23, Rockville, Maryland 20852, 
where certain public records of the NRC that were made available for 
public inspection in paper or microfiche prior to the implementation of 
the NRC Agency wide Documents Access and Management System, commonly 
referred to as ADAMS, will remain available for public inspection. It is 
also the place

[[Page 178]]

where computer terminals are available to access the NRC Library 
components of ADAMS on the NRC Website, http://www.nrc.gov, where copies 
can be made or ordered as set forth in Sec. 9.35 of this chapter. The 
facility is staffed with reference librarians to assist the public in 
identifying and locating documents and in using the NRC Web site and 
ADAMS. The NRC Public Document Room is open from 7:30 am to 4:15 pm, 
Monday through Friday, except on Federal holidays, Reference service and 
access to documents may also be requested by telephone (1-800-397-4209) 
between 8:30 am and 4:15 pm, or by e-mail ([email protected]), fax 
(301-415-3548), or letter (NRC Public Document Room, One White Flint 
North, 11555 Rockville Pike, Room 0-1F23, Rockville, Maryland 20852).
    NRC Web site, http://www.nrc.gov is the Internet uniform resource 
locator name for the Internet address of the Web site where NRC will 
ordinarily make available its public records for inspection.
    Permanent closure means final backfilling of the underground 
facility and the sealing of shafts and boreholes.
    Performance confirmation means the program of tests, experiments, 
and analyses which is conducted to evaluate the accuracy and adequacy of 
the information used to determine with reasonable assurance that the 
performance objectives for the period after permanent closure will be 
met.
    Postclosure controlled area means a surface location, to be marked 
by suitable monuments, extending horizontally no more than 10 kilometers 
in any direction from the outer boundary of the underground facility, 
and the underlying subsurface, which area has been committed to use as a 
geologic repository and from which incompatible activities would be 
restricted following permanent closure.
    Preclosure controlled area means that surface area surrounding the 
geologic repository operations area for which the licensee exercises 
authority over its use, in accordance with the provisions of this part, 
until permanent closure has been completed.
    Radioactive waste or waste means HLW and other radioactive materials 
other than HLW that are received for emplacement in a geologic 
repository.
    Restricted area means an area, access to which is limited by the 
licensee for the purpose of protecting individuals against undue risks 
from exposure to radiation and radioactive materials. Restricted area 
does not include areas used as residential quarters, but separate rooms 
in a residential building may be set aside as a restricted area.
    Retrieval means the act of intentionally removing radioactive waste 
from the underground location at which the waste had been previously 
emplaced for disposal.
    Saturated zone means that part of the earth's crust beneath the 
regional water table in which all voids, large and small, are ideally 
filled with water under pressure greater than atmospheric.
    Site means the location of the preclosure controlled area, or of the 
postclosure controlled area, or both.
    Site characterization means the program of exploration and research, 
both in the laboratory and in the field, undertaken to establish the 
geologic conditions and the ranges of those parameters of a particular 
site relevant to the procedures under this part. Site characterization 
includes borings, surface excavations, excavation of exploratory shafts, 
limited subsurface lateral excavations and borings, and in situ testing 
at depth needed to determine the suitability of the site for a geologic 
repository, but does not include preliminary borings and geophysical 
testing needed to decide whether site characterization should be 
undertaken.
    Unanticipated processes and events means those processes and events 
affecting the geologic setting that are judged not to be reasonably 
likely to occur during the period the intended performance objective 
must be achieved, but which are nevertheless sufficiently credible to 
warrant consideration. Unanticipated processes and events may be either 
natural processes or events or processes and events initiated by human 
activities other than those activities licensed under this part. 
Processes and events initiated by human activities may only be found to 
be sufficiently credible to warrant consideration if it is assumed that: 
(1) The

[[Page 179]]

monuments provided for by this part are sufficiently permanent to serve 
their intended purpose; (2) the value to future generations of potential 
resources within the site can be assessed adequately under the 
applicable provisions of this part; (3) an understanding of the nature 
of radioactivity, and an appreciation of its hazards, have been retained 
in some functioning institutions; (4) institutions are able to assess 
risk and to take remedial action at a level of social organization and 
technological competence equivalent to, or superior to, that which was 
applied in initiating the processes or events concerned; and (5) 
relevant records are preserved, and remain accessible, for several 
hundred years after permanent closure.
    Underground facility means the underground structure, including 
openings and backfill materials, but excluding shafts, boreholes, and 
their seals.
    Unrestricted area means an area, access to which is neither limited 
nor controlled by the licensee.
    Unsaturated zone means the zone between the land surface and the 
regional water table. Generally, fluid pressure in this zone is less 
than atmospheric pressure, and some of the voids may contain air or 
other gases at atmospheric pressure. Beneath flooded areas or in perched 
water bodies the fluid pressure locally may be greater than atmospheric.
    Waste form means the radioactive waste materials and any 
encapsulating or stabilizing matrix.
    Waste package means the waste form and any containers, shielding, 
packing and other absorbent materials immediately surrounding an 
individual waste container.
    Water table means that surface in a groundwater body at which the 
water pressure is atmospheric.

[48 FR 28217, June 21, 1983, as amended at 50 FR 29647, July 22, 1985; 
51 FR 27162, July 30, 1986; 53 FR 43421, Oct. 27, 1988; 61 FR 64267, 
Dec. 4, 1996; 64 FR 48953, Sept. 9, 1999; 69 FR 76601, Dec. 22, 2004; 76 
FR 72086, Nov. 22, 2011]



Sec. 60.3  License required.

    (a) DOE shall not receive or possess source, special nuclear, or 
byproduct material at a geologic repository operations area except as 
authorized by a license issued by the Commission pursuant to this part.
    (b) DOE shall not commence construction of a geologic repository 
operations area unless it has filed an application with the Commission 
and has obtained construction authorization as provided in this part. 
Failure to comply with this requirement shall be grounds for denial of a 
license.



Sec. 60.4  Communications and records.

    (a) Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk: 
Director, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; by hand delivery to 
the NRC's offices at 11555 Rockville Pike, Rockville, Maryland; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, or CD-ROM. Electronic submissions must be made in 
a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.
    (b) Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform provided that the 
copy or microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period. The record may also be stored in electronic media with 
the capability for producing legible, accurate, and complete records 
during the required

[[Page 180]]

retention period. Records such as letters, drawings, specifications, 
must include all pertinent information such as stamps, initials, and 
signatures. The licensee shall maintain adequate safeguards against 
tampering with and loss of records.

[53 FR 19251, May 27, 1988, as amended at 53 FR 43421, Oct. 27, 1988; 68 
FR 58813, Oct. 10, 2003; 74 FR 62682, Dec. 1, 2009; 80 FR 74980, Dec. 1, 
2015]



Sec. 60.5  Interpretations.

    Except as specifically authorized by the Commission, in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be considered binding upon 
the Commission.



Sec. 60.6  Exemptions.

    The Commission may, upon application by DOE, any interested person, 
or upon its own initiative, grant such exemptions from the requirements 
of the regulations in this part as it determines are authorized by law, 
will not endanger life or property or the common defense and security, 
and are otherwise in the public interest.



Sec. 60.7  License not required for certain preliminary activities.

    The requirement for a license set forth in Sec. 60.3(a) of this 
part is not applicable to the extent that DOE receives and possesses 
source, special nuclear, and byproduct material at a geologic 
repository:
    (a) For purposes of site characterization; or
    (b) For use, during site characterization or construction, as 
components of radiographic, radiation monitoring, or similar equipment 
or instrumentation.



Sec. 60.8  Information collection requirements: Approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0127.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 60.47, 60.62, 60.63, 60.65.
    (c) In Sec. 60.47, Form N-71 and associated forms are approved 
under control number 3150-0056, and DOC/NRC Forms AP-1, AP-A, and 
associated forms are approved under control number 0694-0135.

[61 FR 64268, Dec. 4, 1996, as amended at 62 FR 52188, Oct. 6, 1997; 73 
FR 78605, Dec. 23, 2008]



Sec. 60.9  Employee protection.

    (a) Discrimination by a Commission licensee, an applicant for a 
Commission license, or a contractor or subcontractor of a Commission 
licensee or applicant against an employee for engaging in certain 
protected activities is prohibited. Discrimination includes discharge 
and other actions that relate to compensation, terms, conditions, or 
privileges of employment. The protected activities are established in 
section 211 of the Energy Reorganization Act of 1974, as amended, and in 
general are related to the administration or enforcement of a 
requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) introductory text of this section or possible violations of 
requirements imposed under either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) introductory text or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at

[[Page 181]]

any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) introductory 
text.
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, an applicant for a Commission license, or a 
contractor or subcontractor of a Commission licensee or applicant may be 
grounds for--
    (1) Denial, revocation, or suspension of the license.
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant.
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee and each applicant for a license shall 
prominently post the revision of NRC Form 3, ``Notice to Employees,'' 
referenced in 10 CFR 19.11(c). This form must be posted at locations 
sufficient to permit employees protected by this section to observe a 
copy on the way to or from their place of work. Premises must be posted 
not later than 30 days after an application is docketed and remain 
posted while the application is pending before the Commission, during 
the term of the license, and for 30 days following license termination.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[58 FR 52411, Oct. 8, 1993, as amended at 60 FR 24552, May 9, 1995; 61 
FR 6765, Feb. 22, 1996; 68 FR 58813, Oct. 10, 2003; 72 FR 63974, Nov. 
14, 2007; 73 FR 30459, May 28, 2008; 79 FR 66605, Nov. 10, 2014]



Sec. 60.10  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
license or by a licensee or information required

[[Page 182]]

by statute or by the Commission's regulations, orders, or license 
conditions to be maintained by the applicant or the licensee shall be 
complete and accurate in all material respects.
    (b) Each applicant or licensee shall notify the Commission of 
information identified by the applicant or licensee as having for the 
regulated activity a significant implication for public health and 
safety or common defense and security. An applicant or licensee violates 
this paragraph only if the applicant or licensee fails to notify the 
Commission of information that the applicant or licensee has identified 
as having a significant implication for public health and safety or 
common defense and security. Notification shall be provided to the 
Administrator of the appropriate Regional Office within two working days 
of identifying the information. This requirement is not applicable to 
information which is already required to be provided to the Commission 
by other reporting or updating requirements.

[52 FR 49372, Dec. 31, 1987]



Sec. 60.11  Deliberate misconduct.

    (a) Any licensee, applicant for a license, employee of a licensee or 
applicant; or any contractor (including a supplier or consultant), 
subcontractor, employee of a contractor or subcontractor of any licensee 
or applicant for a license who knowingly provides to any licensee, 
applicant, contractor, or subcontractor, any components, equipment, 
materials, or other goods or services that relate to a licensee's or 
applicant's activities in this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee or applicant to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation of 
any license issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, an applicant, or a 
licensee's or applicant's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For the purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee or applicant to be in violation of any 
rule, regulation, or order; or any term, condition, or limitation, of 
any license issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
applicant, contractor, or subcontractor.

[63 FR 1898, Jan. 13, 1998]



                           Subpart B_Licenses

                          Preapplication Review



Sec. 60.15  Site characterization.

    (a) Prior to submittal of an application for a license to be issued 
under this part DOE shall conduct a program of site characterization 
with respect to the site to be described in such application.
    (b) Unless the Commission determines with respect to the site 
described in the application that it is not necessary, site 
characterization shall include a program of in situ exploration and 
testing at the depths that wastes would be emplaced.
    (c) The program of site characterization shall be conducted in 
accordance with the following:
    (1) Investigations to obtain the required information shall be 
conducted in such a manner as to limit adverse effects on the long-term 
performance of the geologic repository to the extent practical.
    (2) The number of exploratory boreholes and shafts shall be limited 
to the extent practical consistent with obtaining the information needed 
for site characterization.
    (3) To the extent practical, exploratory boreholes and shafts in the 
geologic repository operations area shall be located where shafts are 
planned for underground facility construction and operation or where 
large unexcavated pillars are planned.

[[Page 183]]

    (4) Subsurface exploratory drilling, excavation, and in situ testing 
before and during construction shall be planned and coordinated with 
geologic repository operations area design and construction.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28219, June 21, 1983. 
Redesignated and amended at 51 FR 27162, July 30, 1986; 54 FR 27871, 
July 3, 1989]



Sec. 60.16  Site characterization plan required.

    Before proceeding to sink shafts at any area which has been approved 
by the President for site characterization, DOE shall submit to the 
Director, for review and comment, a site characterization plan for such 
area. DOE shall defer the sinking of such shafts until such time as 
there has been an opportunity for Commission comments thereon to have 
been solicited and considered by DOE.

[51 FR 27162, July 30, 1986]



Sec. 60.17  Contents of site characterization plan.

    The site characterization plan shall contain--
    (a) A general plan for site characterization activities to be 
conducted at the area to be characterized, which general plan shall 
include:
    (1) A description of such area, including information on quality 
assurance programs that have been applied to the collection, recording, 
and retention of information used in preparing such description.
    (2) A description of such site characterization activities, 
including the following--
    (i) The extent of planned excavations;
    (ii) Plans for any onsite testing with radioactive material, 
including radioactive tracers, or nonradioactive material;
    (iii) Plans for any investigation activities that may affect the 
capability of such area to isolate high-level radioactive waste;
    (iv) Plans to control any adverse impacts from such site 
characterization activities that are important to safety or that are 
important to waste isolation; and
    (v) Plans to apply quality assurance to data collection, recording, 
and retention.
    (3) Plans for the decontamination and decommissioning of such area, 
and for the mitigation of any significant adverse environmental impacts 
caused by site characterization activities, if such area is determined 
unsuitable for application for a construction authorization for a 
geologic repository operations area;
    (4) Criteria, developed pursuant to section 112(a) of the Nuclear 
Waste Policy Act of 1982, to be used to determine the suitability of 
such area for the location of a geologic repository; and
    (5) Any other information which the Commission, by rule or order, 
requires.
    (b) A description of the possible waste form or waste package for 
the high-level radioactive waste to be emplaced in such geologic 
repository, a description (to the extent practicable) of the 
relationship between such waste form or waste package and the host rock 
at such area, and a description of the activities being conducted by DOE 
with respect to such possible waste form or waste package or their 
relationship; and
    (c) A conceptual design for the geologic repository operations area 
that takes into account likely site-specific requirements.

[51 FR 27163, July 30, 1986]



Sec. 60.18  Review of site characterization activities. \2\
---------------------------------------------------------------------------

    \2\ In addition to the review of site characterization activities 
specified in this section, the Commission contemplates an ongoing review 
of other information on site investigation and site characterization, in 
order to allow early identification of potential licensing issues for 
timely resolution. This activity will include, for example, a review of 
the environmental assessments prepared by DOE at the time of site 
nomination, and review of issues related to long lead time exploratory 
shaft planning and procurement actions by DOE prior to issuance of site 
characterization plans.
---------------------------------------------------------------------------

    (a) The Director shall cause to be published in the Federal Register 
a notice that a site characterization plan has been received from DOE 
and that a staff review of such plan has begun. The notice shall 
identify the area to be

[[Page 184]]

characterized and the NRC staff members to be consulted for further 
information.
    (b) The Director shall make a copy of the site characterization plan 
available at the Public Document Room. The Director shall also transmit 
copies of the published notice of receipt to the Governor and 
legislature of the State in which the area to be characterized is 
located and to the governing body of any affected Indian Tribe. The 
Director shall provide an opportunity, with respect to any area to be 
characterized, for the State in which such area is located and for 
affected Indian Tribes to present their views on the site 
characterization plan and their suggestions with respect to comments 
thereon which may be made by NRC. In addition, the Director shall make 
NRC staff available to consult with States and affected Indian Tribes as 
provided in Subpart C of this part.
    (c) The Director shall review the site characterization plan and 
prepare a site characterization analysis with respect to such plan. In 
the preparation of such site characterization analysis, the Director may 
invite and consider the views of interested persons on DOE's site 
characterization plan and may review and consider comments made in 
connection with public hearings held by DOE.
    (d) The Director shall provide to DOE the site characterization 
analysis together with such additional comments as may be warranted. 
These comments shall include either a statement that the Director has no 
objection to the DOE's site characterization program, if such a 
statement is appropriate, or specific objections with respect to DOE's 
program for characterization of the area concerned. In addition, the 
Director may make specific recommendations pertinent to DOE's site 
characterization program.
    (e) If DOE's planned site characterization activities include onsite 
testing with radioactive material, including radioactive tracers, the 
Director's comments shall include a determination regarding whether or 
not the Commission concurs that the proposed use of such radioactive 
material is necessary to provide data for the preparation of the 
environmental reports required by law and for an application to be 
submitted under Sec. 60.22 of this part.
    (f) The Director shall publish in the Federal Register a notice of 
availability of the site characterization analysis and a request for 
public comment within a reasonable period, as specified (not less than 
90 days). The notice along with copies of the site characterization 
analysis shall be available at the NRC Web site, http://www.nrc.gov, and 
copies of any comments received will also be made available there.
    (g) During the conduct of site characterization activities, DOE 
shall report not less than once every six months to the Commission on 
the nature and extent of such activities and the information that has 
been developed, and on the progress of waste form and waste package 
research and development. The semiannual reports shall include the 
results of site characterization studies, the identification of new 
issues, plans for additional studies to resolve new issues, elimination 
of planned studies no longer necessary, identification of decision 
points reached and modifications to schedules where appropriate. DOE 
shall also report its progress in developing the design of a geologic 
repository operations area appropriate for the area being characterized, 
noting when key design parameters or features which depend upon the 
results of site characterization will be established. Other topics 
related to site characterization shall also be covered if requested by 
the Director.
    (h) During the conduct of site characterization activities, NRC 
staff shall be permitted to visit and inspect the locations at which 
such activities are carried out and to observe excavations, borings, and 
in situ tests as they are done.
    (i) The Director may comment at any time in writing to DOE, 
expressing current views on any aspect of site characterization. In 
particular, such comments shall be made whenever the Director, upon 
review of comments invited on the site characterization analysis or upon 
review of DOE's semiannual reports, determines that there

[[Page 185]]

are substantial new grounds for making recommendations or stating 
objections to DOE's site characterization program. The Director shall 
invite public comment on any comments which the Director makes to DOE 
upon review of the DOE semiannual reports or on any other comments which 
the Director makes to DOE on site characterization.
    (j) The Director shall transmit copies of the site characterization 
analysis and all comments to DOE made by the Director under this section 
to the Governor and legislature of the State in which the area to be 
characterized is located and to the governing body of any affected 
Indian Tribe. When transmitting the site characterization analysis under 
this paragraph, the Director shall invite the addressees to review and 
comment thereon.
    (k) All correspondence between DOE and the NRC under this section, 
including the reports described in paragraph (g), shall be placed in the 
Public Document Room.
    (l) The activities described in paragraphs (a) through (k) of this 
section constitute informal conference between a prospective applicant 
and the staff, as described in Sec. 2.101(a)(1) of this chapter, and 
are not part of a proceeding under the Atomic Energy Act of 1954, as 
amended. Accordingly, neither the issuance of a site characterization 
analysis nor any other comments of the Director made under this section 
constitutes a commitment to issue any authorization or license or in any 
way affect the authority of the Commission, the Atomic Safety and 
Licensing Appeal Board, Atomic Safety and Licensing Boards, other 
presiding officers, or the Director, in any such proceeding.

[51 FR 27163, July 30, 1986, as amended at 64 FR 48954, Sept. 9, 1999]

                          License Applications



Sec. 60.21  Content of application.

    (a) An application shall consist of general information and a Safety 
Analysis Report. An environmental impact statement shall be prepared in 
accordance with the Nuclear Waste Policy Act of 1982, as amended, and 
shall accompany the application. Any Restricted Data or National 
Security Information shall be separated from unclassified information.
    (b) The general information shall include:
    (1) A general description of the proposed geologic repository 
identifying the location of the geologic repository operations area, the 
general character of the proposed activities, and the basis for the 
exercise of licensing authority by the Commission.
    (2) Proposed schedules for construction, receipt of waste, and 
emplacement of wastes at the proposed geologic repository operations 
area.
    (3) A detailed plan to provide physical protection of high-level 
radioactive waste in accordance with Sec. 73.51 of this chapter. This 
plan must include the design for physical protection, the licensee's 
safeguards contingency plan, and security organization personnel 
training and qualification plan. The plan must list tests, inspections, 
audits, and other means to be used to demonstrate compliance with such 
requirements.
    (4) A description of the program to meet the requirements of Sec. 
60.78.
    (5) A description of site characterization work actually conducted 
by DOE at all sites considered in the application and, as appropriate, 
explanations of why such work differed from the description of the site 
characterization program described in the Site Characterization Report 
for each site.
    (c) The Safety Analysis Report shall include:
    (1) A description and assessment of the site at which the proposed 
geologic repository operations area is to be located with appropriate 
attention to those features of the site that might affect geologic 
repository operations area design and performance. The description of 
the site shall identify the location of the geologic repository 
operations area with respect to the boundary of the accessible 
environment.
    (i) The description of the site shall also include the following 
information regarding subsurface conditions. This description shall, in 
all cases, include this information with respect to the

[[Page 186]]

postclosure controlled area. In addition, where subsurface conditions 
outside the postclosure controlled area may affect isolation within the 
postclosure controlled area, the description shall include information 
with respect to subsurface conditions outside the postclosure controlled 
area to the extent the information is relevant and material. The 
detailed information referred to in this paragraph shall include:
    (A) The orientation, distribution, aperture in-filling and origin of 
fractures, discontinuities, and heterogeneities;
    (B) The presence and characteristics of other potential pathways 
such as solution features, breccia pipes, or other potentially permeable 
features;
    (C) The geomechanical properties and conditions, including pore 
pressure and ambient stress conditions;
    (D) The hydrogeologic properties and conditions;
    (E) The geochemical properties; and
    (F) The anticipated response of the geomechanical, hydrogeologic, 
and geochemical systems to the maximum design thermal loading, given the 
pattern of fractures and other discontinuities and the heat transfer 
properties of the rock mass and groundwater.
    (ii) The assessment shall contain:
    (A) An analysis of the geology, geophysics, hydrogeology, 
geochemistry, climatology, and meteorology of the site,
    (B) Analyses to determine the degree to which each of the favorable 
and potentially adverse conditions, if present, has been characterized, 
and the extent to which it contributes to or detracts from isolation. 
For the purpose of determining the presence of the potentially adverse 
conditions, investigations shall extend from the surface to a depth 
sufficient to determine critical pathways for radionuclide migration 
from the underground facility to the accessible environment. Potentially 
adverse conditions shall be investigated outside of the postclosure 
controlled area if they affect isolation within the postclosure 
controlled area.
    (C) An evaluation of the performance of the proposed geologic 
repository for the period after permanent closure, assuming anticipated 
processes and events, giving the rates and quantities of releases of 
radionuclides to the accessible environment as a function of time; and a 
similar evaluation which assumes the occurrence of unanticipated 
processes and events.
    (D) The effectiveness of engineered and natural barriers, including 
barriers that may not be themselves a part of the geologic repository 
operations area, against the release of radioactive material to the 
environment. The analysis shall also include a comparative evaluation of 
alternatives to the major design features that are important to waste 
isolation, with particular attention to the alternatives that would 
provide longer radionuclide containment and isolation.
    (E) An analysis of the performance of the major design structures, 
systems, and components, both surface and subsurface, to identify those 
that are important to safety. For the purposes of this analysis, it 
shall be assumed that operations at the geologic repository operations 
area will be carried out at the maximum capacity and rate of receipt of 
radioactive waste stated in the application.
    (F) An explanation of measures used to support the models used to 
perform the assessments required in paragraphs (A) through (D). Analyses 
and models that will be used to predict future conditions and changes in 
the geologic setting shall be supported by using an appropriate 
combination of such methods as field tests, in situ tests, laboratory 
tests which are representative of field conditions, monitoring data, and 
natural analog studies.
    (2) A description and discussion of the design, both surface and 
subsurface, of the geologic repository operations area including:
    (i) The principal design criteria and their relationship to any 
general performance objectives promulgated by the Commission,
    (ii) The design bases and the relation of the design bases to the 
principal design criteria,
    (iii) Information relative to materials of construction (including 
geologic media, general arrangement, and approximate dimensions), and
    (iv) Codes and standards that DOE proposes to apply to the design 
and

[[Page 187]]

construction of the geologic repository operations area.
    (3) A description and analysis of the design and performance 
requirements for structures, systems, and components of the geologic 
repository that are important to safety. The analysis must include a 
demonstration that--
    (i) The requirements of Sec. 60.111(a) will be met, assuming 
occurrence of Category 1 design basis events; and
    (ii) The requirements of Sec. 60.136 will be met, assuming 
occurrence of Category 2 design basis events.
    (4) A description of the quality assurance program to be applied to 
the structures, systems, and components important to safety and to the 
engineered and natural barriers important to waste isolation.
    (5) A description of the kind, amount, and specifications of the 
radioactive material proposed to be received and possessed at the 
geologic repository operations area.
    (6) An identification and justification for the selection of those 
variables, conditions, or other items which are determined to be 
probable subjects of license specifications. Special attention shall be 
given to those items that may significantly influence the final design.
    (7) A description of the program for control and monitoring of 
radioactive effluents and occupational radiation exposures to maintain 
such effluents and exposures in accordance with the requirements of part 
20 of this chapter.
    (8) A description of the controls that the applicant will apply to 
restrict access and to regulate land use at the site and adjacent areas, 
including a conceptual design of monuments which would be used to 
identify the postclosure controlled area after permanent closure.
    (9) Plans for coping with radiological emergencies at any time prior 
to permanent closure and decontamination or dismantlement of surface 
facilities.
    (10) A description of the program to be used to maintain the records 
described in Sec. Sec. 60.71 and 60.72.
    (11) A description of design considerations that are intended to 
facilitate permanent closure and decontamination or dismantlement of 
surface facilities.
    (12) A description of plans for retrieval and alternate storage of 
the radioactive wastes should the geologic repository prove to be 
unsuitable for disposal of radioactive wastes.
    (13) An identification and evaluation of the natural resources of 
the geologic setting, including estimates as to undiscovered deposits, 
the exploitation of which could affect the ability of the geologic 
repository to isolate radioactive wastes. Undiscovered deposits of 
resources characteristic of the area shall be estimated by reasonable 
inference based on geological and geophysical evidence. This evaluation 
of resources, including undiscoverd deposits, shall be conducted for the 
site and for areas of similar size that are representative of and are 
within the geologic setting. For natural resources with current markets 
the resources shall be assessed, with estimates provided of both gross 
and net value. The estimate of net value shall take into account current 
development, extraction and marketing costs. For natural resources 
without current markets, but which would be marketable given credible 
projected changes in economic or technological factors, the resources 
shall be described by physical factors such as tonnage or other amount, 
grade, and quality.
    (14) An identification of those structures, systems, and components 
of the geologic repository, both surface and subsurface, which require 
research and development to confirm the adequacy of design. For 
structures, systems, and components important to safety and for the 
engineered and natural barriers important to waste isolation, DOE shall 
provide a detailed description of the programs designed to resolve 
safety questions, including a schedule indicating when these questions 
would be resolved.
    (15) The following information concerning activities at the geologic 
repository operations area:
    (i) The organizational structure of DOE as it pertains to 
construction and operation of the geologic repository operations area 
including a description of any delegations of authority and assignments 
of responsibilities, whether

[[Page 188]]

in the form of regulations, administrative directives, contract 
provisions, or otherwise.
    (ii) Identification of key positions which are assigned 
responsibility for safety at and operation of the geologic repository 
operations area.
    (iii) Personnel qualifications and training requirements.
    (iv) Plans for startup activities and startup testing.
    (v) Plans for conduct of normal activities, including maintenance, 
surveillance, and periodic testing of structures, systems, and 
components of the geologic repository operation area.
    (vi) Plans for permanent closure and plans for the decontamination 
or dismantlement of surface facilities.
    (vii) Plans for any uses of the geologic repository operations area 
for purposes other than disposal of radioactive wastes, with an analysis 
of the effects, if any, that such uses may have upon the operation of 
the structures, systems, and components important to safety and the 
engineered and natural barriers important to waste isolation.
    (d) The applicant for a license to receive and possess source, 
special nuclear, and byproduct material at a geologic repository 
operations area sited, constructed, or operated in accordance with the 
Nuclear Waste Policy Act of 1982 shall protect Safeguards Information in 
accordance with the requirements in Sec. 73.21 and the requirements in 
Sec. 73.22 or Sec. 73.23 of this chapter, as applicable, and shall 
protect classified information in accordance with the requirements of 
parts 25 and 95 of this chapter, as applicable.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28219, June 21, 1983; 
54 FR 27871, July 3, 1989; 61 FR 64268, Dec. 4, 1996; 63 FR 26961, May 
15, 1998; 73 FR 63571, Oct. 24, 2008]



Sec. 60.22  Filing and distribution of application.

    (a) An application for a construction authorization for a high-level 
radioactive waste repository at a geologic repository operations area, 
and an application for a license to receive and possess source, special 
nuclear, or byproduct material at a geologic repository operations area 
at a site which has been characterized, and any amendments thereto, and 
an accompanying environmental impact statement and any supplements, 
shall be signed by the Secretary of Energy or the Secretary's authorized 
representative and must be filed with the Director.
    (b) DOE shall maintain the capability to generate additional copies 
for distribution in accordance with written instructions from the 
Director or the Director's designee.
    (c) DOE shall, upon notification of the appointment of an Atomic 
Safety and Licensing Board, update the application, eliminating all 
superseded information, and supplement the environmental impact 
statement if necessary, and serve the updated application and 
environmental impact statement (as it may have been supplemented) as 
directed by the Board. At that time DOE shall also serve one such copy 
of the application and environmental impact statement on the Atomic 
Safety and Licensing Appeal Panel. Any subsequent amendments to the 
application or supplements to the environmental impact statement shall 
be served in the same manner.
    (d) At the time of filing of an application and any amendments 
thereto, one copy shall be made available in an appropriate location 
near the proposed geologic repository operations area (which shall be a 
public document room, if one has been established) for inspection by the 
public and updated as amendments to the application are made. The 
environmental impact statement and any supplements thereto shall be made 
available in the same manner. An updated copy of the application, and 
the environmental impact statement and supplements, shall be produced at 
any public hearing held by the Commission on the application, for use by 
any party to the proceeding.
    (e) The DOE shall certify that the updated copies of the 
application, and the environmental impact statement as it may have been 
supplemented, as referred to in paragraphs (c) and (d) of this section, 
contain the current contents of such documents submitted in accordance 
with the requirements of this part.

[54 FR 27871, July 3, 1989, as amended at 68 FR 58814, Oct. 10, 2003; 69 
FR 2279, Jan. 14, 2004]

[[Page 189]]



Sec. 60.23  Elimination of repetition.

    In its application, environmental report, or Site Characterization 
Report, the DOE may incorporate by reference information contained in 
previous applications, statements, or reports filed with the Commission: 
Provided, That such references are clear and specific and that copies of 
the information so incorporated are available in the public document 
room located near the site of the proposed geologic repository.



Sec. 60.24  Updating of application and environmental impact statement.

    (a) The application shall be as complete as possible in the light of 
information that is reasonably available at the time of docketing.
    (b) The DOE shall update its application in a timely manner so as to 
permit the Commission to review, prior to issuance of a license:
    (1) Additional geologic, geophysical, geochemical, hydrologic, 
meteorologic and other data obtained during construction.
    (2) Conformance of construction of structures, systems, and 
components with the design.
    (3) Results of research programs carried out to confirm the adequacy 
of designs.
    (4) Other information bearing on the Commission's issuance of a 
license that was not available at the time a construction authorization 
was issued.
    (c) The DOE shall supplement its environmental impact statement in a 
timely manner so as to take into account the environmental impacts of 
any substantial changes in its proposed actions or any significant new 
circumstances or information relevant to environmental concerns and 
bearing on the proposed action or its impacts.

[46 FR 13980, Feb. 25, 1981, as amended at 54 FR 27872, July 3, 1989]

                       Construction Authorization



Sec. 60.31  Construction authorization.

    Upon review and consideration of an application and environmental 
impact statement submitted under this part, the Commission may authorize 
construction if it determines:
    (a) Safety. That there is reasonable assurance that the types and 
amounts of radioactive materials described in the application can be 
received, possessed, and disposed of in a geologic repository operations 
area of the design proposed without unreasonable risk to the health and 
safety of the public. In arriving at this determination, the Commission 
shall consider whether:
    (1) DOE has described the proposed geologic repository including but 
not limited to: (i) The geologic, geophysical, geochemical and 
hydrologic characteristics of the site; (ii) the kinds and quantities of 
radioactive waste to be received, possessed, stored, and disposed of in 
the geologic repository operations area; (iii) the principal 
architectural and engineering criteria for the design of the geologic 
repository operations area; (iv) construction procedures which may 
affect the capability of the geologic repository to serve its intended 
function; and (v) features or components incorporated in the design for 
the protection of the health and safety of the public.
    (2) The site and design comply with the performance objectives and 
criteria contained in Subpart E of this part.
    (3) The DOE's quality assurance program complies with the 
requirements of Subpart G of this part.
    (4) The DOE's personnel training program complies with the criteria 
contained in Subpart H of this part.
    (5) The DOE's emergency plan complies with the criteria contained in 
Subpart I of this part.
    (6) The DOE's proposed operating procedures to protect health and to 
minimize danger to life or property are adequate.
    (b) Common defense and security. That there is reasonable assurance 
that the activities proposed in the application will not be inimical to 
the common defense and security.
    (c) Environmental. That, after weighing the environmental, economic, 
technical and other benefits against environmental costs and considering 
available alternatives, the action called for is issuance of the 
construction authorization, with any appropriate conditions to protect 
environmental values.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28220, June 21, 1983; 
54 FR 27872, July 3, 1989; 63 FR 26961, May 15, 1998]

[[Page 190]]



Sec. 60.32  Conditions of construction authorization.

    (a) A construction authorization shall include such conditions as 
the Commission finds to be necessary to protect the health and safety of 
the public, the common defense and security, or environmental values.
    (b) The Commission will incorporate in the construction 
authorization provisions requiring DOE to furnish periodic or special 
reports regarding: (1) Progress of construction, (2) any data about the 
site obtained during construction which are not within the predicted 
limits upon which the facility design was based, (3) any deficiencies in 
design and construction which, if uncorrected, could adversely affect 
safety at any future time, and (4) results of research and development 
programs being conducted to resolve safety questions.
    (c) The construction authorization will include restrictions on 
subsequent changes to the features of the geologic repository and the 
procedures authorized. The restrictions that may be imposed under this 
paragraph can include measures to prevent adverse effects on the 
geologic setting as well as measures related to the design and 
construction of the geologic repository operations area. These 
restrictions will fall into three categories of descending importance to 
public health and safety as follows: (1) Those features and procedures 
which may not be changed without: (i) 60 days prior notice to the 
Commission (ii) 30 days notice of opportunity for a prior hearing, and 
(iii) prior Commission approval; (2) those features and procedures which 
may not be changed without (i) 60 days prior notice to the Commission, 
and (ii) prior Commission approval; and (3) those features and 
procedures which may not be changed without 60 days notice to the 
Commission. Features and procedures falling in paragraph (c)(3) of this 
section may not be changed without prior Commission approval if the 
Commission, after having received the required notice, so orders.
    (d) A construction authorization shall be subject to the limitation 
that a license to receive and possess source, special nuclear, or 
byproduct material at the geologic repository operations area shall not 
be issued by the Commission until (1) the DOE has updated its 
application as specified in Sec. 60.24, and (2) the Commission has made 
the findings stated in Sec. 60.41.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28221, June 21, 1983]



Sec. 60.33  Amendment of construction authorization.

    (a) An application for amendment of a construction authorization 
shall be filed with the Commission fully describing any changes desired 
and following as far as applicable the format prescribed in Sec. 60.21.
    (b) In determining whether an amendment of a construction 
authorization will be approved, the Commission will be guided by the 
considerations which govern the issuance of the initial construction 
authorization, to the extent applicable.

                     License Issuance and Amendment



Sec. 60.41  Standards for issuance of a license.

    A license to receive and possess source, special nuclear, or 
byproduct material at a geologic repository operations area may be 
issued by the Commission upon finding that:
    (a) Construction of the geologic repository operations area has been 
substantially completed in conformity with the application as amended, 
the provisions of the Atomic Energy Act, and the rules and regulations 
of the Commission. Construction may be deemed to be substantially 
complete for the purposes of this paragraph if the construction of (1) 
surface and interconnecting structures, systems, and components, and (2) 
any underground storage space required for initial operation are 
substantially complete.
    (b) The activities to be conducted at the geologic repository 
operations area will be in conformity with the application as amended, 
the provisions of the Atomic Energy Act and the Energy Reorganization 
Act, and the rules and regulations of the Commission.
    (c) The issuance of the license will not be inimical to the common 
defense and security and will not constitute an

[[Page 191]]

unreasonable risk to the health and safety of the public.
    (d) All applicable requirements of part 51 have been satisfied.

[46 FR 13980, Feb. 25, 1981, as amended at 63 FR 26961, May 15, 1998]



Sec. 60.42  Conditions of license.

    (a) A license issued pursuant to this part shall include such 
conditions, including license specifications, as the Commission finds to 
be necessary to protect the health and safety of the public, the common 
defense and security, and environmental values.
    (b) Whether stated therein or not, the following shall be deemed 
conditions in every license issued:
    (1) The license shall be subject to revocation, suspension, 
modification, or amendment for cause as provided by the Atomic Energy 
Act and the Commission's regulations.
    (2) The DOE shall at any time while the license is in effect, upon 
written request of the Commission, submit written statements to enable 
the Commission to determine whether or not the license should be 
modified, suspended or revoked.
    (3) The license shall be subject to the provisions of the Atomic 
Energy Act now or hereafter in effect and to all rules, regulations, and 
orders of the Commission. The terms and conditions of the license shall 
be subject to amendment, revision, or modification, by reason of 
amendments to or by reason of rules, regulations, and orders issued in 
accordance with the terms of the Atomic Energy Act.
    (c) Each license shall be deemed to contain the provisions set forth 
in Section 183 b-d, inclusive, of the Atomic Energy Act, whether or not 
these provisions are expressly set forth in the license.
    (d) The licensee (Department of Energy) shall ensure that Safeguards 
Information is protected against unauthorized disclosure in accordance 
with the requirements in Sec. 73.21 and the requirements in Sec. 73.22 
or Sec. 73.23 of this chapter, as applicable. The licensee (Department 
of Energy) shall ensure that classified information is protected in 
accordance with the requirements of parts 25 and 95 of this chapter, as 
applicable.

[46 FR 13980, Feb. 25, 1981, as amended at 73 FR 63571, Oct. 24, 2008]



Sec. 60.43  License specification.

    (a) A license issued under this part shall include license 
conditions derived from the analyses and evaluations included in the 
application, including amendments made before a license is issued, 
together with such additional conditions as the Commission finds 
appropriate.
    (b) License conditions shall include items in the following 
categories:
    (1) Restrictions as to the physical and chemical form and 
radioisotopic content of radioactive waste.
    (2) Restrictions as to size, shape, and materials and methods of 
construction of radioactive waste packaging.
    (3) Restrictions as to the amount of waste permitted per unit volume 
of storage space considering the physical characteristics of both the 
waste and the host rock.
    (4) Requirements relating to test, calibration, or inspection to 
assure that the foregoing restrictions are observed.
    (5) Controls to be applied to restricted access and to avoid 
disturbance to the postclosure controlled area and to areas outside the 
controlled area where conditions may affect isolation within the 
controlled area.
    (6) Administrative controls, which are the provisions relating to 
organization and management, procedures, recordkeeping, review and 
audit, and reporting necessary to assure that activities at the facility 
are conducted in a safe manner and in conformity with the other license 
specifications.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28221, June 21, 1983; 
61 FR 64268, Dec. 4, 1996]



Sec. 60.44  Changes, tests, and experiments.

    (a)(1) Following authorization to receive and possess source, 
special nuclear, or byproduct material at a geologic repository 
operations area, the DOE may (i) make changes in the geologic repository 
operations area as described in the application, (ii) make changes in 
the procedures as described

[[Page 192]]

in the application, and (iii) conduct tests or experiments not described 
in the application, without prior Commission approval, provided the 
change, test, or experiment involves neither a change in the license 
conditions incorporated in the license nor an unreviewed safety 
question.
    (2) A proposed change, test, or experiment shall be deemed to 
involve an unreviewed safety question if (i) the likelihood of 
occurrence or the consequences of an accident or malfunction of 
equipment important to safety previously evaluated in the application is 
increased, (ii) the possibility of an accident or malfunction of a 
different type than any previously evaluated in the application is 
created, or (iii) the margin of safety as defined in the basis for any 
license condition is reduced.
    (b) The DOE shall maintain records of changes in the geologic 
repository operations area and of changes in procedures made pursuant to 
this section, to the extent that such changes constitute changes in the 
geologic repository operations area or procedures as described in the 
application. Records of tests and experiments carried out pursuant to 
paragraph (a) of this section shall also be maintained. These records 
shall include a written safety evaluation which provides the basis for 
the determination that the change, test, or experiment does not involve 
an unreviewed safety question. The DOE shall prepare annually, or at 
such shorter intervals as may be specified in the license, a report 
containing a brief description of such changes, tests, and experiments, 
including a summary of the safety evaluation of each. The DOE shall 
furnish the report to the appropriate NRC Regional Office shown in 
appendix D to part 20 of this chapter, by an appropriate method listed 
in Sec. 60.4(a), with a copy to the Director of the NRC's Office of 
Nuclear Material Safety and Safeguards. Any report submitted pursuant to 
this paragraph shall be made a part of the public record of the 
licensing proceedings.

[46 FR 13980, Feb. 25, 1981, as amended at 52 FR 31612, Aug. 21, 1987; 
68 FR 58814, Oct. 10, 2003]



Sec. 60.45  Amendment of license.

    (a) An application for amendment of a license may be filed with the 
Commission fully describing the changes desired and following as far as 
applicable the format prescribed for license applications.
    (b) In determining whether an amendment of a license will be 
approved, the Commission will be guided by the considerations that 
govern the issuance of the initial license, to the extent applicable.



Sec. 60.46  Particular activities requiring license amendment.

    (a) Unless expressly authorized in the license, an amendment of the 
license shall be required with respect to any of the following 
activities:
    (1) Any action which would make emplaced high-level radioactive 
waste irretrievable or which would substantially increase the difficulty 
of retrieving such emplaced waste.
    (2) Dismantling of structures.
    (3) Removal or reduction of controls applied to restrict access to 
or avoid disturbance of the controlled area and to areas outside the 
postclosure controlled area where conditions may affect isolation within 
the controlled area.
    (4) Destruction or disposal of records required to be maintained 
under the provisions of this part.
    (5) Any substantial change to the design or operating procedures 
from that specified in the license.
    (6) Permanent closure.
    (7) Any other activity involving an unreviewed safety question.
    (b) An application for such an amendment shall be filed, and shall 
be reviewed, in accordance with the provisions of Sec. 60.45.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28221, June 21, 1983; 
61 FR 64268, Dec. 4, 1996]

                      US/IAEA Safeguards Agreement



Sec. 60.47  Facility information and verification.

    (a) In response to a written request by the Commission, each 
applicant for a construction authorization or license and each recipient 
of a construction authorization or a license shall submit

[[Page 193]]

facility information, as described in Sec. 75.10 of this chapter, on 
Form N-71 and associated forms, and site information on DOC/NRC Form AP-
A and associated forms;
    (b) As required by the Additional Protocol, applicants and licensees 
specified in paragraph (a) of this section shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms;
    (c) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA) and take other action as necessary to implement the 
US/IAEA Safeguards Agreement, as described in part 75 of this chapter.

[73 FR 78605, Dec. 23, 2008]

                            Permanent Closure



Sec. 60.51  License amendment for permanent closure.

    (a) DOE shall submit an application to amend the license prior to 
permanent closure. The submission shall consist of an update of the 
license application submitted under Sec. Sec. 60.21 and 60.22, 
including:
    (1) A description of the program for post-permanent closure 
monitoring of the geologic repository.
    (2) A detailed description of the measures to be employed--such as 
land use controls, construction of monuments, and preservation of 
records--to regulate or prevent activities that could impair the long-
term isolation of emplaced waste within the geologic repository and to 
assure that relevant information will be preserved for the use of future 
generations. As a minimum, such measures shall include:
    (i) Identification of the postclosure controlled area and geologic 
repository operations area by monuments that have been designed, 
fabricated, and emplaced to be as permanent as is practicable; and
    (ii) Placement of records in the archives and land record systems of 
local State, and Federal government agencies, and archives elsewhere in 
the world, that would be likely to be consulted by potential human 
intruders--such records to identify the location of the geologic 
repository operations area, including the underground facility, 
boreholes and shafts, and the boundaries of the postclosure controlled 
area, and the nature and hazard of the waste.
    (3) Geologic, geophysical, geochemical, hydrologic, and other site 
data that are obtained during the operational period pertinent to the 
long-term isolation of emplaced radioactive wastes.
    (4) The results of tests, experiments, and any other analyses 
relating to backfill of excavated areas, shaft sealing, waste 
interaction with the host rock, and any other tests, experiments, or 
analyses pertinent to the long-term isolation of emplaced wastes within 
the geologic repository.
    (5) Any substantial revision of plans for permanent closure.
    (6) Other information bearing upon permanent closure that was not 
available at the time a license was issued.
    (b) If necessary, so as to take into account the environmental 
impact of any substantial changes in the permanent closure activities 
proposed to be carried out or any significant new information regarding 
the environmental impacts of such closure, DOE shall also supplement its 
environmental impact statement and submit such statement, as 
supplemented, with the application for license amendment.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28221, June 21, 1983; 
54 FR 27872, July 3, 1989; 61 FR 64268, Dec. 4, 1996]



Sec. 60.52  Termination of license.

    (a) Following permanent closure and the decontamination or 
dismantlement of surface facilities, DOE may apply for an amendment to 
terminate the license.
    (b) Such application shall be filed, and will be reviewed, in 
accordance with the provisions of Sec. 60.45 and this section.
    (c) A license shall be terminated only when the Commission finds 
with respect to the geologic repository:
    (1) That the final disposition of radioactive wastes has been made 
in conformance with the DOE's plan, as amended and approved as part of 
the license.
    (2) That the final state of the geologic repository operations area 
conforms to DOE's plans for permanent

[[Page 194]]

closure and DOE's plans for the decontamination or dismantlement of 
surface facilities, as amended and approved as part of the license.
    (3) That the termination of the license is authorized by law, 
including sections 57, 62, and 81 of the Atomic Energy Act, as amended.

[46 FR 13980, Feb. 25, 1981, as amended at 48 FR 28222, June 21, 1983]



 Subpart C_Participation by State Governments and Affected Indian Tribes

    Source: 51 FR 27164, July 30, 1986, unless otherwise noted.



Sec. 60.61  Provision of information.

    (a) The Director shall provide to the Governor and legislature of 
any State in which a geologic repository operations area is or may be 
located, and to the governing body of any affected Indian Tribe, timely 
and complete information regarding determinations or plans made by the 
Commission with respect to the site characterization, siting, 
development, design, licensing, construction, operation, regulation, 
permanent closure, or decontamination and dismantlement of surface 
facilities, of such geologic repository operations area.
    (b) For purposes of this section, a geologic repository operations 
area shall be considered to be one which ``may be located'' in a State 
if the location thereof in such State has been described in a site 
characterization plan submitted to the Commission under this part.
    (c) Notwithstanding paragraph (a) of this section, the Director is 
not required to distribute any document to any entity if, with respect 
to such document, that entity or its counsel is included on a service 
list prepared pursuant to part 2 of this chapter.
    (d) Copies of all communications by the Director under this section 
are available at the NRC Web site, http://www.nrc.gov, and/or at the NRC 
Public Document Room, and copies are furnished to DOE.

[51 FR 27164, July 30, 1986, as amended at 64 FR 48954, Sept. 9, 1999]



Sec. 60.62  Site review.

    (a) Whenever an area has been approved by the President for site 
characterization, and upon request of a State or an affected Indian 
Tribe, the Director shall make NRC staff available to consult with 
representatives of such States and Tribes.
    (b) Requests for consultation shall be made in writing to the 
Director.
    (c) Consultation under this section may include:
    (1) Keeping the parties informed of the Director's views on the 
progress of site characterization.
    (2) Review of applicable NRC regulations, licensing procedures, 
schedules, and opportunities for State and Tribe participation in the 
Commission's regulatory activities.
    (3) Cooperation in development of proposals for State and Tribe 
participation in license reviews.



Sec. 60.63  Participation in license reviews.

    (a) State, local governmental bodies, and affected, Federally-
recognized Indian Tribes may participate in license reviews as provided 
in subpart J of part 2 of this chapter. A State in which a repository 
for high-level radioactive waste is proposed to be located and any 
affected, Federally-recognized Indian Tribe shall have an unquestionable 
legal right to participate as a party in such proceedings.
    (b) In addition, whenever an area has been approved by the President 
for site characterization, a State or an affected Indian Tribe may 
submit to the Director a proposal to facilitate its participation in the 
review of a site characterization plan and/or license application. The 
proposal may be submitted at any time and must contain a description and 
schedule of how the State or affected Indian Tribe wishes to participate 
in the review, or what services or activities the State or affected 
Indian Tribe wishes NRC to carry out, and how the services or activities 
proposed to be carried out by NRC would contribute to such 
participation. The proposal may include educational or information 
services (seminars, public meetings) or other actions on the part

[[Page 195]]

of NRC, such as employment or exchange of State personnel under the 
Intergovernmental Personnel Act.
    (c) The Director shall arrange for a meeting between the 
representatives of the State or affected Indian Tribe and the NRC staff 
to discuss any proposal submitted under paragraph (b) of this section, 
with a view to identifying any modifications that may contribute to the 
effective participation by such State or Tribe.
    (d) Subject to the availability of funds, the Director shall approve 
all or any part of a proposal, as it may be modified through the meeting 
described above, if it is determined that:
    (1) The proposed activities are suitable in light of the type and 
magnitude of impacts which the State or affected Indian Tribe may bear;
    (2) The proposed activities:
    (i) Will enhance communications between NRC and the State or 
affected Indian Tribe;
    (ii) Will make a productive and timely contribution to the review; 
and
    (iii) Are authorized by law.
    (e) The Director will advise the State or affected Indian Tribe 
whether its proposal has been accepted or denied, and if all or any part 
of proposal is denied, the Director shall state the reason for the 
denial.
    (f) Proposals submitted under this section, and responses thereto, 
shall be made available at the NRC Web site, http://www.nrc.gov, and/or 
at the NRC Public Document Room.

[51 FR 27164, July 30, 1986, as amended at 64 FR 48954, Sept. 9, 1999; 
69 FR 2279, Jan. 14, 2004]



Sec. 60.64  Notice to States.

    If the Governor and legislature of a State have jointly designated 
on their behalf a single person or entity to receive notice and 
information from the Commission under this part, the Commission will 
provide such notice and information to the jointly designated person or 
entity instead of the Governor and legislature separately.



Sec. 60.65  Representation.

    Any person who acts under this subpart as a representative for a 
State (or for the Governor or legislature thereof) or for an affected 
Indian Tribe shall include in the request or other submission, or at the 
request of the Commission, a statement of the basis of his or her 
authority to act in such representative capacity.



           Subpart D_Records, Reports, Tests, and Inspections



Sec. 60.71  Records and reports.

    (a) DOE shall maintain such records and make such reports in 
connection with the licensed activity as may be required by the 
conditions of the license or by rules, regulations, and orders of the 
Commission as authorized by the Atomic Energy Act and the Energy 
Reorganization Act.
    (b) Records of the receipt, handling, and disposition of radioactive 
waste at a geologic repository operations area shall contain sufficient 
information to provide a complete history of the movement of the waste 
from the shipper through all phases of storage and disposal. DOE shall 
retain these records in a manner that ensures their useability for 
future generations in accordance with Sec. 60.51(a)(2).

[48 FR 28222, June 21, 1983, as amended at 53 FR 19251, May 27, 1988]



Sec. 60.72  Construction records.

    (a) DOE shall maintain records of construction of the geologic 
repository operations area in a manner that ensures their useability for 
future generations in accordance with Sec. 60.51(a)(2).
    (b) The records required under paragraph (a) shall include at least 
the following:
    (1) Surveys of the underground facility excavations, shafts, and 
boreholes referenced to readily identifiable surface features or 
monuments;
    (2) A description of the materials encountered;
    (3) Geologic maps and geologic cross sections;
    (4) Locations and amount of seepage;
    (5) Details of equipment, methods, progress, and sequence of work;
    (6) Construction problems;
    (7) Anomalous conditions encountered;
    (8) Instrument locations, readings, and analysis;

[[Page 196]]

    (9) Location and description of structural support systems;
    (10) Location and description of dewatering systems; and
    (11) Details, methods of emplacement, and location of seals used.

[48 FR 28222, June 21, 1983, as amended at 53 FR 19251, May 27, 1988]



Sec. 60.73  Reports of deficiencies.

    DOE shall promptly notify the Commission of each deficiency found in 
the characteristics of the site, and design and construction of the 
geologic repository operations area which, were it to remain 
uncorrected, could: (a) Be a substantial safety hazard, (b) represent a 
significant deviation from the design criteria and design bases stated 
in the application, or (c) represent a deviation from the conditions 
stated in the terms of a construction authorization or the license, 
including license specifications. The notification shall be in the form 
of a written report, copies of which shall be sent to the Director and 
to the appropriate Nuclear Regulatory Commission Regional Office listed 
in appendix D of part 20 of this chapter.

[48 FR 28222, June 21, 1983]



Sec. 60.74  Tests.

    (a) DOE shall perform, or permit the Commission to perform, such 
tests as the Commission deems appropriate or necessary for the 
administration of the regulations in this part. These may include tests 
of:
    (1) Radioactive waste,
    (2) The geologic repository including its structures, systems, and 
components,
    (3) Radiation detection and monitoring instruments, and
    (4) Other equipment and devices used in connection with the receipt, 
handling, or storage of radioactive waste.
    (b) The tests required under this section shall include a 
performance confirmation program carried out in accordance with subpart 
F of this part.

[48 FR 28222, June 21, 1983]



Sec. 60.75  Inspections.

    (a) DOE shall allow the Commission to inspect the premises of the 
geologic repository operations area and adjacent areas to which DOE has 
rights of access.
    (b) DOE shall make available to the Commission for inspection, upon 
reasonable notice, records kept by DOE pertaining to activities under 
this part.
    (c)(1) DOE shall upon requests by the Director, Office of Nuclear 
Material Safety and Safeguards, provide rent-free office space for the 
exclusive use of the Commission inspection personnel. Heat, air-
conditioning, light, electrical outlets and janitorial services shall be 
furnished by DOE. The office shall be convenient to and have full access 
to the facility and shall provide the inspector both visual and acoustic 
privacy.
    (2) The space provided shall be adequate to accommodate a full-time 
inspector, a part-time secretary and transient NRC personnel and will be 
generally commensurate with other office facilities at the geologic 
repository operations area. A space of 250 square feet either within the 
geologic repository operations area's office complex or in an office 
trailer or other onsite space at the geologic repository operations area 
is suggested as a guide. For locations at which activities are carried 
out under licenses issued under other parts of this chapter, additional 
space may be requested to accommodate additional full-time inspectors. 
The Office space that is provided shall be subject to the approval of 
the Director, Office of Nuclear Material Safety and Safeguards. All 
furniture, supplies and communication equipment will be furnished by the 
Commission.
    (3) DOE shall afford any NRC resident inspector assigned to that 
location, or other NRC inspectors identified by the Regional 
Administrator as likely to inspect the facility, immediate unfettered 
access, equivalent to access provided regular employees, following 
proper identification and compliance with applicable access control 
measures for security, radiological protection and personal safety.

[48 FR 28222, June 21, 1983, as amended at 52 FR 31612, Aug. 21, 1987; 
76 FR 72086, Nov. 22, 2011]

[[Page 197]]



Sec. 60.78  Material control and accounting records and reports.

    DOE shall implement a program of material control and accounting 
(and accidental criticality reporting) that is the same as that 
specified in Sec. Sec. 72.72, 72.74, 72.76, and 72.78 of this chapter.

[63 FR 26961, May 15, 1998]



                      Subpart E_Technical Criteria

    Source: 48 FR 28222, June 21, 1983, unless otherwise noted.



Sec. 60.101  Purpose and nature of findings.

    (a)(1) Subpart B of this part prescribes the standards for issuance 
of a license to receive and possess source, special nuclear, or 
byproduct material at a geologic repository operations area. In 
particular, Sec. 60.41(c) requires a finding that the issuance of a 
license will not constitute an unreasonable risk to the health and 
safety of the public. The purpose of this subpart is to set out 
performance objectives and site and design criteria which, if satisfied, 
will support such a finding of no unreasonable risk.
    (2) While these performance objectives and criteria are generally 
stated in unqualified terms, it is not expected that complete assurance 
that they will be met can be presented. A reasonable assurance, on the 
basis of the record before the Commission, that the objectives and 
criteria will be met is the general standard that is required. For Sec. 
60.112, and other portions of this subpart that impose objectives and 
criteria for repository performance over long times into the future, 
there will inevitably be greater uncertainties. Proof of the future 
performance of engineered barrier systems and the geologic setting over 
time periods of many hundreds or many thousands of years is not to be 
had in the ordinary sense of the word. For such long-term objectives and 
criteria, what is required is reasonable assurance, making allowance for 
the time period, hazards, and uncertainties involved, that the outcome 
will be in conformance with those objectives and criteria. Demonstration 
of compliance with such objectives and criteria will involve the use of 
data from accelerated tests and predictive models that are supported by 
such measures as field and laboratory tests, monitoring data and natural 
analog studies.
    (b) Subpart B of this part also lists findings that must be made in 
support of an authorization to construct a geologic repository 
operations area. In particular, Sec. 60.31(a) requires a finding that 
there is reasonable assurance that the types and amounts of radioactive 
materials described in the application can be received, possessed, and 
disposed of in a geologic repository operations area of the design 
proposed without unreasonable risk to the health and safety of the 
public. As stated in that paragraph, in arriving at this determination, 
the Commission will consider whether the site and design comply with the 
criteria contained in this subpart. Once again, while the criteria may 
be written in unqualified terms, the demonstration of compliance may 
take uncertainties and gaps in knowledge into account, provided that the 
Commission can make the specified finding of reasonable assurance as 
specified in paragraph (a) of this section.



Sec. 60.102  Concepts.

    This section provides a functional overview of subpart E. In the 
event of any inconsistency with definitions found in Sec. 60.2, those 
definitions shall prevail.
    (a) The HLW facility. NRC exercises licensing and related regulatory 
authority over those facilities described in section 202 (3) and (4) of 
the Energy Reorganization Act of 1974. Any of these facilities is 
designated a HLW facility.
    (b) The geologic repository operations area. (1) This part deals 
with the exercise of authority with respect to a particular class of HLW 
facility--namely a geologic repository operations area.
    (2) A geologic repository operations area consists of those surface 
and subsurface areas that are part of a geologic repository where 
radioactive waste handling activities are conducted. The underground 
structure, including openings and backfill materials, but excluding 
shafts, boreholes, and their seals, is designated the underground 
facility.

[[Page 198]]

    (3) The exercise of Commission authority requires that the geologic 
repository operations area be used for storage (which includes disposal) 
of high-level radioactive wastes (HLW).
    (4) HLW includes irradiated reactor fuel as well as reprocessing 
wastes. However, if DOE proposes to use the geologic repository 
operations area for storage of radioactive waste other than HLW, the 
storage of this radioactive waste is subject to the requirements of this 
part.
    (c) Areas related to isolation. Although the activities subject to 
regulation under this part are those to be carried out at the geologic 
repository operations area, the licensing process also considers 
characteristics of adjacent areas that are defined in other ways. There 
is to be an area surrounding the underground facility referred to above, 
which is designated the postclosure controlled area, within which DOE is 
to exercise specified controls to prevent adverse human actions 
following permanent closure. The location of the controlled area is the 
site. The accessible environment is the atmosphere, land surface, 
surface water, oceans, and the portion of the lithosphere that is 
outside the controlled area. There is an area, designated the geologic 
setting, which includes the geologic, hydrologic, and geochemical 
systems of the region in which a geologic repository operations area is 
or may be located. The geologic repository operations area plus the 
portion of the geologic setting that provides isolation of the 
radioactive waste make up the geologic repository.
    (d) Stages in the licensing process. There are several stages in the 
licensing process. The site characterization stage, though begun before 
submission of a license application, may result in consequences 
requiring evaluation in the license review. The construction stage would 
follow, after issuance of a construction authorization. A period of 
operations follows the issuance of a license by the Commission. The 
period of operations includes the time during which emplacement of 
wastes occurs; any subsequent period before permanent closure during 
which the emplaced wastes are retrievable; and permanent closure, which 
includes sealing of shafts. Permanent closure represents the end of 
active human intervention with respect to the engineered barrier system.
    (e) Isolation of waste. (1) During the first several hundred years 
following permanent closure of a geologic repository, when radiation and 
thermal levels are high and the uncertainties in assessing repository 
performance are large, special emphasis is placed upon the ability to 
contain the wastes by waste packages within an engineered barrier 
system. This is known as the containment period. The engineered barrier 
system includes the waste packages and the underground facility. A waste 
package is composed of the waste form and any containers, shielding, 
packing, and absorbent materials immediately surrounding an individual 
waste container. The underground facility means the underground 
structure, including openings and backfill materials, but excluding, 
shafts, boreholes, and their seals.
    (2) Following the containment period special emphasis is placed upon 
the ability to achieve isolation of the wastes by virtue of the 
characteristics of the geologic repository. The engineered barrier 
system works to control the release of radioactive material to the 
geologic setting and the geologic setting works to control the release 
of radioactive material to the accessible environment. Isolation means 
inhibiting the transport of radioactive material so that amounts and 
concentrations of the materials entering the accessible environment will 
be kept within prescribed limits.

[48 FR 28222, June 21, 1983, as amended at 61 FR 64268, Dec. 4, 1996]

                         Performance Objectives



Sec. 60.111  Performance of the geologic repository operations area
through permanent closure.

    (a) Protection against radiation exposures and releases of 
radioactive material. The geologic repository operations area shall be 
designed so that until permanent closure has been completed, radiation 
exposures and radiation levels, and releases of radioactive materials to 
unrestricted areas, will be maintained within the limits specified in 
part 20 of

[[Page 199]]

this chapter and such generally applicable environmental standards for 
radioactivity as may have been established by the Environmental 
Protection Agency.
    (b) Retrievability of waste. (1) The geologic repository operations 
area shall be designed to preserve the option of waste retrieval 
throughout the period during which wastes are being emplaced and, 
thereafter, until the completion of a preformance confirmation program 
and Commission review of the information obtained from such a program. 
To satisfy this objective, the geologic repository operations area shall 
be designed so that any or all of the emplaced waste could be retrieved 
on a reasonable schedule starting at any time up to 50 years after waste 
emplacement operations are initiated, unless a different time period is 
approved or specified by the Commission. This different time period may 
be established on a case-by-case basis consistent with the emplacement 
schedule and the planned performance confirmation program.
    (2) This requirement shall not preclude decisions by the Commission 
to allow backfilling part or all of, or permanent closure of, the 
geologic repository operations area prior to the end of the period of 
design for retrievability.
    (3) For purposes of this paragraph, a reasonable schedule for 
retrieval is one that would permit retrieval in about the same time as 
that devoted to construction of the geologic repository operations area 
and the emplacement of wastes.

[48 FR 28222, June 21, 1983, as amended at 61 FR 64268, Dec. 4, 1996; 62 
FR 59276, Nov. 3, 1997]



Sec. 60.112  Overall system performance objective for the geologic
repository after permanent closure.

    The geologic setting shall be selected and the engineered barrier 
system and the shafts, boreholes and their seals shall be designed to 
assure that releases of radioactive materials to the accessible 
environment following permanent closure conform to such generally 
applicable environmental standards for radioactivity as may have been 
established by the Environmental Protection Agency with respect to both 
anticipated processes and events and unanticipated processes and events.



Sec. 60.113  Performance of particular barriers after permanent closure.

    (a) General provisions--(1) Engineered barrier system. (i) The 
engineered barrier system shall be designed so that assuming anticipated 
processes and events: (A) Containment of HLW will be substantially 
complete during the period when radiation and thermal conditions in the 
engineered barrier system are dominated by fission product decay; and 
(B) any release of radionuclides from the engineered barrier system 
shall be a gradual process which results in small fractional releases to 
the geologic setting over long times. For disposal in the saturated 
zone, both the partial and complete filling with groundwater of 
available void spaces in the underground facility shall be appropriately 
considered and analysed among the anticipated processes and events in 
designing the engineered barrier system.
    (ii) In satisfying the preceding requirement, the engineered barrier 
system shall be designed, assuming anticipated processes and events, so 
that:
    (A) Containment of HLW within the waste packages will be 
substantially complete for a period to be determined by the Commission 
taking into account the factors specified in Sec. 60.113(b) provided, 
that such period shall be not less than 300 years nor more than 1,000 
years after permanent closure of the geologic repository; and
    (B) The release rate of any radionuclide from the engineered barrier 
system following the containment period shall not exceed one part in 
100,000 per year of the inventory of that radionuclide calculated to be 
present at 1,000 years following permanent closure, or such other 
fraction of the inventory as may be approved or specified by the 
Commission; provided, that this requirement does not apply to any 
radionuclide which is released at a rate less than 0.1% of the 
calculated total release rate limit. The calculated total release rate 
limit shall be taken to be

[[Page 200]]

one part in 100,000 per year of the inventory of radioactive waste, 
originally emplaced in the underground facility, that remains after 
1,000 years of radioactive decay.
    (2) Geologic setting. The geologic repository shall be located so 
that pre-waste-emplacement groundwater travel time along the fastest 
path of likely radionuclide travel from the disturbed zone to the 
accessible environment shall be at least 1,000 years or such other 
travel time as may be approved or specified by the Commission.
    (b) On a case-by-case basis, the Commission may approve or specify 
some other radionuclide release rate, designed containment period or 
pre-waste-emplacement groundwater travel time, provided that the overall 
system performance objective, as it relates to anticipated processes and 
events, is satisfied. Among the factors that the Commission may take 
into account are:
    (1) Any generally applicable environmental standard for 
radioactivity established by the Environmental Protection Agency;
    (2) The age and nature of the waste, and the design of the 
underground facility, particularly as these factors bear upon the time 
during which the thermal pulse is dominated by the decay heat from the 
fission products;
    (3) The geochemical characteristics of the host rock, surrounding 
strata and groundwater; and
    (4) Particular sources of uncertainty in predicting the performance 
of the geologic repository.
    (c) Additional requirements may be found to be necessary to satisfy 
the overall system performance objective as it relates to unanticipated 
processes and events.

                       Land Ownership and Control



Sec. 60.121  Requirements for ownership and control of interests 
in land.

    (a) Ownership of land. (1) Both the geologic repository operations 
area and the postclosure controlled area shall be located in and on 
lands that are either acquired lands under the jurisdiction and control 
of DOE, or lands permanently withdrawn and reserved for its use.
    (2) These lands shall be held free and clear of all encumbrances, if 
significant, such as: (i) Rights arising under the general mining laws; 
(ii) easements for right-of-way; and (iii) all other rights arising 
under lease, rights of entry, deed, patent, mortgage, appropriation, 
prescription, or otherwise.
    (b) Additional controls. Appropriate controls shall be established 
outside of the postclosure controlled area. DOE shall exercise any 
jurisdiction and control over surface and subsurface estates necessary 
to prevent adverse human actions that could significantly reduce the 
geologic repository's ability to achieve isolation. The rights of DOE 
may take the form of appropriate possessory interests, servitudes, or 
withdrawals from location or patent under the general mining laws.
    (c) Water rights. (1) DOE shall also have obtained such water rights 
as may be needed to accomplish the purpose of the geologic repository 
operations area.
    (2) Water rights are included in the additional controls to be 
established under paragraph (b) of this section.

[48 FR 28222, June 21, 1983, as amended at 61 FR 64268, Dec. 4, 1996]

                             Siting Criteria



Sec. 60.122  Siting criteria.

    (a)(1) A geologic setting shall exhibit an appropriate combination 
of the conditions specified in paragraph (b) of this section so that, 
together with the engineered barriers system, the favorable conditions 
present are sufficient to provide reasonable assurance that the 
performance objectives relating to isolation of the waste will be met.
    (2) If any of the potentially adverse conditions specified in 
paragraph (c) of this section is present, it may compromise the ability 
of the geologic repository to meet the performance objectives relating 
to isolation of the waste. In order to show that a potentially adverse 
condition does not so compromise the performance of the geologic 
repository the following must be demonstrated:
    (i) The potentially adverse human activity or natural condition has 
been adequately investigated, including the extent to which the 
condition may be

[[Page 201]]

present and still be undetected taking into account the degree of 
resolution achieved by the investigations; and
    (ii) The effect of the potentially adverse human activity or natural 
condition on the site has been adequately evaluated using analyses which 
are sensitive to the potentially adverse human activity or natural 
condition and assumptions which are not likely to underestimate its 
effect; and
    (iii)(A) The potentially adverse human activity or natural condition 
is shown by analysis pursuant to paragraph (a)(2)(ii) of this section 
not to affect significantly the ability of the geologic repository to 
meet the performance objectives relating to isolation of the waste, or
    (B) The effect of the potentially adverse human activity or natural 
condition is compensated by the presence of a combination of the 
favorable characteristics so that the performance objectives relating to 
isolation of the waste are met, or
    (C) The potentially adverse human activity or natural condition can 
be remedied.
    (b) Favorable conditions. (1) The nature and rates of tectonic, 
hydrogeologic, geochemical, and geomorphic processes (or any of such 
processes) operating within the geologic setting during the Quaternary 
Period, when projected, would not affect or would favorably affect the 
ability of the geologic repository to isolate the waste.
    (2) For disposal in the saturated zone, hydrogeologic conditions 
that provide:
    (i) A host rock with low horizontal and vertical permeability;
    (ii) Downward or dominantly horizontal hydraulic gradient in the 
host rock and immediately surrounding hydrogeologic units; and
    (iii) Low vertical permeability and low hydraulic gradient between 
the host rock and the surrounding hydrogeologic units.
    (3) Geochemical conditions that:
    (i) Promote precipitation or sorption of radionuclides;
    (ii) Inhibit the formation of particulates, colloids, and inorganic 
and organic complexes that increase the mobility of radionuclides; or
    (iii) Inhibit the transport of radionuclides by particulates, 
colloids, and complexes.
    (4) Mineral assemblages that, when subjected to anticipated thermal 
loading, will remain unaltered or alter to mineral assemblages having 
equal or increased capacity to inhibit radionuclide migration.
    (5) Conditions that permit the emplacement of waste at a minimum 
depth of 300 meters from the ground surface. (The ground surface shall 
be deemed to be the elevation of the lowest point on the surface above 
the disturbed zone.)
    (6) A low population density within the geologic setting and a 
postclosure controlled area that is remote from population centers.
    (7) Pre-waste-emplacement groundwater travel time along the fastest 
path of likely radionuclide travel from the disturbed zone to the 
accessible environment that substantially exceeds 1,000 years.
    (8) For disposal in the unsaturated zone, hydrogeologic conditions 
that provide--
    (i) Low moisture flux in the host rock and in the overlying and 
underlying hydrogeologic units;
    (ii) A water table sufficiently below the underground facility such 
that fully saturated voids contiguous with the water table do not 
encounter the underground facility;
    (iii) A laterally extensive low-permeability hydrogeologic unit 
above the host rock that would inhibit the downward movement of water or 
divert downward moving water to a location beyond the limits of the 
underground facility;
    (iv) A host rock that provides for free drainage; or
    (v) A climatic regime in which the average annual historic 
precipitation is a small percentage of the average annual potential 
evapotranspiration.
    (c) Potentially adverse conditions. The following conditions are 
potentially adverse conditions if they are characteristic of the 
postclosure controlled area or may affect isolation within the 
controlled area.
    (1) Potential for flooding of the underground facility, whether 
resulting from the occupancy and modification

[[Page 202]]

of floodplains or from the failure of existing or planned man-made 
surface water impoundments.
    (2) Potential for foreseeable human activity to adversely affect the 
groundwater flow system, such as groundwater withdrawal, extensive 
irrigation, subsurface injection of fluids, underground pumped storage, 
military activity or construction of large scale surface water 
impoundments.
    (3) Potential for natural phenomena such as landslides, subsidence, 
or volcanic activity of such a magnitude that large-scale surface water 
impoundments could be created that could change the regional groundwater 
flow system and thereby adversely affect the performance of the geologic 
repository.
    (4) Structural deformation, such as uplift, subsidence, folding, or 
faulting that may adversely affect the regional groundwater flow system.
    (5) Potential for changes in hydrologic conditions that would affect 
the migration of radionuclides to the accessible environment, such as 
changes in hydraulic gradient, average interstitial velocity, storage 
coefficient, hydraulic conductivity, natural recharge, potentiometric 
levels, and discharge points.
    (6) Potential for changes in hydrologic conditions resulting from 
reasonably foreseeable climatic changes.
    (7) Groundwater conditions in the host rock, including chemical 
composition, high ionic strength or ranges of Eh-pH, that could increase 
the solubility or chemical reactivity of the engineered barrier system.
    (8) Geochemical processes that would reduce sorption of 
radionuclides, result in degradation of the rock strength, or adversely 
affect the performance of the engineered barrier system.
    (9) Groundwater conditions in the host rock that are not reducing.
    (10) Evidence of dissolutioning such as breccia pipes, dissolution 
cavities, or brine pockets.
    (11) Structural deformation such as uplift, subsidence, folding, and 
faulting during the Quaternary Period.
    (12) Earthquakes which have occurred historically that if they were 
to be repeated could affect the site significantly.
    (13) Indications, based on correlations of earthquakes with tectonic 
processes and features, that either the frequency of occurrence or 
magnitude of earthquakes may increase.
    (14) More frequent occurrence of earthquakes or earthquakes of 
higher magnitude than is typical of the area in which the geologic 
setting is located.
    (15) Evidence of igneous activity since the start of the Quaternary 
Period.
    (16) Evidence of extreme erosion during the Quaternary Period.
    (17) The presence of naturally occurring materials, whether 
identified or undiscovered, within the site, in such form that:
    (i) Economic extraction is currently feasible or potentially 
feasible during the foreseeable future; or
    (ii) Such materials have greater gross value or net value than the 
average for other areas of similar size that are representative of and 
located within the geologic setting.
    (18) Evidence of subsurface mining for resources within the site.
    (19) Evidence of drilling for any purpose within the site.
    (20) Rock or groundwater conditions that would require complex 
engineering measures in the design and construction of the underground 
facility or in the sealing of boreholes and shafts.
    (21) Geomechanical properties that do not permit design of 
underground opening that will remain stable through permanent closure.
    (22) Potential for the water table to rise sufficiently so as to 
cause saturation of an underground facility located in the unsaturated 
zone.
    (23) Potential for existing or future perched water bodies that may 
saturate portions of the underground facility or provide a faster flow 
path from an underground facility located in the unsaturated zone to the 
accessible environment.
    (24) Potential for the movement of radionuclides in a gaseous state

[[Page 203]]

through air-filled pore spaces of an unsaturated geologic medium to the 
accessible environment.

[48 FR 28222, June 21, 1983, as amended at 50 FR 29647, July 22, 1985; 
61 FR 64269, Dec. 4, 1996]

       Design Criteria for the Geologic Repository Operations Area



Sec. 60.130  General considerations.

    (a) Pursuant to the provisions of Sec. 60.21(c)(2)(i), an 
application for construction authorization for a high-level radioactive 
waste repository at a geologic repository operations area, and an 
application for a license to receive, possess, store, and dispose of 
high-level radioactive waste in the geologic repository operations area, 
must include the principal design criteria for a proposed facility. The 
principal design criteria establish the necessary design, fabrication, 
construction, testing, maintenance, and performance requirements for 
structures, systems, and components important to safety and/or important 
to waste isolation. Sections 60.131 through 60.134 specify minimum 
requirements for the principal design criteria for the geologic 
repository operations area.
    (b) These design criteria are not intended to be exhaustive. 
However, omissions in Sec. Sec. 60.131 through 60.134 do not relieve 
DOE from any obligation to provide such features in a specific facility 
needed to achieve the performance objectives.

[69 FR 2280, Jan. 14, 2004]



Sec. 60.131  General design criteria for the geologic repository 
operations area.

    (a) Radiological protection. The geologic repository operations area 
shall be designed to maintain radiation doses, levels, and 
concentrations of radioactive material in air in restricted areas within 
the limits specified in part 20 of this chapter. Design shall include:
    (1) Means to limit concentrations of radioactive material in air;
    (2) Means to limit the time required to perform work in the vicinity 
of radioactive materials, including, as appropriate, designing equipment 
for ease of repair and replacement and providing adequate space for ease 
of operation;
    (3) Suitable shielding;
    (4) Means to monitor and control the dispersal of radioactive 
contamination;
    (5) Means to control access to high radiation areas or airborne 
radioactivity areas; and
    (6) A radiation alarm system to warn of significant increases in 
radiation levels, concentrations of radioactive material in air, and of 
increased radioactivity released in effluents. The alarm system shall be 
designed with provisions for calibration and for testing its 
operability.
    (b) Protection against design basis events. The structures, systems, 
and components important to safety shall be designed so that they will 
perform their necessary safety functions, assuming occurrence of design 
basis events.
    (c) Protection against dynamic effects of equipment failure and 
similar events. The structures, systems, and components important to 
safety shall be designed to withstand dynamic effects such as missile 
impacts, that could result from equipment failure, and similar events 
and conditions that could lead to loss of their safety functions.
    (d) Protection against fires and explosions. (1) The structures, 
systems, and components important to safety shall be designed to perform 
their safety functions during and after credible fires or explosions in 
the geologic repository operations area.
    (2) To the extent practicable, the geologic repository operations 
area shall be designed to incorporate the use of noncombustible and heat 
resistant materials.
    (3) The geologic repository operations area shall be designed to 
include explosion and fire detection alarm systems and appropriate 
suppression systems with sufficient capacity and capability to reduce 
the adverse effects of fires and explosions on structures, systems, and 
components important to safety.
    (4) The geologic repository operations area shall be designed to 
include means to protect systems, structures, and components important 
to safety against the adverse effects of either the

[[Page 204]]

operation or failure of the fire suppression systems.
    (e) Emergency capability. (1) The structures, systems, and 
components important to safety shall be designed to maintain control of 
radioactive waste and radioactive effluents, and permit prompt 
termination of operations and evacuation of personnel during an 
emergency.
    (2) The geologic repository operations area shall be designed to 
include onsite facilities and services that ensure a safe and timely 
response to emergency conditions and that facilitate the use of 
available offsite services (such as fire, police, medical, and ambulance 
service) that may aid in recovery from emergencies.
    (f) Utility services. (1) Each utility service system that is 
important to safety shall be designed so that essential safety functions 
can be performed, assuming occurrence of the design basis events.
    (2) The utility services important to safety shall include redundant 
systems to the extent necessary to maintain, with adequate capacity, the 
ability to perform their safety functions.
    (3) Provisions shall be made so that, if there is a loss of the 
primary electric power source or circuit, reliable and timely emergency 
power can be provided to instruments, utility service systems, and 
operating systems, including alarm systems, important to safety.
    (g) Inspection, testing, and maintenance. The structures, systems, 
and components important to safety shall be designed to permit periodic 
inspection, testing, and maintenance, as necessary, to ensure their 
continued functioning and readiness.
    (h) Criticality control. All systems for processing, transporting, 
handling, storage, retrieval, emplacement, and isolation of radioactive 
waste shall be designed to ensure that nuclear criticality is not 
possible unless at least two unlikely, independent, and concurrent or 
sequential changes have occurred in the conditions essential to nuclear 
criticality safety. Each system must be designed for criticality safety 
assuming occurrence of design basis events. The calculated effective 
multiplication factor (keff) must be sufficiently below unity 
to show at least a 5 percent margin, after allowance for the bias in the 
method of calculation and the uncertainty in the experiments used to 
validate the method of calculation.
    (i) Instrumentation and control systems. The design shall include 
provisions for instrumentation and control systems to monitor and 
control the behavior of systems important to safety, assuming occurrence 
of design basis events.
    (j) Compliance with mining regulations. To the extent that DOE is 
not subject to the Federal Mine Safety and Health Act of 1977, as to the 
construction and operation of the geologic repository operations area, 
the design of the geologic repository operations area shall nevertheless 
include provisions for worker protection necessary to provide reasonable 
assurance that all structures, systems, and components important to 
safety can perform their intended functions. Any deviation from relevant 
design requirements in 30 CFR, chapter I, subchapters D, E, and N will 
give rise to a rebuttable presumption that this requirement has not been 
met.
    (k) Shaft conveyances used in radioactive waste handling. (1) Hoists 
important to safety shall be designed to preclude cage free fall.
    (2) Hoists important to safety shall be designed with a reliable 
cage location system.
    (3) Loading and unloading systems for hoists important to safety 
shall be designed with a reliable system of interlocks that will fail 
safely upon malfunction.
    (4) Hoists important to safety shall be designed to include two 
independent indicators to indicate when waste packages are in place and 
ready for transfer.

[48 FR 28222, June 21, 1983, as amended at 61 FR 64269, Dec. 4, 1996]



Sec. 60.132  Additional design criteria for surface facilities 
in the geologic repository operations area.

    (a) Facilities for receipt and retrieval of waste. Surface 
facilities in the geologic repository operations area shall be designed 
to allow safe handling and storage of wastes at the geologic repository 
operations area, whether these wastes

[[Page 205]]

are on the surface before emplacement or as a result of retrieval from 
the underground facility.
    (b) Surface facility ventilation. Surface facility ventilation 
systems supporting waste transfer, inspection, decontamination, 
processing, or packaging shall be designed to provide protection against 
radiation exposures and offsite releases as provided in Sec. 60.111(a).
    (c) Radiation control and monitoring--(1) Effluent control. The 
surface facilities shall be designed to control the release of 
radioactive materials in effluents during Category 1 design basis events 
so as to meet the performance objectives of Sec. 60.111(a).
    (2) Effluent monitoring. The effluent monitoring systems shall be 
designed to measure the amount and concentration of radionuclides in any 
effluent with sufficient precision to determine whether releases conform 
to the design requirement for effluent control. The monitoring systems 
shall be designed to include alarms that can be periodically tested.
    (d) Waste treatment. Radioactive waste treatment facilities shall be 
designed to process any radioactive wastes generated at the geologic 
repository operations area into a form suitable to permit safe disposal 
at the geologic repository operations area or to permit safe 
transportation and conversion to a form suitable for disposal at an 
alternative site in accordance with any regulations that are applicable.
    (e) Consideration of decommissioning. The surface facility shall be 
designed to facilitate decontamination or dismantlement to the same 
extent as would be required, under other parts of this chapter, with 
respect to equivalent activities licensed thereunder.

[48 FR 28222, June 21, 1983, as amended at 61 FR 64270, Dec. 4, 1996]



Sec. 60.133  Additional design criteria for the underground facility.

    (a) General criteria for the underground facility. (1) The 
orientation, geometry, layout, and depth of the underground facility, 
and the design of any engineered barriers that are part of the 
underground facility shall contribute to the containment and isolation 
of radionuclides.
    (2) The underground facility shall be designed so that the effects 
of credible disruptive events during the period of operations, such as 
flooding, fires and explosions, will not spread through the facility.
    (b) Flexibility of design. The underground facility shall be 
designed with sufficient flexibility to allow adjustments where 
necessary to accommodate specific site conditions identified through in 
situ monitoring, testing, or excavation.
    (c) Retrieval of waste. The underground facility shall be designed 
to permit retrieval of waste in accordance with the performance 
objectives of Sec. 60.111.
    (d) Control of water and gas. The design of the underground facility 
shall provide for control of water or gas intrusion.
    (e) Underground openings. (1) Openings in the underground facility 
shall be designed so that operations can be carried out safely and the 
retrievability option maintained.
    (2) Openings in the underground facility shall be designed to reduce 
the potential for deleterious rock movement or fracturing of overlying 
or surrounding rock.
    (f) Rock excavation. The design of the underground facility shall 
incorporate excavation methods that will limit the potential for 
creating a preferential pathway for groundwater to contact the waste 
packages or radionuclide migration to the accessible environment.
    (g) Underground facility ventilation. The ventilation system shall 
be designed to:
    (1) Control the transport of radioactive particulates and gases 
within and releases from the underground facility in accordance with the 
performance objectives of Sec. 60.111(a),
    (2) Assure the ability to perform essential safety functions 
assuming occurrence of design basis events.
    (3) Separate the ventilation of excavation and waste emplacement 
areas.
    (h) Engineered barriers. Engineered barriers shall be designed to 
assist the geologic setting in meeting the performance objectives for 
the period following permanent closure.

[[Page 206]]

    (i) Thermal loads. The underground facility shall be designed so 
that the performance objectives will be met taking into account the 
predicted thermal and thermomechanical response of the host rock, and 
surrounding strata, groundwater system.

[48 FR 28222, June 21, 1983, as amended at 50 FR 29648, July 22, 1985; 
61 FR 64270, Dec. 4, 1996]



Sec. 60.134  Design of seals for shafts and boreholes.

    (a) General design criterion. Seals for shafts and boreholes shall 
be designed so that following permanent closure they do not become 
pathways that compromise the geologic repository's ability to meet the 
performance objectives or the period following permanent closure.
    (b) Selection of materials and placement methods. Materials and 
placement methods for seals shall be selected to reduce, to the extent 
practicable:
    (1) The potential for creating a preferential pathway for 
groundwater to contact the waste packages or
    (2) For radionuclide migration through existing pathways.

[48 FR 28222, June 21, 1983, as amended at 50 FR 29648, July 22, 1985]

                  Design Criteria for the Waste Package



Sec. 60.135  Criteria for the waste package and its components.

    (a) High-level-waste package design in general. (1) Packages for HLW 
shall be designed so that the in situ chemical, physical, and nuclear 
properties of the waste package and its interactions with the 
emplacement environment do not compromise the function of the waste 
packages or the performance of the underground facility or the geologic 
setting.
    (2) The design shall include but not be limited to consideration of 
the following factors: solubility, oxidation/reduction reactions, 
corrosion, hydriding, gas generation, thermal effects, mechanical 
strength, mechanical stress, radiolysis, radiation damage, radionuclide 
retardation, leaching, fire and explosion hazards, thermal loads, and 
synergistic interactions.
    (b) Specific criteria for HLW package design--(1) Explosive, 
pyrophoric, and chemically reactive materials. The waste package shall 
not contain explosive or pyrophoric materials or chemically reactive 
materials in an amount that could compromise the ability of the 
underground facility to contribute to waste isolation or the ability of 
the geologic repository to satisfy the performance objectives.
    (2) Free liquids. The waste package shall not contain free liquids 
in an amount that could compromise the ability of the waste packages to 
achieve the performance objectives relating to containment of HLW 
(because of chemical interactions or formation of pressurized vapor) or 
result in spillage and spread of contamination in the event of waste 
package perforation during the period through permanent closure.
    (3) Handling. Waste packages shall be designed to maintain waste 
containment during transportation, emplacement, and retrieval.
    (4) Unique identification. A label or other means of identification 
shall be provided for each waste package. The identification shall not 
impair the integrity of the waste package and shall be applied in such a 
way that the information shall be legible at least to the end of the 
period of retrievability. Each waste package identification shall be 
consistent with the waste package's permanent written records.
    (c) Waste form criteria for HLW. High-level radioactive waste that 
is emplaced in the underground facility shall be designed to meet the 
following criteria:
    (1) Solidification. All such radioactive wastes shall be in solid 
form and placed in sealed containers.
    (2) Consolidation. Particulate waste forms shall be consolidated 
(for example, by incorporation into an encapsulating matrix) to limit 
the availability and generation of particulates.
    (3) Combustibles. All combustible radioactive wastes shall be 
reduced to a noncombustible form unless it can be demonstrated that a 
fire involving the waste packages containing combustibles will not 
compromise the integrity

[[Page 207]]

of other waste packages, adversely affect any structures, systems, or 
components important to safety, or compromise the ability of the 
underground facility to contribute to waste isolation.
    (d) Design criteria for other radioactive wastes. Design criteria 
for waste types other than HLW will be addressed on an individual basis 
if and when they are proposed for disposal in a geologic repository.

                       Preclosure Controlled Area



Sec. 60.136  Preclosure controlled area.

    (a) A preclosure controlled area must be established for the 
geologic repository operations area.
    (b) The geologic repository operations area shall be designed so 
that, for Category 2 design basis events, no individual located on or 
beyond any point on the boundary of the preclosure controlled area will 
receive the more limiting of a total effective dose equivalent of 0.05 
Sv (5 rem), or the sum of the deep-dose equivalent and the committed 
dose equivalent to any individual organ or tissue (other than the lens 
of the eye) of 0.5 Sv (50 rem). The eye dose equivalent shall not exceed 
0.15 Sv (15 rem), and the shallow dose equivalent to skin shall not 
exceed 0.5 Sv (50 rem). The minimum distance from the surface facilities 
in the geologic repository operations area to the boundary of the 
preclosure controlled area must be at least 100 meters.
    (c) The preclosure controlled area may be traversed by a highway, 
railroad, or waterway, so long as appropriate and effective arrangements 
are made to control traffic and to protect public health and safety.

[61 FR 64270, Dec. 4, 1996]

                  Performance Confirmation Requirements



Sec. 60.137  General requirements for performance confirmation.

    The geologic repository operations area shall be designed so as to 
permit implementation of a performance confirmation program that meets 
the requirements of subpart F of this part.



               Subpart F_Performance Confirmation Program

    Source: 48 FR 28228, June 21, 1983, unless otherwise noted.



Sec. 60.140  General requirements.

    (a) The performance confirmation program shall provide data which 
indicates, where practicable, whether:
    (1) Actual subsurface conditions encountered and changes in those 
conditions during construction and waste emplacement operations are 
within the limits assumed in the licensing review; and
    (2) Natural and engineered systems and components required for 
repository operation, or which are designed or assumed to operate as 
barriers after permanent closure, are functioning as intended and 
anticipated.
    (b) The program shall have been started during site characterization 
and it will continue until permanent closure.
    (c) The program shall include in situ monitoring, laboratory and 
field testing, and in situ experiments, as may be appropriate to 
accomplish the objective as stated above.
    (d) The program shall be implemented so that:
    (1) It does not adversely affect the ability of the natural and 
engineered elements of the geologic repository to meet the performance 
objectives.
    (2) It provides baseline information and analysis of that 
information on those parameters and natural processes pertaining to the 
geologic setting that may be changed by site characterization, 
construction, and operational activities.
    (3) It monitors and analyzes changes from the baseline condition of 
parameters that could affect the performance of a geologic repository.
    (4) It provides an established plan for feedback and analysis of 
data, and implementation of appropriate action.



Sec. 60.141  Confirmation of geotechnical and design parameters.

    (a) During repository construction and operation, a continuing 
program of surveillance, measurement, testing, and geologic mapping 
shall be conducted to ensure that geotechnical and

[[Page 208]]

design parameters are confirmed and to ensure that appropriate action is 
taken to inform the Commission of changes needed in design to 
accommodate actual field conditions encountered.
    (b) Subsurface conditions shall be monitored and evaluated against 
design assumptions.
    (c) As a minimum, measurements shall be made of rock deformations 
and displacement, changes in rock stress and strain, rate and location 
of water inflow into subsurface areas, changes in groundwater 
conditions, rock pore water pressures including those along fractures 
and joints, and the thermal and thermomechanical response of the rock 
mass as a result of development and operations of the geologic 
repository.
    (d) These measurements and observations shall be compared with the 
original design bases and assumptions. If significant differences exist 
between the measurements and observations and the original design bases 
and assumptions, the need for modifications to the design or in 
construction methods shall be determined and these differences and the 
recommended changes reported to the Commission.
    (e) In situ monitoring of the thermomechanical response of the 
underground facility shall be conducted until permanent closure to 
ensure that the performance of the natural and engineering features are 
within design limits.



Sec. 60.142  Design testing.

    (a) During the early or developmental stages of construction, a 
program for in situ testing of such features as borehole and shaft 
seals, backfill, and the thermal interaction effects of the waste 
packages, backfill, rock, and groundwater shall be conducted.
    (b) The testing shall be initiated as early as is practicable.
    (c) A backfill test section shall be constructed to test the 
effectiveness of backfill placement and compaction procedures against 
design requirements before permanent backfill placement is begun.
    (d) Test sections shall be established to test the effectiveness of 
borehole and shaft seals before full-scale operation proceeds to seal 
boreholes and shafts.



Sec. 60.143  Monitoring and testing waste packages.

    (a) A program shall be established at the geologic repository 
operations area for monitoring the condition of the waste packages. 
Waste packages chosen for the program shall be representative of those 
to be emplaced in the underground facility.
    (b) Consistent with safe operation at the geologic repository 
operations area, the environment of the waste packages selected for the 
waste package monitoring program shall be representative of the 
environment in which the wastes are to be emplaced.
    (c) The waste package monitoring program shall include laboratory 
experiments which focus on the internal condition of the waste packages. 
To the extent practical, the environment experienced by the emplaced 
waste packages within the underground facility during the waste package 
monitoring program shall be duplicated in the laboratory experiments.
    (d) The waste package monitoring program shall continue as long as 
practical up to the time of permanent closure.



                       Subpart G_Quality Assurance

    Source: 48 FR 28228, June 21, 1983, unless otherwise noted.



Sec. 60.150  Scope.

    As used in this part, quality assurance comprises all those planned 
and systematic actions necessary to provide adequate confidence that the 
geologic repository and its subsystems or components will perform 
satisfactorily in service. Quality assurance includes quality control, 
which comprises those quality assurance actions related to the physical 
characteristics of a material, structure, component, or system which 
provide a means to control the quality of the material, structure, 
component, or system to predetermined requirements.



Sec. 60.151  Applicability.

    The quality assurance program applies to all systems, structures and

[[Page 209]]

components important to safety, to design and characterization of 
barriers important to waste isolation and to activities related thereto. 
These activities include: site characterization, facility and equipment 
construction, facility operation, performance confirmation, permanent 
closure, and decontamination and dismantling of surface facilities.



Sec. 60.152  Implementation.

    DOE shall implement a quality assurance program based on the 
criteria of appendix B of 10 CFR part 50 as applicable, and 
appropriately supplemented by additional criteria as required by Sec. 
60.151.



            Subpart H_Training and Certification of Personnel

    Source: 48 FR 28229, June 21, 1983, unless otherwise noted.



Sec. 60.160  General requirements.

    Operations of systems and components that have been identified as 
important to safety in the Safety Analysis Report and in the license 
shall be performed only by trained and certified personnel or by 
personnel under the direct visual supervision of an individual with 
training and certification in such operation. Supervisory personnel who 
direct operations that are important to safety must also be certified in 
such operations.



Sec. 60.161  Training and certification program.

    DOE shall establish a program for training, proficiency testing, 
certification and requalification of operating and supervisory 
personnel.



Sec. 60.162  Physical requirements.

    The physical condition and the general health of personnel certified 
for operations that are important to safety shall not be such as might 
cause operational errors that could endanger the public health and 
safety. Any condition which might cause impaired judgment or motor 
coordination must be considered in the selection of personnel for 
activities that are important to safety. These conditions need not 
categorically disqualify a person, so long as appropriate provisions are 
made to accommodate such conditions.

Subpart I--Emergency Planning Criteria [Reserved]



                          Subpart J_Violations



Sec. 60.181  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55076, Nov. 24, 1992]



Sec. 60.183  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 60 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 60 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223

[[Page 210]]

are as follows: Sec. Sec. 60.1, 60.2, 60.3, 60.5, 60.6, 60.7, 60.8, 
60.15, 60.16, 60.17, 60.18, 60.21, 60.22, 60.23, 60.24, 60.31, 60.32, 
60.33, 60.41, 60.42, 60.43, 60.44, 60.45, 60.46, 60.51, 60.52, 60.61, 
60.62, 60.63, 60.64, 60.65, 60.101, 60.102, 60.111, 60.112, 60.113, 
60.121, 60.122, 60.130, 60.131, 60.132, 60.133, 60.134, 60.135, 60.137, 
60.140, 60.141, 60.142, 60.143, 60.150, 60.151, 60.152, 60.162, 60.181, 
and 60.183.

[57 FR 55076, Nov. 24, 1992]



PART 61_LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE
--Table of Contents



                      Subpart A_General Provisions

Sec.
61.1 Purpose and scope.
61.2 Definitions.
61.3 License required.
61.4 Communications.
61.5 Interpretations.
61.6 Exemptions.
61.7 Concepts.
61.8 Information collection requirements: OMB approval.
61.9 Employee protection.
61.9a Completeness and accuracy of information.
61.9b Deliberate misconduct.

                           Subpart B_Licenses

61.10 Content of application.
61.11 General information.
61.12 Specific technical information.
61.13 Technical analyses.
61.14 Institutional information.
61.15 Financial information.
61.16 Other information.
61.20 Filing and distribution of application.
61.21 Elimination of repetition.
61.22 Updating of application.
61.23 Standards for issuance of a license.
61.24 Conditions of licenses.
61.25 Changes.
61.26 Amendment of license.
61.27 Application for renewal or closure.
61.28 Contents of application for closure.
61.29 Post-closure observation and maintenance.
61.30 Transfer of license.
61.31 Termination of license.

                      US/IAEA Safeguards Agreement

61.32 Facility information and verification.

                    Subpart C_Performance Objectives

61.40 General requirement.
61.41 Protection of the general population from releases of 
          radioactivity.
61.42 Protection of individuals from inadvertent intrusion.
61.43 Protection of individuals during operations.
61.44 Stability of the disposal site after closure.

      Subpart D_Technical Requirements for Land Disposal Facilities

61.50 Disposal site suitability requirements for land disposal.
61.51 Disposal site design for land disposal.
61.52 Land disposal facility operation and disposal site closure.
61.53 Environmental monitoring.
61.54 Alternative requirements for design and operations.
61.55 Waste classification.
61.56 Waste characteristics.
61.57 Labeling.
61.58 Alternative requirements for waste classification and 
          characteristics.
61.59 Institutional requirements.

                     Subpart E_Financial Assurances

61.61 Applicant qualifications and assurances.
61.62 Funding for disposal site closure and stabilization.
61.63 Financial assurances for institutional controls.

     Subpart F_Participation by State Governments and Indian Tribes

61.70 Scope.
61.71 State and Tribal government consultation.
61.72 Filing of proposals for State and Tribal participation.
61.73 Commission approval of proposals.

           Subpart G_Records, Reports, Tests, and Inspections

61.80 Maintenance of records, reports, and transfers.
61.81 Tests at land disposal facilities.
61.82 Commission inspections of land disposal facilities.
61.83 Violations.
61.84 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 53, 57, 62, 63, 65, 81, 
161, 181, 182, 183, 223, 234 (42 U.S.C. 2073, 2077, 2092, 2093, 2095, 
2111, 2201, 2231, 2232, 2233, 2273, 2282); Energy Reorganization Act of 
1974, secs. 201, 206, 211 (42 U.S.C. 5841, 5846, 5851); Low-Level 
Radioactive Waste Policy Amendments Act of 1985, sec. 2 (42 U.S.C. 
2021b); 44 U.S.C. 3504 note.

    Source: 47 FR 57463, Dec. 27, 1982, unless otherwise noted.

[[Page 211]]


    Editorial Note: Nomenclature changes to part 61 appear at 80 FR 
74980, Dec. 1, 2015, and at 81 FR 86909, Dec. 2, 2016.



                      Subpart A_General Provisions



Sec. 61.1  Purpose and scope.

    (a) The regulations in this part establish, for land disposal of 
radioactive waste, the procedures, criteria, and terms and conditions 
upon which the Commission issues licenses for the disposal of 
radioactive wastes containing byproduct, source and special nuclear 
material received from other persons. Disposal of waste by an individual 
licensee is set forth in part 20 of this chapter. Applicability of the 
requirements in this part to Commission licenses for waste disposal 
facilities in effect on the effective date of this rule will be 
determined on a case-by-case basis and implemented through terms and 
conditions of the license or by orders issued by the Commission.
    (b) Except as provided in part 150 of this chapter, which addresses 
assumption of certain regulatory authority by Agreement States, and 
Sec. 61.6 ``Exemptions,'' the regulations in this part apply to all 
persons in the United States. The regulations in this part do not apply 
to--
    (1) Disposal of high-level waste as provided for in part 60 or 63 of 
this chapter;
    (2) Disposal of uranium or thorium tailings or wastes (byproduct 
material as defined in Sec. 40.4 (a-1) as provided for in part 40 of 
this chapter in quantities greater than 10,000 kilograms and containing 
more than 5 millicuries of radium-226; or
    (3) Disposal of licensed material as provided for in part 20 of this 
chapter.
    (c) This part also gives notice to all persons who knowingly provide 
to any licensee, applicant, contractor, or subcontractor, components, 
equipment, materials, or other goods or services, that relate to a 
licensee's or applicant's activities subject to this part, that they may 
be individually subject to NRC enforcement action for violation of Sec. 
61.9b.

[47 FR 57463, Dec. 27, 1982, as amended at 56 FR 40690, Aug. 15, 1991; 
63 FR 1898, Jan. 13, 1998; 66 FR 55791, Nov. 2, 2001]



Sec. 61.2  Definitions.

    As used in this part:
    Active maintenance means any significant remedial activity needed 
during the period of institutional control to maintain a reasonable 
assurance that the performance objectives in Sec. Sec. 61.41 and 61.42 
are met. Such active maintenance includes ongoing activities such as the 
pumping and treatment of water from a disposal unit or one-time measures 
such as replacement of a disposal unit cover. Active maintenance does 
not include custodial activities such as repair of fencing, repair or 
replacement of monitoring equipment, revegetation, minor additions to 
soil cover, minor repair of disposal unit covers, and general disposal 
site upkeep such as mowing grass.
    Buffer zone is a portion of the disposal site that is controlled by 
the licensee and that lies under the disposal units and between the 
disposal units and the boundary of the site.
    Chelating agent means amine polycarboxylic acids (e.g., EDTA, DTPA), 
hydroxy-carboxylic acids, and polycarboxylic acids (e.g., citric acid, 
carbolic acid, and glucinic acid).
    Commencement of construction means any clearing of land, excavation, 
or other substantial action that would adversely affect the environment 
of a land disposal facility. The term does not mean disposal site 
exploration, necessary roads for disposal site exploration, borings to 
determine foundation conditions, or other preconstruction monitoring or 
testing to establish background information related to the suitability 
of the disposal site or the protection of environmental values.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Custodial Agency means an agency of the government designated to act 
on behalf of the government owner of the disposal site.
    Director means the Director, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission.
    Disposal means the isolation of radioactive wastes from the 
biosphere inhabited by man and containing his food

[[Page 212]]

chains by emplacement in a land disposal facility.
    Disposal site means that portion of a land disposal facility which 
is used for disposal of waste. It consists of disposal units and a 
buffer zone.
    Disposal unit means a discrete portion of the disposal site into 
which waste is placed for disposal. For near-surface disposal the unit 
is usually a trench.
    Engineered barrier means a man-made structure or device that is 
intended to improve the land disposal facility's ability to meet the 
performance objectives in subpart C.
    Explosive material means any chemical compound, mixture, or device, 
which produces a substantial instantaneous release of gas and heat 
spontaneously or by contact with sparks or flame.
    Government agency means any executive department, commission, 
independent establishment, or corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States; or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the government.
    Hazardous waste means those wastes designated as hazardous by 
Environmental Protection Agency regulations in 40 CFR part 261.
    Hydrogeologic unit means any soil or rock unit or zone which by 
virtue of its porosity or permeability, or lack thereof, has a distinct 
influence on the storage or movement of groundwater.
    Inadvertent intruder means a person who might occupy the disposal 
site after closure and engage in normal activities, such as agriculture, 
dwelling construction, or other pursuits in which the person might be 
unknowingly exposed to radiation from the waste.
    Indian Tribe means an Indian Tribe as defined in the Indian Self-
Determination and Education Assistance Act (25 U.S.C. 5301).
    Intruder barrier means a sufficient depth of cover over the waste 
that inhibits contact with waste and helps to ensure that radiation 
exposures to an inadvertent intruder will meet the performance 
objectives set forth in this part, or engineered structures that provide 
equivalent protection to the inadvertent intruder.
    Land disposal facility means the land, building, and structures, and 
equipment which are intended to be used for the disposal of radioactive 
wastes. For purposes of this chapter, a ``geologic repository'' as 
defined in part 60 or 63 is not considered a land disposal facility.
    License means a license issued under the regulations in part 61 of 
this chapter. Licensee means the holder of such a license.
    Monitoring means observing and making measurements to provide data 
to evaluate the performance and characteristics of the disposal site.
    Near-surface disposal facility means a land disposal facility in 
which radioactive waste is disposed of in or within the upper 30 meters 
of the earth's surface.
    Person means (1) any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
government agency other than the Commission or the Department of Energy 
(except that the Department of Energy is considered a person within the 
meaning of the regulations in this part to the extent that its 
facilities and activities are subject to the licensing and related 
regulatory authority of the Commission pursuant to law), any State or 
any political subdivision of or any political entity within a State, any 
foreign government or nation or any political subdivision of any such 
government or nation, or other entity; and (2) any legal successor, 
representative, agent, or agency of the foregoing.
    Pyrophoric liquid means any liquid that ignites spontaneously in dry 
or moist air at or below 130 [deg]F (54.5 [deg]C). A pyrophoric solid is 
any solid material, other than one classed as an explosive, which under 
normal conditions is liable to cause fires through friction, retained 
heat from manufacturing or processing, or which can be ignited readily 
and when ignited burns so vigorously and persistently as to create a 
serious transportation, handling, or disposal hazard. Included are 
spontaneously combustible and water-reactive materials.

[[Page 213]]

    Site closure and stablization means those actions that are taken 
upon completion of operations that prepare the disposal site for 
custodial care and that assure that the disposal site will remain stable 
and will not need ongoing active maintenance.
    State means any State, Territory, or possession of the United 
States, Puerto Rico, and the District of Columbia.
    Stability means structural stabillity.
    Surveillance means observation of the disposal site for purposes of 
visual detection of need for maintenance, custodial care, evidence of 
intrusion, and compliance with other license and regulatory 
requirements.
    Tribal Governing Body means a Tribal organization as defined in the 
Indian Self-Determination and Education Assistance Act (25 U.S.C. 5301).
    Waste means those low-level radioactive wastes containing source, 
special nuclear, or byproduct material that are acceptable for disposal 
in a land disposal facility. For the purposes of this definition, low-
level radioactive waste means radioactive waste not classified as high-
level radioactive waste, transuranic waste, spent nuclear fuel, or 
byproduct material as defined in paragraphs (2), (3), and (4) of the 
definition of Byproduct material set forth in Sec. 20.1003 of this 
chapter.

[47 FR 57463, Dec. 27, 1982, as amended at 54 FR 22583, May 25, 1989; 58 
FR 33891, June 22, 1993; 66 FR 55792, Nov. 2, 2001; 72 FR 55933, Oct. 1, 
2007; 73 FR 5725, Jan. 31, 2008; 79 FR 75740, Dec. 19, 2014; 82 FR 
52825, Nov. 15, 2017]



Sec. 61.3  License required.

    (a) No person may receive, possess, and dispose of radioactive waste 
containing source, special nuclear, or byproduct material at a land 
disposal facility unless authorized by a license issued by the 
Commission pursuant to this part, or unless exemption has been granted 
by the Commission under Sec. 61.6 of this part.
    (b) Each person shall file an application with the Commission and 
obtain a license as provided in this part before commencing construction 
of a land disposal facility. Failure to comply with this requirement may 
be grounds for denial of a license.



Sec. 61.4  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk; 
Director, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; by hand delivery to 
the NRC's Offices at 11555 Rockville Pike, Rockville, Maryland; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, or CD-ROM. Electronic submissions must be made in 
a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[73 FR 5725, Jan. 31, 2008, as amended at 74 FR 62683, Dec. 1, 2009; 79 
FR 75740, Dec. 19, 2014; 80 FR 74980, Dec. 1, 2015]



Sec. 61.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be considered binding upon 
the Commission.



Sec. 61.6  Exemptions.

    The Commission may, upon application by any interested person, or 
upon its own initiative, grant any exemption from the requirements of 
the regulations in this part as it determines is authorized by law, will 
not endanger life or property or the common defense and security, and is 
otherwise in the public interest.

[[Page 214]]



Sec. 61.7  Concepts.

    (a) The disposal facility. (1) Part 61 is intended to apply to land 
disposal of radioactive waste and not to other methods such as sea or 
extraterrestrial disposal. Part 61 contains procedural requirements and 
performance objectives applicable to any method of land disposal. It 
contains specific technical requirements for near-surface disposal of 
radioactive waste, a subset of land disposal, which involves disposal in 
the uppermost portion of the earth, approximately 30 meters. Near-
surface disposal includes disposal in engineered facilities which may be 
built totally or partially above-grade provided that such facilities 
have protective earthen covers. Near-surface disposal does not include 
disposal facilities which are partially or fully above-grade with no 
protective earthen cover, which are referred to as ``above-ground 
disposal.'' Burial deeper than 30 meters may also be satisfactory. 
Technical requirements for alternative methods may be added in the 
future.
    (2) Near-surface disposal of radioactive waste takes place at a 
near-surface disposal facility, which includes all of the land and 
buildings necessary to carry out the disposal. The disposal site is that 
portion of the facility which is used for disposal of waste and consists 
of disposal units and a buffer zone. A disposal unit is a discrete 
portion of the disposal site into which waste is placed for disposal. 
For near-surface disposal, the disposal unit is usually a trench. A 
buffer zone is a portion of the disposal site that is controlled by the 
licensee and that lies under the site and between the boundary of the 
disposal site and any disposal unit. It provides controlled space to 
establish monitoring locations which are intended to provide an early 
warning of radionuclide movement, and to take mitigative measures if 
needed. In choosing a disposal site, site characteristics should be 
considered in terms of the indefinite future and evaluated for at least 
a 500-year timeframe.
    (b) Waste classification and near-surface disposal. (1) Disposal of 
radioactive waste in near-surface disposal facilities has the following 
safety objectives: protection of the general population from releases of 
radioactivity, protection of individuals from inadvertent intrusion, and 
protection of individuals during operations. A fourth objective is to 
ensure stability of the site after closure.
    (2) A cornerstone of the system is stability--stability of the waste 
and the disposal site so that once emplaced and covered, the access of 
water to the waste can be minimized. Migration of radionuclides is thus 
minimized, long-term active maintenance can be avoided, and potential 
exposures to intruders reduced. While stability is a desirable 
characteristic for all waste much radioactive waste does not contain 
sufficient amounts of radionuclides to be of great concern from these 
standpoints; this waste, however, tends to be unstable, such as ordinary 
trash type wastes. If mixed with the higher activity waste, their 
deterioration could lead to failure of the system and permit water to 
penetrate the disposal unit and cause problems with the higher activity 
waste. Therefore, in order to avoid placing requirements for a stable 
waste form on relatively innocuous waste, these wastes have been classed 
as Class A waste. The Class A waste will be disposed of in separate 
disposal units at the disposal site. However, Class A waste that is 
stable may be mixed with other classes of waste. Those higher activity 
wastes that should be stable for proper disposal are classed as Class B 
and C waste. To the extent that it is practicable, Class B and C waste 
forms or containers should be designed to be stable, i.e., maintain 
gross physical properties and identity, over 300 years. For certain 
radionuclides prone to migration, a maximum disposal site inventory 
based on the characteristics of the disposal site may be established to 
limit potential exposure.
    (3) It is possible but unlikely that persons might occupy the site 
in the future and engage in normal pursuits without knowing that they 
were receiving radiation exposure. These persons are referred to as 
inadvertent intruders. Protection of such intruders can involve two 
principal controls: institutional control over the site after operations 
by the site owner to ensure that no such occupation or improper use of 
the site occurs; or, designating

[[Page 215]]

which waste could present an unacceptable risk to an intruder, and 
disposing of this waste in a manner that provides some form of intruder 
barrier that is intended to prevent contact with the waste. This 
regulation incorporates both types of protective controls.
    (4) Institutional control of access to the site is required for up 
to 100 years. This permits the disposal of Class A and Class B waste 
without special provisions for intrusion protection, since these classes 
of waste contain types and quantities of radioisotopes that will decay 
during the 100-year period and will present an acceptable hazard to an 
intruder. The government landowner administering the active 
institutional control program has flexibility in controlling site access 
which may include allowing productive uses of the land provided the 
integrity and long-term performance of the site are not affected.
    (5) Waste that will not decay to levels which present an acceptable 
hazard to an intruder within 100 years is designated as Class C waste. 
This waste is disposed of at a greater depth than the other classes of 
waste so that subsequent surface activities by an intruder will not 
disturb the waste. Where site conditions prevent deeper disposal, 
intruder barriers such as concrete covers may be used. The effective 
life of these intruder barriers should be 500 years. A maximum 
concentration of radionuclides is specified for all wastes so that at 
the end of the 500 year period, remaining radioactivity will be at a 
level that does not pose an unacceptable hazard to an intruder or public 
health and safety. Waste with concentrations above these limits is 
generally unacceptable for near-surface disposal. There may be some 
instances where waste with concentrations greater than permitted for 
Class C would be acceptable for near-surface disposal with special 
processing or design. These will be evaluated on a case-by-case basis. 
Class C waste must also be stable.
    (c) The licensing process. (1) During the preoperational phase, the 
potential applicant goes through a process of disposal site selection by 
selecting a region of interest, examining a number of possible disposal 
sites within the area of interest and narrowing the choice to the 
proposed site. Through a detailed investigation of the disposal site 
characteristics the potential applicant obtains data on which to base an 
analysis of the disposal site's suitability. Along with these data and 
analyses, the applicant submits other more general information to the 
Commission in the form of an application for a license for land 
disposal. The Commission's review of the application is in accordance 
with administrative procedures established by rule and may involve 
participation by affected State governments or Indian Tribes. While the 
proposed disposal site must be owned by a State or the Federal 
government before the Commission will issue a license, it may be 
privately owned during the preoperational phase if suitable arrangements 
have been made with a State or the Federal government to take ownership 
in fee of the land before the license is issued.
    (2) During the operational phase, the licensee carries out disposal 
activities in accordance with the requirements of this regulation and 
any conditions on the license. Periodically, the authority to conduct 
the above ground operations and dispose of waste will be subject to a 
license renewal, at which time the operating history will be reviewed 
and a decision made to permit or deny continued operation. When disposal 
operations are to cease, the licensee applies for an amendment to his 
license to permit site closure. After final review of the licensee's 
site closure and stabilization plan, the Commission may approve the 
final activities necessary to prepare the disposal site so that ongoing 
active maintenance of the site is not required during the period of 
institutional control.
    (3) During the period when the final site closure and stabilization 
activities are being carried out, the licensee is in a disposal site 
closure phase. Following that, for a period of 5 years, the licensee 
must remain at the disposal site for a period of post-closure 
observation and maintenance to assure that the disposal site is stable 
and ready for institutional control. The Commission may approve shorter 
or require longer periods if conditions warrant. At the end of this 
period, the licensee applies

[[Page 216]]

for a license transfer to the disposal site owner.
    (4) After a finding of satisfactory disposal site closure, the 
Commission will transfer the license to the State or Federal government 
that owns the disposal site. If the Department of Energy is the Federal 
agency administering the land on bahalf of the Federal government the 
license will be terminated because the Commission lacks regulatory 
authority over the Department for this activity. Under the conditions of 
the transferred license, the owner will carry out a program of 
monitoring to assure continued satisfactory disposal site performance, 
physical surveillance to restrict access to the site and carry out minor 
custodial activities. During this period, productive uses of the land 
might be permitted if those uses do not affect the stability of the site 
and its ability to meet the performance objectives. At the end of the 
prescribed period of institutional control, the license will be 
terminated by the Commission.

[47 FR 57463, Dec. 27, 1982, as amended at 58 FR 33891, June 22, 1993]



Sec. 61.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0135.
    (b) The approved information collection requirements contained in 
this Part appear in Sec. Sec. 61.3, 61.6, 61.9, 61.10, 61.11, 61.12, 
61.13, 61.14, 61.15, 61.16, 61.20, 61.22, 61.24, 61.26, 61.27, 61.28, 
61.30, 61.31, 61.32, 61.53, 61.55, 61.57, 61.58, 61.61, 61.62, 61.63, 
61.72, and 61.80.
    (c) In Sec. 61.32, Form N-71 and associated forms are approved 
under control number 3150-0056, and DOC/NRC Forms AP-1, AP-A, and 
associated forms are approved under control numbers 0694-0135.

[58 FR 33891, June 22, 1993, as amended at 62 FR 52188, Oct. 6, 1997; 73 
FR 78606, Dec. 23, 2008]



Sec. 61.9  Employee protection.

    (a) Discrimination by a Commission licensee, an applicant for a 
Commission license, or a contractor or subcontractor of a Commission 
licensee or applicant against an employee for engaging in certain 
protected activities is prohibited. Discrimination includes discharge 
and other actions that relate to compensation, terms, conditions, or 
privileges of employment. The protected activities are established in 
section 211 of the Energy Reorganization Act of 1974, as amended, and in 
general are related to the administration or enforcement of a 
requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) introductory text of the section or possible violations of 
requirements imposed under either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) introductory text or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) introductory 
text.
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting

[[Page 217]]

without direction from his or her employer (or the employer's agent), 
deliberately causes a violation of any requirement of the Energy 
Reorganization Act of 1974, as amended, or the Atomic Energy Act of 
1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, an applicant for a Commission license, or a 
contractor or subcontractor of a Commission licensee or applicant may be 
grounds for--
    (1) Denial, revocation, or suspension of the license.
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant.
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee and each applicant for a license shall 
prominently post the revision of NRC Form 3, ``Notice to Employees,'' 
referenced in 10 CFR 19.11(c). This form must be posted at locations 
sufficient to permit employees protected by this section to observe a 
copy on the way to or from their place of work. Premises must be posted 
not later than 30 days after an application is docketed and remain 
posted while the application is pending before the Commission, during 
the term of the license, and for 30 days following license termination.
    (2) Copies of NRC Form 3 can be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[58 FR 52412, Oct. 8, 1993, as amended at 60 FR 24552, May 9, 1995; 61 
FR 6765, Feb. 22, 1996; 68 FR 58814, Oct. 10, 2003; 72 FR 63974, Nov. 
14, 2007; 73 FR 30459, May 28, 2008; 79 FR 66605, Nov. 10, 2014]



Sec. 61.9a  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
license or by a licensee or information required by statute or by the 
Commission's regulations, orders, or license conditions to be maintained 
by the applicant or the licensee shall be complete and accurate in all 
material respects.
    (b) Each applicant or licensee shall notify the Commission of 
information identified by the applicant or licensee as having for the 
regulated activity a significant implication for public health and 
safety or common defense and security. An applicant or licensee violates 
this paragraph only if the applicant or licensee fails to notify the

[[Page 218]]

Commission of information that the applicant or licensee has identified 
as having a significant implication for public health and safety or 
common defense and security. Notification shall be provided to the 
Administrator of the appropriate Regional Office within two working days 
of identifying the information. This requirement is not applicable to 
information which is already required to be provided to the Commission 
by other reporting or updating requirements.

[52 FR 49372, Dec. 31, 1987]



Sec. 61.9b  Deliberate misconduct.

    (a) Any licensee, applicant for a license, employee of a licensee or 
applicant; or any contractor (including a supplier or consultant), 
subcontractor, employee of a contractor or subcontractor of any licensee 
or applicant for a license, who knowingly provides to any licensee, 
applicant, contractor, or subcontractor, any components, equipment, 
materials, or other goods or services that relate to a licensee's or 
applicant's activities in this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee or applicant to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation of 
any license issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, an applicant, or a 
licensee's or applicant's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For the purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee or applicant to be in violation of any 
rule, regulation, or order; or any term, condition, or limitation, of 
any license issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
applicant, contractor, or subcontractor.

[63 FR 1898, Jan. 13, 1998]



                           Subpart B_Licenses



Sec. 61.10  Content of application.

    An application to receive from others, possess and dispose of wastes 
containing or contaminated with source, byproduct or special nuclear 
material by land disposal must consist of general information, specific 
technical information, institutional information, and financial 
information as set forth in Sec. Sec. 61.11 through 61.16. An 
environmental report prepared in accordance with subpart A of part 51 of 
this chapter must accompany the application.

[49 FR 9405, Mar. 12, 1984]



Sec. 61.11  General information.

    The general information must include each of the following:
    (a) Identity of the applicant including:
    (1) The full name, address, telephone number and description of the 
business or occupation of the applicant;
    (2) If the applicant is a partnership, the name, and address of each 
partner and the principal location where the partnership does business;
    (3) If the applicant is a corporation or an unincorporated 
association, (i) the state where it is incorporated or organized and the 
principal location where it does business, and (ii) the names and 
addresses of its directors and principal officers; and
    (4) If the applicant is acting as an agent or representative of 
another person in filing the application, all information required under 
this paragraph must be supplied with respect to the other person.
    (b) Qualifications of the applicant:
    (1) The organizational structure of the applicant, both offsite and 
onsite, including a description of lines of authority and assignments of 
responsibilities, whether in the form of administrative directives, 
contract provisions, or otherwise;

[[Page 219]]

    (2) The technical qualifications, including training and experience, 
of the applicant and members of the applicant's staff to engage in the 
proposed activities. Minimum training and experience requirements for 
personnel filling key positions described in paragraph (b)(1) of this 
section must be provided;
    (3) A description of the applicant's personnel training program; and
    (4) The plan to maintain an adequate complement of trained personnel 
to carry out waste receipt, handling, and disposal operations in a safe 
manner.
    (c) A description of:
    (1) The location of the proposed disposal site;
    (2) The general character of the proposed activities;
    (3) The types and quantities of radioactive waste to be received, 
possessed, and disposed of;
    (4) Plans for use of the land disposal facility for purposes other 
than disposal of radioactive wastes; and
    (5) The proposed facilities and equipment.
    (d) Proposed schedules for construction, receipt of waste, and first 
emplacement of waste at the proposed land disposal facility.



Sec. 61.12  Specific technical information.

    The specific technical information must include the following 
information needed for demonstration that the performance objectives of 
subpart C of this part and the applicable technical requirements of 
subpart D of this part will be met:
    (a) A description of the natural and demographic disposal site 
characteristics as determined by disposal site selection and 
characterization activities. The description must include geologic, 
geotechnical, hydrologic, meteorologic, climatologic, and biotic 
features of the disposal site and vicinity.
    (b) A description of the design features of the land disposal 
facility and the disposal units. For near-surface disposal, the 
description must include those design features related to infiltration 
of water; integrity of covers for disposal units; structural stability 
of backfill, wastes, and covers; contact of wastes with standing water; 
disposal site drainage; disposal site closure and stabilization; 
elimination to the extent practicable of long-term disposal site 
maintenance; inadvertent intrusion; occupational exposures; disposal 
site monitoring; and adequacy of the size of the buffer zone for 
monitoring and potential mitigative measures.
    (c) A description of the principal design criteria and their 
relationship to the performance objectives.
    (d) A description of the design basis natural events or phenomena 
and their relationship to the principal design criteria.
    (e) A description of codes and standards which the applicant has 
applied to the design and which will apply to construction of the land 
disposal facilities.
    (f) A description of the construction and operation of the land 
disposal facility. The description must include as a minimum the methods 
of construction of disposal units; waste emplacement; the procedures for 
and areas of waste segregation; types of intruder barriers; onsite 
traffic and drainage systems; survey control program; methods and areas 
of waste storage; and methods to control surface water and groundwater 
access to the wastes. The description must also include a description of 
the methods to be employed in the handling and disposal of wastes 
containing chelating agents or other non-radiological substances that 
might affect meeting the performance objectives in subpart C of this 
part.
    (g) A description of the disposal site closure plan, including those 
design features which are intended to facilitate disposal site closure 
and to eliminate the need for ongoing active maintenance.
    (h) An identification of the known natural resources at the disposal 
site, the exploitation of which could result in inadvertent intrusion 
into the low-level wastes after removal of active institutional control.
    (i) A description of the kind, amount, classification and 
specifications of the radioactive material proposed to be received, 
possessed, and disposed of at the land disposal facility.
    (j) A description of the quality assurance program, tailored to LLW 
disposal, developed and applied by the applicant for the determination 
of natural disposal site characteristics and

[[Page 220]]

for quality assurance during the design, construction, operation, and 
closure of the land disposal facility and the receipt, handling, and 
emplacement of waste.
    (k) A description of the radiation safety program for control and 
monitoring of radioactive effluents to ensure compliance with the 
performance objective in Sec. 61.41 of this part and occupational 
radiation exposure to ensure compliance with the requirements of part 20 
of this chapter and to control contamination of personnel, vehicles, 
equipment, buildings, and the disposal site. Both routine operations and 
accidents must be addressed. The program description must include 
procedures, instrumentation, facilities, and equipment.
    (l) A description of the environmental monitoring program to provide 
data to evaluate potential health and environmental impacts and the plan 
for taking corrective measures if migration of radionuclides is 
indicated.
    (m) A description of the administrative procedures that the 
applicant will apply to control activities at the land disposal 
facility.
    (n) A description of the facility electronic recordkeeping system as 
required in Sec. 61.80.

[47 FR 57463, Dec. 27, 1982, as amended at 58 FR 33891, June 22, 1993; 
60 FR 15666, Mar. 27, 1995]



Sec. 61.13  Technical analyses.

    The specific technical information must also include the following 
analyses needed to demonstrate that the performance objectives of 
subpart C of this part will be met:
    (a) Pathways analyzed in demonstrating protection of the general 
population from releases of radioactivity must include air, soil, 
groundwater, surface water, plant uptake, and exhumation by burrowing 
animals. The analyses must clearly identify and differentiate between 
the roles performed by the natural disposal site characteristics and 
design features in isolating and segregating the wastes. The analyses 
must clearly demonstrate that there is reasonable assurance that the 
exposure to humans from the release of radioactivity will not exceed the 
limits set forth in Sec. 61.41.
    (b) Analyses of the protection of individuals from inadvertent 
intrusion must include demonstration that there is reasonable assurance 
the waste classification and segregation requirements will be met and 
that adequate barriers to inadvertent intrusion will be provided.
    (c) Analyses of the protection of individuals during operations must 
include assessments of expected exposures due to routine operations and 
likely accidents during handling, storage, and disposal of waste. The 
analyses must provide reasonable assurance that exposures will be 
controlled to meet the requirements of part 20 of this chapter.
    (d) Analyses of the long-term stability of the disposal site and the 
need for ongoing active maintenance after closure must be based upon 
analyses of active natural processes such as erosion, mass wasting, 
slope failure, settlement of wastes and backfill, infiltration through 
covers over disposal areas and adjacent soils, and surface drainage of 
the disposal site. The analyses must provide reasonable assurance that 
there will not be a need for ongoing active maintenance of the disposal 
site following closure.



Sec. 61.14  Institutional information.

    The institutional information must include:
    (a) A certification by the Federal or State government which owns 
the disposal site that the Federal or State government is prepared to 
accept transfer of the license when the provisions of Sec. 61.30 are 
met, and will assume responsibility for custodial care after site 
closure and postclosure observation and maintenance.
    (b) Where the proposed disposal site is on land not owned by the 
Federal or a State government, the applicant must submit evidence that 
arrangements have been made for assumption of ownership in fee by the 
Federal or a State government before the Commission issues a license.



Sec. 61.15  Financial information.

    The financial information must be sufficient to demonstrate that the 
financial qualifications of the applicant are adequate to carry out the 
activities for which the license is sought and

[[Page 221]]

meet other financial assurance requirements as specified in subpart E of 
this part.



Sec. 61.16  Other information.

    Depending upon the nature of the wastes to be disposed of, and the 
design and proposed operation of the land disposal facility, additional 
information may be requested by the Commission including the following:
    (a) Physical security measures, if appropriate. Any application to 
receive and possess special nuclear material in quantities subject to 
the requirements of part 73 of this chapter shall demonstrate how the 
physical security requirements of part 73 will be met. In determining 
whether receipt and possession will be subject to the requirements of 
part 73, the applicant shall not consider the quantity of special 
nuclear material that has been disposed of.
    (b) Safety information concerning criticality, if appropriate. (1) 
Any application to receive and possess special nuclear material in 
quantities that would be subject to the requirements of Sec. 70.24, 
``Criticality accident requirements'' of part 70 of this chapter shall 
demonstrate how the requirements of that section will be met, unless the 
applicant requests an exemption pursuant to Sec. 70.24(d). In 
determining whether receipt and possession would be subject to the 
requirements of Sec. 70.24, the applicant shall not consider the 
quantity of special nuclear material that has been disposed of.
    (2) Any application to receive and possess special nuclear material 
shall describe proposed procedures for avoiding accidental criticality, 
which address both storage of special nuclear material prior to disposal 
and waste emplacement for disposal.



Sec. 61.20  Filing and distribution of application.

    (a) An application for a license under this part, and any amendments 
thereto, must be filed with the Director, must be signed by the 
applicant or the applicant's authorized representative under oath or 
affirmation, and, if the document is in paper form, must be the signed 
original.
    (b) The applicant shall maintain the capability to generate 
additional copies of the application for distribution in accordance with 
written instructions from the Director or the Director's designee.
    (c) Fees. Application, amendment, and inspection fees applicable to 
a license covering the receipt and disposal of radioactive wastes in a 
land disposal facility are required by part 170 of this chapter.

[47 FR 57463, Dec. 27, 1982, as amended at 49 FR 9405, Mar. 12, 1984; 68 
FR 58814, Oct. 10, 2003]



Sec. 61.21  Elimination of repetition.

    In its application, the applicant may incorporate by reference 
information contained in previous applications, statements, or reports 
filed with the Commission if these references are clear and specific.

[49 FR 9405, Mar. 12, 1984]



Sec. 61.22  Updating of application.

    (a) The application must be as complete as possible in the light of 
information that is available at the time of submittal.
    (b) The applicant shall supplement its application in a timely 
manner, as necessary, to permit the Commission to review, prior to 
issuance of a license, any changes in the activities proposed to be 
carried out or new information regarding the proposed activities.

[49 FR 9405, Mar. 12, 1984]



Sec. 61.23  Standards for issuance of a license.

    A license for the receipt, possession, and disposal of waste 
containing or contaminated with source, special nuclear, or byproduct 
material will be issued by the Commission upon finding that the issuance 
of the license will not be inimical to the common defense and security 
and will not constitute an unreasonable risk to the health and safety of 
the public, and:
    (a) The applicant is qualified by reason of training and experience 
to carry out the disposal operations requested in a manner that protects 
health and minimizes danger to life or property.

[[Page 222]]

    (b) The applicant's proposed disposal site, disposal design, land 
disposal facility operations (including equipment, facilities, and 
procedures), disposal site closure, and postclosure institutional 
control are adequate to protect the public health and safety in that 
they provide reasonable assurance that the general population will be 
protected from releases of radioactivity as specified in the performance 
objective in Sec. 61.41, Protection of the general population from 
releases of radioactivity.
    (c) The applicant's proposed disposal site, disposal site design, 
land disposal facility operations (including equipment, facilities, and 
procedures), disposal site closure, and postclosure institutional 
control are adequate to protect the public health and safety in that 
they will provide reasonable assurance that individual inadvertent 
intruders are protected in accordance with the performance objective in 
Sec. 61.42, Protection of individuals from inadvertent intrusion.
    (d) The applicant's proposed land disposal facility operations, 
including equipment, facilities, and procedures, are adequate to protect 
the public health and safety in that they will provide reasonable 
assurance that the standards for radiation protection set out in part 20 
of this chapter will be met.
    (e) The applicant's proposed disposal site, disposal site design, 
land disposal facility operations, disposal site closure, and 
postclosure institutional control are adequate to protect the public 
health and safety in that they will provide reasonable assurance that 
long-term stability of the disposed waste and the disposal site will be 
achieved and will eliminate to the extent practicable the need for 
ongoing active maintenance of the disposal site following closure.
    (f) The applicant's demonstration provides reasonable assurance that 
the applicable technical requirements of subpart D of this part will be 
met.
    (g) The applicant's proposal for institutional control provides 
reasonable assurance that institutional control will be provided for the 
length of time found necessary to ensure the findings in paragraphs (b) 
through (e) of this section and that the institutional control meets the 
requirements of Sec. 61.59, Institutional requirements.
    (h) The information on financial assurances meets the requirements 
of subpart E of this part.
    (i) The applicant's physical security information provides 
reasonable assurance that the requirements of part 73 of this chapter 
will be met, insofar as they are applicable to special nuclear material 
to be possessed before disposal under the license.
    (j) The applicant's criticality safety procedures are adequate to 
protect the public health and safety and provide reasonable assurance 
that the requirements of Sec. 70.24, Criticality accident requirements, 
of part 70 of this chapter will be met, insofar as they are applicable 
to special nuclear material to be possessed before disposal under the 
license.
    (k) Any additional information submitted as requested by the 
Commission pursuant to Sec. 61.16, Other information, is adequate.
    (l) The requirements of subpart A of part 51 of this chapter have 
been met.

[47 FR 57463, Dec. 27, 1982, as amended at 49 FR 9405, Mar. 12, 1984]



Sec. 61.24  Conditions of licenses.

    (a) A license issued under this part, or any right thereunder, may 
be transferred, assigned, or in any manner disposed of, either 
voluntarily or involuntarily, directly or indirectly, through transfer 
of control of the license to any person, only if the Commission finds, 
after securing full information, that the transfer is in accordance with 
the provisions of the Atomic Energy Act and gives its consent in writing 
in the form of a license amendment.
    (b) The licensee shall submit written statements under oath upon 
request of the Commission, at any time before termination of the 
license, to enable the Commission to determine whether or not the 
license should be modified, suspended, or revoked.
    (c) The license will be transferred to the site owner only on the 
full implementation of the final closure plan as approved by the 
Commission, including post-closure observation and maintenance.
    (d) The licensee shall be subject to the provisions of the Atomic 
Energy

[[Page 223]]

Act now or hereafter in effect, and to all rules, regulations, and 
orders of the Commission. The terms and conditions of the license are 
subject to amendment, revision, or modification, by reason of amendments 
to, or by reason of rules, regulations, and orders issued in accordance 
with the terms of the Atomic Energy Act.
    (e) Any license may be revoked, suspended or modified in whole or in 
part for any material false statement in the application or any 
statement of fact required under Section 182 of the Act, or because of 
conditions revealed by any application or statement of fact or any 
report, record, or inspection or other means which would warrant the 
Commission to refuse to grant a license to the original application, or 
for failure to operate the facility in accordance with the terms of the 
license, or for any violation of, or failure to observe any of the terms 
and conditions of the Act, or any rule, regulation, license or order of 
the Commission.
    (f) Each person licensed by the Commission pursuant to the 
regulations in this part shall confine possession and use of materials 
to the locations and purposes authorized in the license.
    (g) No radioactive waste may be disposed of until the Commission has 
inspected the land disposal facility and has found it to be in 
conformance with the description, design, and construction described in 
the application for a license.
    (h) The Commission may incorporate in any license at the time of 
issuance, or thereafter, by appropriate rule, regulation or order, 
additional requirements and conditions with respect to the licensee's 
receipt, possession, and disposal of source, special nuclear or 
byproduct material as it deems appropriate or necessary in order to:
    (1) Promote the common defense and security;
    (2) Protect health or to minimize danger to life or property;
    (3) Require reports and the keeping of records, and to provide for 
inspections of activities under the license that may be necessary or 
appropriate to effectuate the purposes of the Act and regulations 
thereunder.
    (i) Any licensee who receives and possesses special nuclear material 
under this part in quantities that would be subject to the requirements 
of Sec. 70.24 of part 70 of this chapter shall comply with the 
requirements of that section. The licensee shall not consider the 
quantity of special nuclear material that has been disposed of.
    (j) The authority to dispose of wastes expires on the date stated in 
the license except as provided in Sec. 61.27(a) of this part.
    (k)(1) Each licensee shall notify the appropriate NRC Regional 
Administrator, in writing, immediately following the filing of a 
voluntary or involuntary petition for bankruptcy under any Chapter of 
Title 11 (Bankruptcy) of the United States Code by or against:
    (i) The licensee;
    (ii) An entity (as that term is defined in 11 U.S.C. 101(14)) 
controlling the licensee or listing the license or licensee as property 
of the estate; or
    (iii) An affiliate (as that term is defined in 11 U.S.C. 101(2)) of 
the licensee.
    (2) This notification must indicate:
    (i) The bankruptcy court in which the petition for bankruptcy was 
filed; and
    (ii) The date of the filing of the petition.

[47 FR 57463, Dec. 27, 1982, as amended at 52 FR 1295, Jan. 12, 1987]



Sec. 61.25  Changes.

    (a) Except as provided for in specific license conditions, the 
licensee shall not make changes in the land disposal facility or 
procedures described in the license application. The license will 
include conditions restricting subsequent changes to the facility and 
the procedures authorized which are important to public health and 
safety. These license restrictions will fall into three categories of 
descending importance to public health and safety as follows: (1) those 
features and procedures which may not be changed without (i) 60 days 
prior notice to the Commission, (ii) 30 days notice of opportunity for a 
prior hearing, and (iii) prior Commission approval; (2) those features 
and procedures which may not be changed without (i) 60 days prior notice 
to the Commisson, and (ii) prior Commission approval; and (3) those 
features and procedures which may not be changed

[[Page 224]]

without 60 days prior notice to the Commission. Features and procedures 
falling in paragraph (a)(3) of this section may not be changed without 
prior Commission approval if the Commission, after having received the 
required notice, so orders.
    (b) Amendments authorizing site closure, license transfer, or 
license termination shall be included in paragraph (a)(1) of this 
section.
    (c) The Commission shall provide a copy of the notices of 
opportunity for hearing provided in paragraph (a)(1) of this section to 
State and local officials or tribal governing bodies specified in Sec. 
2.104(c) of this chapter.

[47 FR 57463, Dec. 27, 1982, as amended at 77 FR 46600, Aug. 3, 2012]



Sec. 61.26  Amendment of license.

    (a) An application for amendment of a license must be filed in 
accordance with Sec. 61.20 and shall fully describe the changes 
desired.
    (b) In determining whether an amendment to a license will be 
approved, the Commission will apply the criteria set forth in Sec. 
61.23.



Sec. 61.27  Application for renewal or closure.

    (a) Any expiration date on a license applies only to the above 
ground activities and to the authority to dispose of waste. Failure to 
renew the license shall not relieve the licensee of responsibility for 
carrying out site closure, postclosure observation and transfer of the 
license to the site owner. An application for renewal or an application 
for closure under Sec. 61.28 must be filed at least 30 days prior to 
license expiration.
    (b) Applications for renewal of a license must be filed in 
accordance with Sec. Sec. 61.10 through 61.16 and Sec. 61.20. 
Applications for closure must be filed in accordance with Sec. Sec. 
61.20 and 61.28. Information contained in previous applications, 
statements or reports filed with the Commission under the license may be 
incorporated by reference if the references are clear and specific.
    (c) In any case in which a licensee has timely filed an application 
for renewal of a license, the license for continued receipt and disposal 
of licensed materials does not expire until the Commission has taken 
final action on the application for renewal.
    (d) In determining whether a license will be renewed, the Commission 
will apply the criteria set forth in Sec. 61.23.



Sec. 61.28  Contents of application for closure.

    (a) Prior to final closure of the disposal site, or as otherwise 
directed by the Commission, the applicant shall submit an application to 
amend the license for closure. This closure application must include a 
final revision and specific details of the disposal site closure plan 
included as part of the license application submitted under Sec. 
61.12(g) that includes each of the following:
    (1) Any additional geologic, hydrologic, or other disposal site data 
pertinent to the long-term containment of emplaced radioactive wastes 
obtained during the operational period.
    (2) The results of tests, experiments, or any other analyses 
relating to backfill of excavated areas, closure and sealing, waste 
migration and interaction with emplacement media, or any other tests, 
experiments, or analysis pertinent to the long-term containment of 
emplaced waste within the disposal site.
    (3) Any proposed revision of plans for:
    (i) Decontamination and/or dismantlement of surface facilities;
    (ii) Backfilling of excavated areas; or
    (iii) Stabilization of the disposal site for post-closure care.
    (b) An environmental report or a supplement to an environmental 
report prepared in accordance with subpart A of part 51 of this chapter 
must accompany the application.
    (c) Upon review and consideration of an application to amend the 
license for closure submitted in accordance with paragraph (a) of this 
section, the Commission shall issue an amendment authorizing closure if 
there is reasonable assurance that the long-term performance objectives 
of subpart C of this part will be met.

[47 FR 57463, Dec. 27, 1982, as amended at 49 FR 9406, Mar. 12, 1984]

[[Page 225]]



Sec. 61.29  Post-closure observation and maintenance.

    Following completion of closure authorized in Sec. 61.28, the 
licensee shall observe, monitor, and carry out necessary maintenance and 
repairs at the disposal site until the license is transferred by the 
Commission in accordance with Sec. 61.30. Responsibility for the 
disposal site must be maintained by the licensee for 5 years. A shorter 
or longer time period for post-closure observation and maintenance may 
be established and approved as part of the site closure plan, based on 
site-specific conditions.



Sec. 61.30  Transfer of license.

    (a) Following closure and the period of post-closure observation and 
maintenance, the licensee may apply for an amendment to transfer the 
license to the disposal site owner. The license shall be transferred 
when the Commission finds:
    (1) That the closure of the disposal site has been made in 
conformance with the licensee's disposal site closure plan, as amended 
and approved as part of the license;
    (2) That reasonable assurance has been provided by the licensee that 
the performance objectives of subpart C of this part are met;
    (3) That any funds for care and records required by Sec. 61.80 (e) 
and (f) have been transferred to the disposal site owner;
    (4) That the post-closure monitoring program is operational for 
implementation by the disposal site owner; and
    (5) That the Federal or State government agency which will assume 
responsibility for institutional control of the disposal site is 
prepared to assume responsibility and ensure that the institutional 
requirements found necessary under Sec. 61.23(g) will be met.

[47 FR 57463, Dec. 27, 1982, as amended at 61 FR 24674, May 16, 1996]



Sec. 61.31  Termination of license.

    (a) Following any period of institutional control needed to meet the 
requirements found necessary under Sec. 61.23, the licensee may apply 
for an amendment to terminate the license.
    (b) This application must be filed, and will be reviewed, in 
accordance with the provision of Sec. 61.20 and of this section.
    (c) A license is terminated only when the Commission finds:
    (1) That the institutional control requirements found necessary 
under Sec. 61.23(g) have been met; and
    (2) That any additional requirements resulting from new information 
developed during the institutional control period have been met, and 
that permanent monuments or markers warning against intrusion have been 
installed.
    (3) That the records required by Sec. 61.80 (e) and (f) have been 
sent to the party responsible for institutional control of the disposal 
site and a copy has been sent to the Commission immediately prior to 
license termination.

[47 FR 57463, Dec. 27, 1982, as amended at 61 FR 24674, May 16, 1996]

                      US/IAEA Safeguards Agreement



Sec. 61.32  Facility information and verification.

    (a) In response to a written request by the Commission, each 
applicant for a license and each recipient of a license shall submit 
facility information, as described in Sec. 75.10 of this chapter, on 
Form N-71 and associated forms and site information on DOC/NRC Form AP-
A, and associated forms;
    (b) As required by the Additional Protocol, applicants and licensees 
specified in paragraph (a) of this section shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms; and
    (c) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA) and take other action as necessary to implement the 
US/IAEA Safeguards Agreement, as described in Part 75 of this chapter.

[73 FR 78606, Dec. 23, 2008]



                    Subpart C_Performance Objectives



Sec. 61.40  General requirement.

    Land disposal facilities must be sited, designed, operated, closed, 
and

[[Page 226]]

controlled after closure so that reasonable assurance exists that 
exposures to humans are within the limits established in the performance 
objectives in Sec. Sec. 61.41 through 61.44.



Sec. 61.41  Protection of the general population from releases of
radioactivity.

    Concentrations of radioactive material which may be released to the 
general environment in groundwater, surface water, air, soil, plants, or 
animals must not result in an annual dose exceeding an equivalent of 25 
millirems to the whole body, 75 millirems to the thyroid, and 25 
millirems to any other organ of any member of the public. Reasonable 
effort should be made to maintain releases of radioactivity in effluents 
to the general environment as low as is reasonably achievable.



Sec. 61.42  Protection of individuals from inadvertent intrusion.

    Design, operation, and closure of the land disposal facility must 
ensure protection of any individual inadvertently intruding into the 
disposal site and occupying the site or contacting the waste at any time 
after active institutional controls over the disposal site are removed.



Sec. 61.43  Protection of individuals during operations.

    Operations at the land disposal facility must be conducted in 
compliance with the standards for radiation protection set out in part 
20 of this chapter, except for releases of radioactivity in effluents 
from the land disposal facility, which shall be governed by Sec. 61.41 
of this part. Every reasonable effort shall be made to maintain 
radiation exposures as low as is reasonably achievable.



Sec. 61.44  Stability of the disposal site after closure.

    The disposal facility must be sited, designed, used, operated, and 
closed to achieve long-term stability of the disposal site and to 
eliminate to the extent practicable the need for ongoing active 
maintenance of the disposal site following closure so that only 
surveillance, monitoring, or minor custodial care are required.



      Subpart D_Technical Requirements for Land Disposal Facilities



Sec. 61.50  Disposal site suitability requirements for land disposal.

    (a) Disposal site suitability for near-surface disposal. (1) The 
purpose of this section is to specify the minimum characteristics a 
disposal site must have to be acceptable for use as a near-surface 
disposal facility. The primary emphasis in disposal site suitability is 
given to isolation of wastes, a matter having long-term impacts, and to 
disposal site features that ensure that the long-term performance 
objectives of subpart C of this part are met, as opposed to short-term 
convenience or benefits.
    (2) The disposal site shall be capable of being characterized, 
modeled, analyzed and monitored.
    (3) Within the region or state where the facility is to be located, 
a disposal site should be selected so that projected population growth 
and future developments are not likely to affect the ability of the 
disposal facility to meet the performance objectives of subpart C of 
this part.
    (4) Areas must be avoided having known natural resources which, if 
exploited, would result in failure to meet the performance objectives of 
subpart C of this part.
    (5) The disposal site must be generally well drained and free of 
areas of flooding or frequent ponding. Waste disposal shall not take 
place in a 100-year flood plain, coastal high-hazard area or wetland, as 
defined in Executive Order 11988, ``Floodplain Management Guidelines.''
    (6) Upstream drainage areas must be minimized to decrease the amount 
of runoff which could erode or inundate waste disposal units.
    (7) The disposal site must provide sufficient depth to the water 
table that groundwater intrusion, perennial or otherwise, into the waste 
will not occur. The Commission will consider an exception to this 
requirement to allow disposal below the water table if it can be 
conclusively shown that disposal site characteristics will result in 
molecular diffusion being the predominant means of radionuclide movement

[[Page 227]]

and the rate of movement will result in the performance objectives of 
subpart C of this part being met. In no case will waste disposal be 
permitted in the zone of fluctuation of the water table.
    (8) The hydrogeologic unit used for disposal shall not discharge 
groundwater to the surface within the disposal site.
    (9) Areas must be avoided where tectonic processes such as faulting, 
folding, seismic activity, or vulcanism may occur with such frequency 
and extent to significantly affect the ability of the disposal site to 
meet the performance objectives of subpart C of this part, or may 
preclude defensible modeling and prediction of long-term impacts.
    (10) Areas must be avoided where surface geologic processes such as 
mass wasting, erosion, slumping, landsliding, or weathering occur with 
such frequency and extent to significantly affect the ability of the 
disposal site to meet the performance objectives of subpart C of this 
part, or may preclude defensible modeling and prediction of long-term 
impacts.
    (11) The disposal site must not be located where nearby facilities 
or activities could adversely impact the ability of the site to meet the 
performance objectives of subpart C of this part or significantly mask 
the environmental monitoring program.
    (b) Disposal site suitability requirements for land disposal other 
than near-surface. [Reserved]



Sec. 61.51  Disposal site design for land disposal.

    (a) Disposal site design for near-surface disposal. (1) Site design 
features must be directed toward long-term isolation and avoidance of 
the need for continuing active maintenance after site closure.
    (2) The disposal site design and operation must be compatible with 
the disposal site closure and stabilization plan and lead to disposal 
site closure that provides reasonable assurance that the performance 
objectives of subpart C of this part will be met.
    (3) The disposal site must be designed to complement and improve, 
where appropriate, the ability of the disposal site's natural 
characteristics to assure that the performance objectives of subpart C 
of this part will be met.
    (4) Covers must be designed to minimize to the extent practicable 
water infiltration, to direct percolating or surface water away from the 
disposed waste, and to resist degradation by surface geologic processes 
and biotic activity.
    (5) Surface features must direct surface water drainage away from 
disposal units at velocities and gradients which will not result in 
erosion that will require ongoing active maintenance in the future.
    (6) The disposal site must be designed to minimize to the extent 
practicable the contact of water with waste during storage, the contact 
of standing water with waste during disposal, and the contact of 
percolating or standing water with wastes after disposal.
    (b) Disposal site design for other than near-surface disposal. 
[Reserved]



Sec. 61.52  Land disposal facility operation and disposal site 
closure.

    (a) Near-surface disposal facility operation and disposal site 
closure. (1) Wastes designated as Class A pursuant to Sec. 61.55, must 
be segregated from other wastes by placing in disposal units which are 
sufficiently separated from disposal units for the other waste classes 
so that any interaction between Class A wastes and other wastes will not 
result in the failure to meet the performance objectives in subpart C of 
this Part. This segregation is not necessary for Class A wastes if they 
meet the stability requirements in Sec. 61.56(b) of this part.
    (2) Wastes designated as Class C pursuant to Sec. 61.55, must be 
disposed of so that the top of the waste is a minimum of 5 meters below 
the top surface of the cover or must be disposed of with intruder 
barriers that are designed to protect against an inadvertent intrusion 
for a least 500 years.
    (3) All wastes shall be disposed of in accordance with the 
requirements of paragraphs (a) (4) through (11) of this section.

[[Page 228]]

    (4) Wastes must be emplaced in a manner that maintains the package 
integrity during emplacement, minimizes the void spaces between 
packages, and permits the void spaces to be filled.
    (5) Void spaces between waste packages must be filled with earth or 
other material to reduce future subsidence within the fill.
    (6) Waste must be placed and covered in a manner that limits the 
radiation dose rate at the surface of the cover to levels that at a 
minimum will permit the licensee to comply with all provisions of 
Sec. Sec. 20.1301 and 20.1302 of this chapter at the time the license 
is transferred pursuant to Sec. 61.30 of this part.
    (7) The boundaries and locations of each disposal unit (e.g., 
trenches) must be accurately located and mapped by means of a land 
survey. Near-surface disposal units must be marked in such a way that 
the boundaries of each unit can be easily defined. Three permanent 
survey marker control points, referenced to United States Geological 
Survey (USGS) or National Geodetic Survey (NGS) survey control stations, 
must be established on the site to facilitate surveys. The USGS or NGS 
control stations must provide horizontal and vertical controls as 
checked against USGS or NGS record files.
    (8) A buffer zone of land must be maintained between any buried 
waste and the disposal site boundary and beneath the disposed waste. The 
buffer zone shall be of adequate dimensions to carry out environmental 
monitoring activities specified in Sec. 61.53(d) of this part and take 
mitigative measures if needed.
    (9) Closure and stabilization measures as set forth in the approved 
site closure plan must be carried out as each disposal unit (e.g., each 
trench) is filled and covered.
    (10) Active waste disposal operations must not have an adverse 
effect on completed closure and stabilization measures.
    (11) Only wastes containing or contaminated with radioactive 
materials shall be disposed of at the disposal site.
    (b) Facility operation and disposal site closure for land disposal 
facilities other than near-surface. [Reserved]

[47 FR 57463, Dec. 27, 1982, as amended at 56 FR 23474, May 21, 1991; 56 
FR 61352, Dec. 3, 1991; 58 FR 67662, Dec. 22, 1993]



Sec. 61.53  Environmental monitoring.

    (a) At the time a license application is submitted, the applicant 
shall have conducted a preoperational monitoring program to provide 
basic environmental data on the disposal site characteristics. The 
applicant shall obtain information about the ecology, meteorology, 
climate, hydrology, geology, geochemistry, and seismology of the 
disposal site. For those characteristics that are subject to seasonal 
variation, data must cover at least a twelve month period.
    (b) The licensee must have plans for taking corrective measures if 
migration of radionuclides would indicate that the performance 
objectives of subpart C may not be met.
    (c) During the land disposal facility site construction and 
operation, the licensee shall maintain a monitoring program. 
Measurements and observations must be made and recorded to provide data 
to evaluate the potential health and environmental impacts during both 
the construction and the operation of the facility and to enable the 
evaluation of long-term effects and the need for mitigative measures. 
The monitoring system must be capable of providing early warning of 
releases of radionuclides from the disposal site before they leave the 
site boundary.
    (d) After the disposal site is closed, the licensee responsible for 
post-operational surveillance of the disposal site shall maintain a 
monitoring system based on the operating history and the closure and 
stabilization of the disposal site. The monitoring system must be 
capable of providing early warning of releases of radionuclides from the 
disposal site before they leave the site boundary.



Sec. 61.54  Alternative requirements for design and operations.

    The Commission may, upon request or on its own initiative, authorize 
provisions other than those set forth in Sec. Sec. 61.51 through 61.53 
for the segregation

[[Page 229]]

and disposal of waste and for the design and operation of a land 
disposal facility on a specific basis, if it finds reasonable assurance 
of compliance with the performance objectives of subpart C of this part.



Sec. 61.55  Waste classification.

    (a) Classification of waste for near surface disposal--(1) 
Considerations. Determination of the classification of radioactive waste 
involves two considerations. First, consideration must be given to the 
concentration of long-lived radionuclides (and their shorter-lived 
precursors) whose potential hazard will persist long after such 
precautions as institutional controls, improved waste form, and deeper 
disposal have ceased to be effective. These precautions delay the time 
when long-lived radionuclides could cause exposures. In addition, the 
magnitude of the potential dose is limited by the concentration and 
availability of the radionuclide at the time of exposure. Second, 
consideration must be given to the concentration of shorter-lived 
radionuclides for which requirements on institutional controls, waste 
form, and disposal methods are effective.
    (2) Classes of waste. (i) Class A waste is waste that is usually 
segregated from other waste classes at the disposal site. The physical 
form and characteristics of Class A waste must meet the minimum 
requirements set forth in Sec. 61.56(a). If Class A waste also meets 
the stability requirements set forth in Sec. 61.56(b), it is not 
necessary to segregate the waste for disposal.
    (ii) Class B waste is waste that must meet more rigorous 
requirements on waste form to ensure stability after disposal. The 
physical form and characteristics of Class B waste must meet both the 
minimum and stability requirements set forth in Sec. 61.56.
    (iii) Class C waste is waste that not only must meet more rigorous 
requirements on waste form to ensure stability but also requires 
additional measures at the disposal facility to protect against 
inadvertent intrusion. The physical form and characteristics of Class C 
waste must meet both the minimum and stability requirements set forth in 
Sec. 61.56.
    (iv) Waste that is not generally acceptable for near-surface 
disposal is waste for which form and disposal methods must be different, 
and in general more stringent, than those specified for Class C waste. 
In the absence of specific requirements in this part, such waste must be 
disposed of in a geologic repository as defined in part 60 or 63 of this 
chapter unless proposals for disposal of such waste in a disposal site 
licensed pursuant to this part are approved by the Commission.
    (3) Classification determined by long-lived radionuclides. If 
radioactive waste contains only radionuclides listed in Table 1, 
classification shall be determined as follows:
    (i) If the concentration does not exceed 0.1 times the value in 
Table 1, the waste is Class A.
    (ii) If the concentration exceeds 0.1 times the value in Table 1 but 
does not exceed the value in Table 1, the waste is Class C.
    (iii) If the concentration exceeds the value in Table 1, the waste 
is not generally acceptable for near-surface disposal.
    (iv) For wastes containing mixtures of radionuclides listed in Table 
1, the total concentration shall be determined by the sum of fractions 
rule described in paragraph (a)(7) of this section.

                                 Table 1
------------------------------------------------------------------------
                                                           Concentration
                       Radionuclide                          curies per
                                                            cubic meter
------------------------------------------------------------------------
C-14.....................................................           8
C-14 in activated metal..................................          80
Ni-59 in activated metal.................................         220
Nb-94 in activated metal.................................           0.2
Tc-99....................................................           3
I-129....................................................           0.08
Alpha emitting transuranic nuclides with half-life            \1\ 100
 greater than 5 years....................................
Pu-241...................................................   \1\ 3,500
Cm-242...................................................  \1\ 20,000
------------------------------------------------------------------------
\1\ Units are nanocuries per gram.

    (4) Classification determined by short-lived radionuclides. If 
radioactive waste does not contain any of the radionuclides listed in 
Table 1, classification shall be determined based on the concentrations 
shown in Table 2. However, as specified in paragraph (a)(6) of this 
section, if radioactive waste does not

[[Page 230]]

contain any nuclides listed in either Table 1 or 2, it is Class A.
    (i) If the concentration does not exceed the value in Column 1, the 
waste is Class A.
    (ii) If the concentration exceeds the value in Column 1, but does 
not exceed the value in Column 2, the waste is Class B.
    (iii) If the concentration exceeds the value in Column 2, but does 
not exceed the value in Column 3, the waste is Class C.
    (iv) If the concentration exceeds the value in Column 3, the waste 
is not generally acceptable for near-surface disposal.
    (v) For wastes containing mixtures of the nuclides listed in Table 
2, the total concentration shall be determined by the sum of fractions 
rule described in paragraph (a)(7) of this section.

                                 Table 2
------------------------------------------------------------------------
                                                   Concentration, curies
                                                      per cubic meter
                   Radionuclide                   ----------------------
                                                             Col.   Col.
                                                    Col. 1    2      3
------------------------------------------------------------------------
Total of all nuclides with less than 5 year half-   700     (\1\)  (\1\)
 life............................................
H-3..............................................    40     (\1\)  (\1\)
Co-60............................................   700     (\1\)  (\1\)
Ni-63............................................     3.5      70    700
Ni-63 in activated metal.........................    35       700   7000
Sr-90............................................     0.04    150   7000
Cs-137...........................................     1        44   4600
------------------------------------------------------------------------
\1\ There are no limits established for these radionuclides in Class B
  or C wastes. Practical considerations such as the effects of external
  radiation and internal heat generation on transportation, handling,
  and disposal will limit the concentrations for these wastes. These
  wastes shall be Class B unless the concentrations of other nuclides in
  Table 2 determine the waste to be Class C independent of these
  nuclides.

    (5) Classification determined by both long- and short-lived 
radionuclides. If radioactive waste contains a mixture of radionuclides, 
some of which are listed in Table 1, and some of which are listed in 
Table 2, classification shall be determined as follows:
    (i) If the concentration of a nuclide listed in Table 1 does not 
exceed 0.1 times the value listed in Table 1, the class shall be that 
determined by the concentration of nuclides listed in Table 2.
    (ii) If the concentration of a nuclide listed in Table 1 exceeds 0.1 
times the value listed in Table 1 but does not exceed the value in Table 
1, the waste shall be Class C, provided the concentration of nuclides 
listed in Table 2 does not exceed the value shown in Column 3 of Table 
2.
    (6) Classification of wastes with radionuclides other than those 
listed in Tables 1 and 2. If radioactive waste does not contain any 
nuclides listed in either Table 1 or 2, it is Class A.
    (7) The sum of the fractions rule for mixtures of radionuclides. For 
determining classification for waste that contains a mixture of 
radionuclides, it is necessary to determine the sum of fractions by 
dividing each nuclide's concentration by the appropriate limit and 
adding the resulting values. The appropriate limits must all be taken 
from the same column of the same table. The sum of the fractions for the 
column must be less than 1.0 if the waste class is to be determined by 
that column. Example: A waste contains Sr-90 in a concentration of 50 
Ci/m\3\ and Cs-137 in a concentration of 22 Ci/m\3\. Since the 
concentrations both exceed the values in Column 1, Table 2, they must be 
compared to Column 2 values. For Sr-90 fraction 50/150 = 0.33; for Cs-
137 fraction, 22/44 = 0.5; the sum of the fractions = 0.83. Since the 
sum is less than 1.0, the waste is Class B.
    (8) Determination of concentrations in wastes. The concentration of 
a radionuclide may be determined by indirect methods such as use of 
scaling factors which relate the inferred concentration of one 
radionuclide to another that is measured, or radionuclide material 
accountability, if there is reasonable assurance that the indirect 
methods can be correlated with actual measurements. The concentration of 
a radionuclide may be averaged over the volume of the waste, or weight 
of the waste if the units are expressed as nanocuries per gram.

[47 FR 57463, Dec. 27, 1982, as amended at 54 FR 22583, May 25, 1989; 66 
FR 55792, Nov. 2, 2001]



Sec. 61.56  Waste characteristics.

    (a) The following requirements are minimum requirements for all 
classes of waste and are intended to facilitate handling at the disposal 
site and provide protection of health and safety of personnel at the 
disposal site.
    (1) Waste must not be packaged for disposal in cardboard or 
fiberboard boxes.

[[Page 231]]

    (2) Liquid waste must be solidified or packaged in sufficient 
absorbent material to absorb twice the volume of the liquid.
    (3) Solid waste containing liquid shall contain as little free 
standing and noncorrosive liquid as is reasonably achievable, but in no 
case shall the liquid exceed 1% of the volume.
    (4) Waste must not be readily capable of detonation or of explosive 
decomposition or reaction at normal pressures and temperatures, or of 
explosive reaction with water.
    (5) Waste must not contain, or be capable of generating, quantities 
of toxic gases, vapors, or fumes harmful to persons transporting, 
handling, or disposing of the waste. This does not apply to radioactive 
gaseous waste packaged in accordance with paragraph (a)(7) of this 
section.
    (6) Waste must not be pyrophoric. Pyrophoric materials contained in 
waste shall be treated, prepared, and packaged to be nonflammable.
    (7) Waste in a gaseous form must be packaged at a pressure that does 
not exceed 1.5 atmospheres at 20 [deg]C. Total activity must not exceed 
100 curies per container.
    (8) Waste containing hazardous, biological, pathogenic, or 
infectious material must be treated to reduce to the maximum extent 
practicable the potential hazard from the non-radiological materials.
    (b) The requirements in this section are intended to provide 
stability of the waste. Stability is intended to ensure that the waste 
does not structurally degrade and affect overall stability of the site 
through slumping, collapse, or other failure of the disposal unit and 
thereby lead to water infiltration. Stability is also a factor in 
limiting exposure to an inadvertent intruder, since it provides a 
recognizable and nondispersible waste.
    (1) Waste must have structural stability. A structurally stable 
waste form will generally maintain its physical dimensions and its form, 
under the expected disposal conditions such as weight of overburden and 
compaction equipment, the presence of moisture, and microbial activity, 
and internal factors such as radiation effects and chemical changes. 
Structural stability can be provided by the waste form itself, 
processing the waste to a stable form, or placing the waste in a 
disposal container or structure that provides stability after disposal.
    (2) Notwithstanding the provisions in Sec. 61.56(a) (2) and (3), 
liquid wastes, or wastes containing liquid, must be converted into a 
form that contains as little free standing and noncorrosive liquid as is 
reasonably achievable, but in no case shall the liquid exceed 1% of the 
volume of the waste when the waste is in a disposal container designed 
to ensure stability, or 0.5% of the volume of the waste for waste 
processed to a stable form.
    (3) Void spaces within the waste and between the waste and its 
package must be reduced to the extent practicable.



Sec. 61.57  Labeling.

    Each package of waste must be clearly labeled to identify whether it 
is Class A waste, Class B waste, or Class C waste, in accordance with 
Sec. 61.55.



Sec. 61.58  Alternative requirements for waste classification 
and characteristics.

    The Commission may, upon request or on its own initiative, authorize 
other provisions for the classification and characteristics of waste on 
a specific basis, if, after evaluation, of the specific characteristics 
of the waste, disposal site, and method of disposal, it finds reasonable 
assurance of compliance with the performance objectives in subpart C of 
this part.



Sec. 61.59  Institutional requirements.

    (a) Land ownership. Disposal of radioactive waste received from 
other persons may be permitted only on land owned in fee by the Federal 
or a State government.
    (b) Institutional control. The land owner or custodial agency shall 
carry out an institutional control program to physically control access 
to the disposal site following transfer of control of the disposal site 
from the disposal site operator. The institutional control program must 
also include, but not be limited to, carrying out an environmental 
monitoring program at the disposal site, periodic surveillance, minor

[[Page 232]]

custodial care, and other requirements as determined by the Commission; 
and administration of funds to cover the costs for these activities. The 
period of institutional controls will be determined by the Commission, 
but institutional controls may not be relied upon for more than 100 
years following transfer of control of the disposal site to the owner.



                     Subpart E_Financial Assurances



Sec. 61.61  Applicant qualifications and assurances.

    Each applicant shall show that it either possesses the necessary 
funds or has reasonable assurance of obtaining the necessary funds, or 
by a combination of the two, to cover the estimated costs of conducting 
all licensed activities over the planned operating life of the project, 
including costs of construction and disposal.



Sec. 61.62  Funding for disposal site closure and stabilization.

    (a) The applicant shall provide assurance that sufficient funds will 
be available to carry out disposal site closure and stabilization, 
including: (1) Decontamination or dismantlement of land disposal 
facility structures; and (2) closure and stabilization of the disposal 
site so that following transfer of the disposal site to the site owner, 
the need for ongoing active maintenance is eliminated to the extent 
practicable and only minor custodial care, surveillance, and monitoring 
are required. These assurances shall be based on Commission-approved 
cost estimates reflecting the Commission-approved plan for disposal site 
closure and stabilization. The applicant's cost estimates must take into 
account total capital costs that would be incurred if an independent 
contractor were hired to perform the closure and stabilization work.
    (b) In order to avoid unnecessary duplication and expense, the 
Commission will accept financial sureties that have been consolidated 
with earmarked financial or surety arrangements established to meet 
requirements of other Federal or State agencies and/or local governing 
bodies for such decontamination, closure and stabilization. The 
Commission will accept this arrangement only if they are considered 
adequate to satisfy these requirements and that the portion of the 
surety which covers the closure of the disposal site is clearly 
identified and committed for use in accomplishing these activities.
    (c) The licensee's surety mechanism will be annually reviewed by the 
Commission to assure that sufficient funds are available for completion 
of the closure plan, assuming that the work has to be performed by an 
independent contractor.
    (d) The amount of surety liability should change in accordance with 
the predicted cost of future closure and stabilization. Factors 
affecting closure and stabilization cost estimates include: inflation; 
increases in the amount of disturbed land; changes in engineering plans; 
closure and stabilization that has already been accomplished and any 
other conditions affecting costs. This will yield a surety that is at 
least sufficient at all times to cover the costs of closure of the 
disposal units that are expected to be used before the next license 
renewal.
    (e) The term of the surety mechanism must be open ended unless it 
can be demonstrated that another arrangement would provide an equivalent 
level of assurance. This assurance could be provided with a surety 
mechanism which is written for a specified period of time (e.g., five 
years) yet which must be automatically renewed unless the party who 
issues the surety notifies the Commission and the beneficiary (the site 
owner) and the principal (the licensee) not less than 90 days prior to 
the renewal date of its intention not to renew. In such a situation the 
licensee must submit a replacement surety within 30 days after 
notification of cancellation. If the licensee fails to provide a 
replacement surety acceptable to the Commission, the site owner may 
collect on the original surety.
    (f) Proof of forfeiture must not be necessary to collect the surety 
so that in the event that the licensee could not provide an acceptable 
replacement surety within the required time, the surety shall be 
automatically collected prior to its expiration. The conditions

[[Page 233]]

described above would have to be clearly stated on any surety instrument 
which is not open-ended, and must be agreed to by all parties. Liability 
under the surety mechanism must remain in effect until the closure and 
stabilization program has been completed and approved by the Commission 
and the license has been transferred to the site owner.
    (g) Financial surety arrangements generally acceptable to the 
Commission include: surety bonds, cash deposits, certificates of 
deposits, deposits of government securities, escrow accounts, 
irrevocable letters or lines of credit, trust funds, and combinations of 
the above or such other types of arrangements as may be approved by the 
Commission. However, self-insurance, or any arrangement which 
essentially constitutes pledging the assets of the licensee, will not 
satisfy the surety requirement for private sector applicants since this 
provides no additional assurance other than that which already exists 
through license requirements.



Sec. 61.63  Financial assurances for institutional controls.

    (a) Prior to the issuance of the license, the applicant shall 
provide for Commission review and approval a copy of a binding 
arrangement, such as a lease, between the applicant and the disposal 
site owner that ensures that sufficient funds will be available to cover 
the costs of monitoring and any required maintenance during the 
institutional control period. The binding arrangement will be reviewed 
periodically by the Commission to ensure that changes in inflation, 
technology and disposal facility operations are reflected in the 
arrangements.
    (b) Subsequent changes to the binding arrangement specified in 
paragraph (a) of this section relevant to institutional control shall be 
submitted to the Commission for approval.



     Subpart F_Participation by State Governments and Indian Tribes



Sec. 61.70  Scope.

    This subpart describes mechanisms through which the Commission will 
implement a formal request from a State or tribal government to 
participate in the review of a license application for a land disposal 
facility. Nothing in this subpart may be construed to bar the State or 
tribal governing body from participating in subsequent Commission 
proceedings concerning the license application as provided under Federal 
law and regulations.



Sec. 61.71  State and Tribal government consultation.

    Upon request of a State or tribal governing body, the Director shall 
make available Commission staff to discuss with representatives of the 
State or tribal governing body information submitted by the applicant, 
applicable Commission regulations, licensing procedures, potential 
schedules, and the type and scope of State activities in the license 
review permitted by law. In addition, staff shall be made available to 
consult and cooperate with the State or tribal governing body in 
developing proposals for participation in the license review.



Sec. 61.72  Filing of proposals for State and Tribal participation.

    (a) A State or tribal governing body whose interest is affected by a 
near-surface disposal facility at the proposed site may submit to the 
Director a proposal for participation in the review of a license 
application. Proposals must be submitted within the following time 
periods:
    (1) For the State in which the disposal facility will be located, or 
any State that is member of an interstate compact that includes the 
State in which the disposal facility is located, no later than 45 days 
following publication in the Federal Register of the notice of tendering 
of an application submitted under Sec. 61.20.
    (2) For any other State, or for a tribal governing body, no later 
than 120 days following publication in the Federal Register of the 
notice of tendering of an application submitted under Sec. 61.20.
    (b) Proposals for participation in the licensing process must be 
made in writing and must be signed by the Governor of the State or the 
official otherwise provided for by State or tribal law.

[[Page 234]]

    (c) At a minimum, proposals must contain each of the following items 
of information:
    (1) A general description of how the State or Tribe wishes to 
participate in the licensing process specifically identifying those 
issues it wishes to review.
    (2) A description of material and information which the State or 
Tribe plans to submit to the Commission for consideration in the 
licensing process. A tentative schedule referencing steps in the review 
and calendar dates for planned submittals should be included.
    (3) A description of any work that the State or Tribe proposes to 
perform for the Commission in support of the licensing process.
    (4) A description of State or Tribal plans to facilitate local 
government and citizen participation.
    (5) A preliminary estimate of the types and extent of impacts which 
the State expects, should a disposal facility be located as proposed.
    (6) If desired, any requests for educational or information services 
(seminars, public meetings) or other actions from the Commission such as 
establishment of additional Public Document Rooms or exchange of State 
personnel under the Intergovernmental Personnel Act.



Sec. 61.73  Commission approval of proposals.

    (a) Upon receipt of a proposal submitted in accordance with Sec. 
61.72, the Director shall arrange for a meeting between the 
representatives of the State or Tribal governing body and the Commission 
staff to discuss the proposal and to ensure full and effective 
participation by the State or Tribe in the Commission's license review.
    (b) If requested by a State or Tribal governing body, the Director 
may approve all or any part of a proposal if the Director determines 
that:
    (1) The proposed activities are within the scope of Commission 
statutory responsibility and the type and magnitude of impacts which the 
State or Tribe may bear are sufficient to justify their participation; 
and
    (2) The proposed activities will contribute productively to the 
licensing review.
    (c) The decision of the Director will be transmitted in writing to 
the governor or the designated official of the Tribal governing body.
    (d) Participation by a State or Indian Tribe shall not affect their 
rights to participate in an adjudicatory hearing as provided by part 2 
of this chapter.



           Subpart G_Records, Reports, Tests, and Inspections



Sec. 61.80  Maintenance of records, reports, and transfers.

    (a) Each licensee shall maintain any records and make any reports in 
connection with the licensed activities as may be required by the 
conditions of the license or by the rules, regulations, and orders of 
the Commission.
    (b) Records which are required by the regulations in this part or by 
license conditions must be maintained for a period specified by the 
appropriate regulations in this chapter or by license condition. If a 
retention period is not otherwise specified, these records must be 
maintained and transferred to the officials specified in paragraph (e) 
of this section as a condition of license termination unless the 
Commission otherwise authorizes their disposition.
    (c) Records which must be maintained pursuant to this part may be 
the original or a reproduced copy or a microform if this reproduced copy 
or microform is capable of producing copy that is clear and legible at 
the end of the required retention period. The record may also be stored 
in electronic media with the capability for producing legible, accurate, 
and complete records during the required retention period. Records such 
as letters, drawings, specifications, must include all pertinent 
information such as stamps, initials, and signatures. The licensee shall 
maintain adequate safeguards against tampering with and loss of records.
    (d) If there is a conflict between the Commission's regulations in 
this part, license condition, or other written Commission approval or 
authorization pertaining to the retention period for the same type of 
record, the longest retention period specified takes precedence.

[[Page 235]]

    (e) Notwithstanding paragraphs (a) through (d) of this section, the 
licensee shall record the location and the quantity of radioactive 
wastes contained in the disposal site and transfer these records upon 
license termination to the chief executive of the nearest municipality, 
the chief executive of the county in which the facility is located, the 
county zoning board or land development and planning agency, the State 
governor and other State, local, and Federal governmental agencies as 
designated by the Commission at the time of license termination.
    (f) Following receipt and acceptance of a shipment of radioactive 
waste, the licensee shall record the date that the shipment is received 
at the disposal facility, the date of disposal of the waste, a traceable 
shipment manifest number, a description of any engineered barrier or 
structural overpack provided for disposal of the waste, the location of 
disposal at the disposal site, the containment integrity of the waste 
disposal containers as received, any discrepancies between materials 
listed on the manifest and those received, the volume of any pallets, 
bracing, or other shipping or onsite generated materials that are 
contaminated, and are disposed of as contaminated or suspect materials, 
and any evidence of leaking or damaged disposal containers or radiation 
or contamination levels in excess of limits specified in Department of 
Transportation and Commission regulations. The licensee shall briefly 
describe any repackaging operations of any of the disposal containers 
included in the shipment, plus any other information required by the 
Commission as a license condition. The licensee shall retain these 
records until the Commission transfers or terminates the license that 
authorizes the activities described in this section.
    (g) Each licensee shall comply with the safeguards reporting 
requirements of Sec. Sec. 30.55, 40.64, 74.13, and 74.15 of this 
chapter if the quantities or activities of materials received or 
transferred exceed the limits of these sections. Inventory reports 
required by these sections are not required for materials after 
disposal.
    (h) Each licensee authorized to dispose of radioactive waste 
received from other persons shall file a copy of its financial report or 
a certified financial statement annually with the Commission in order to 
update the information base for determining financial qualifications.
    (i)(1) Each licensee authorized to dispose of waste materials 
received from other persons under this part shall submit annual reports 
to the Director, Office of Nuclear Material Safety and Safeguards, by an 
appropriate method listed in Sec. 60.4 of this chapter, with a copy to 
the appropriate NRC Regional Office shown in appendix D to part 20 of 
this chapter. Reports must be submitted by the end of the first calendar 
quarter of each year for the preceding year.
    (2) The reports shall include (i) specification of the quantity of 
each of the principal radionuclides released to unrestricted areas in 
liquid and in airborne effluents during the preceding year, (ii) the 
results of the environmental monitoring program, (iii) a summary of 
licensee disposal unit survey and maintenance activities, (iv) a 
summary, by waste class, of activities and quantities of radionuclides 
disposed of, (v) any instances in which observed site characteristics 
were significantly different from those described in the application for 
a license; and (vi) any other information the Commission may require. If 
the quantities of radioactive materials released during the reporting 
period, monitoring results, or maintenance performed are significantly 
different from those expected in the materials previously reviewed as 
part of the licensing action, the report must cover this specifically.
    (j) Each licensee shall report in accordance with the requirements 
of Sec. 70.52 of this chapter.
    (k) Any transfer of byproduct, source, and special nuclear materials 
by the licensee is subject to the requirements in Sec. Sec. 30.41, 
40.51, and 70.42 of this chapter. Byproduct, source and special nuclear 
material means materials as defined in these parts, respectively.
    (l) In addition to the other requirements of this section, the 
licensee shall store, or have stored, manifest and other information 
pertaining to receipt

[[Page 236]]

and disposal of radioactive waste in an electronic recordkeeping system.
    (1) The manifest information that must be electronically stored is--
    (i) That required in 10 CFR part 20, appendix G, with the exception 
of shipper and carrier telephone numbers and shipper and consignee 
certifications; and
    (ii) That information required in paragraph (f) of this section.
    (2) As specified in facility license conditions, the licensee shall 
report the stored information, or subsets of this information, on a 
computer-readable medium.

[47 FR 57463, Dec. 27, 1982, as amended at 52 FR 31612, Aug. 21, 1987; 
53 FR 19251, May 27, 1988; 58 FR 33891, June 22, 1993; 60 FR 15666, Mar. 
27, 1995; 67 FR 78141, Dec. 23, 2002; 68 FR 58814, Oct. 10, 2003; 73 FR 
5725, Jan. 31, 2008; 79 FR 75740, Dec. 19, 2014]



Sec. 61.81  Tests at land disposal facilities.

    (a) Each licensee shall perform, or permit the Commission to 
perform, any tests as the Commission deems appropriate or necessary for 
the administration of the regulations in this part, including tests of:
    (1) Radioactive wastes and facilities used for the receipt, storage, 
treatment, handling and disposal of radioactive wastes.
    (2) Radiation detection and monitoring instruments; and
    (3) Other equipment and devices used in connection with the receipt, 
possession, handling, treatment, storage, or disposal of radioactive 
waste.



Sec. 61.82  Commission inspections of land disposal facilities.

    (a) Each licensee shall afford to the Commission at all reasonable 
times opportunity to inspect radioactive waste not yet disposed of, and 
the premises, equipment, operations, and facilities in which radioactive 
wastes are received, possessed, handled, treated, stored, or disposed 
of.
    (b) Each licensee shall make available to the Commission for 
inspection, upon reasonable notice, records kept by it pursuant to the 
regulations in this chapter. Authorized representatives of the 
Commission may copy and take away copies of, for the Commission's use, 
any record required to be kept pursuant to this part.



Sec. 61.83  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55077, Nov. 24, 1992]



Sec. 61.84  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 61 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 61 that are not issued under sections 
161b, 161i, or 161o for the purposes of Section 223 are as follows: 
Sec. Sec. 61.1, 61.2, 61.4, 61.5, 61.6, 61.7, 61.8, 61.10, 61.11, 
61.12, 61.13, 61.14, 61.15, 61.16, 61.20, 61.21, 61.22, 61.23, 61.26, 
61.30, 61.31, 61.50, 61.51, 61.54, 61.55,

[[Page 237]]

61.58, 61.59, 61.61, 61.63, 61.70, 61.71, 61.72, 61.73, 61.83, and 
61.84.

[57 FR 55077, Nov. 24, 1992]



PART 62_CRITERIA AND PROCEDURES FOR EMERGENCY ACCESS TO NON-FEDERAL
AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES--Table of Contents



                      Subpart A_General Provisions

Sec.
62.1 Purpose and scope.
62.2 Definitions.
62.3 Communications.
62.4 Interpretations.
62.5 Specific exemptions.
62.8 Information collection requirements: OMB approval.

            Subpart B_Request for a Commission Determination

62.11 Filing and distribution of a determination request.
62.12 Contents of a request for emergency access: General information.
62.13 Contents of a request for emergency access: Alternatives.
62.14 Contents of a request for an extension of emergency access.
62.15 Additional information.
62.16 Withdrawal of a determination request.
62.17 Elimination of repetition.
62.18 Denial of request.

            Subpart C_Issuance of a Commission Determination

62.21 Determination for granting emergency access.
62.22 Notice of issuance of a determination.
62.23 Determination for granting temporary emergency access.
62.24 Extension of emergency access.
62.25 Criteria for a Commission determination.
62.26 Criteria for designating a disposal facility.

                Subpart D_Termination of Emergency Access

62.31 Termination of emergency access.

    Authority: Atomic Energy Act of 1954, sec. 161 (42 U.S.C. 2201); 
Energy Reorganization Act of 1974, secs. 201 (42 U.S.C. 5841); Low-Level 
Radioactive Waste Policy Amendments Act of 1985, secs. 2, 6 (42 U.S.C. 
2021b, 2021f); 44 U.S.C. 3504 note.

    Source: 54 FR 5420, Feb. 3, 1989, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 62.1  Purpose and scope.

    (a) The regulations in this part establish for specific low-level 
radioactive waste:
    (1) Criteria and procedures for granting emergency access under 
section 6 of the Low-Level Radioactive Waste Policy Amendments Act of 
1985 (42 U.S.C. 2021) to any non-Federal or regional low-level 
radioactive waste (LLW) disposal facility or to any non-Federal disposal 
facility within a State that is not a member of a Compact, and
    (2) The terms and conditions upon which the Commission will grant 
this emergency access.
    (b) The regulations in this part apply to all persons as defined by 
this regulation, who have been denied access to existing regional or 
non-Federal low-level radioactive waste disposal facilities and who 
submit a request to the Commission for a determination pursuant to this 
part.
    (c) The regulations in this part apply only to the LLW that the 
States have the responsibility to dispose of pursuant to section 3(1)(a) 
of the Act.



Sec. 62.2  Definitions.

    As used in this part:
    Act means the Low-Level Radioactive Waste Policy Amendments Act of 
1985 (Pub. L. 99-240).
    Agreement State means a State that--
    (1) Has entered into an agreement with the Nuclear Regulatory 
Commission under section 274 of the Atomic Energy Act of 1954 (42 U.S.C. 
2021); and
    (2) Has authority to regulate the disposal of low-level radioactive 
waste under such agreement.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Compact means a Compact entered into by two or more States pursuant 
to the Low-Level Radioactive Waste Policy Amendments Act of 1985.
    Compact Commission means the regional commission, committee, or 
board established in a Compact to administer such Compact.
    Disposal means the permanent isolation of low-level radioactive 
waste pursuant to the requirements established by the Nuclear Regulatory 
Commission

[[Page 238]]

under applicable laws, or by an Agreement State if such isolation occurs 
in this Agreement State.
    Emergency access means access to an operating non-Federal or 
regional low-level radioactive waste disposal facility or facilities for 
a period not to exceed 180 days, which is granted by NRC to a generator 
of low-level radioactive waste who has been denied the use of those 
facilities.
    Extension of emergency access means an extension of the access that 
had been previously granted by NRC to an operating non-Federal or 
regional low-level radioactive waste disposal facility or facilities for 
a period not to exceed 180 days.
    Low-level radioactive waste (LLW) means radioactive material that--
    (1) Is not high-level radioactive waste, spent nuclear fuel, or 
byproduct material (as defined in paragraphs (2), (3), and (4) of the 
definition of Byproduct Material set forth in Sec. 20.1003 of this 
chapter); and
    (2) The NRC, consistent with existing law and in accordance with 
paragraph (1) of this definition, classifies as low-level radioactive 
waste.
    Non-Federal disposal facility means a low-level radioactive waste 
disposal facility that is commercially operated or is operated by a 
State.
    Person means any individual, corporation, partnership, firm, 
association, trust, State, public or private institution, group or 
agency who is an NRC or NRC Agreement State licensed generator of low-
level radioactive waste within the scope of Sec. 62.1(c) of this part; 
any Governor (or for any State without a Governor, the chief executive 
officer of the State) on behalf of any NRC or NRC Agreement State 
licensed generator or generators of low-level radioactive waste within 
the scope of Sec. 62.1(c) of this part located in his or her State; or 
their duly authorized representative, legal successor, or agent.
    Regional disposal facility means a non-Federal low-level radioactive 
waste disposal facility in operation on January 1, 1985, or subsequently 
established and operated under a compact.
    State means any State of the United States, the District of 
Columbia, and the Commonwealth of Puerto Rico.
    Temporary emergency access means access that is granted at NRC's 
discretion under Sec. 62.23 of this part upon determining that access 
is necessary to eliminate an immediate and serious threat to the public 
health and safety or the common defense and security. Such access 
expires 45 days after the granting and cannot be extended.

[54 FR 5420, Feb. 3, 1989, as amended at 72 FR 55933, Oct. 1, 2007]



Sec. 62.3  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk, 
Director, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; by hand delivery to 
the NRC's offices at 11555 Rockville Pike, Rockville, Maryland; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, or CD-ROM. Electronic submissions must be made in 
a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[73 FR 5725, Jan. 31, 2008, as amended at 74 FR 62683, Dec. 1, 2009; 79 
FR 75740, Dec. 19, 2014; 80 FR 74980, Dec. 1, 2015]



Sec. 62.4  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General

[[Page 239]]

Counsel will be considered binding on the Commission.



Sec. 62.5  Specific exemptions.

    The Commission may, upon application of any interested person or 
upon its own initiative, grant an exemption from the requirements of the 
regulations in this part that it determines is authorized by law and 
will not endanger life or property or the common defense and security 
and is otherwise in the public interest.



Sec. 62.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0143.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 62.11, 62.12, 62.13, 62.14, and 62.15.

[54 FR 5420, Feb. 3, 1989, as amended at 62 FR 52188, Oct. 6, 1997]



            Subpart B_Request for a Commission Determination



Sec. 62.11  Filing and distribution of a determination request.

    (a) The person submitting a request for a Commission determination 
shall file a signed original of the request with the Commission at the 
address specified in Sec. 62.3 of this part, with a copy also provided 
to the appropriate Regional Administrator at the address specified in 
appendix D to part 20 of this chapter. The request must be signed by the 
person requesting the determination or the person's authorized 
representative under oath or affirmation.
    (b) Upon receipt of a request for a determination, the Secretary of 
the Commission shall publish a notice acknowledging receipt of the 
request in the Federal Register. The notice must require that public 
comment on the request be submitted within 10 days of the publication 
date of the notice. A copy of the request will be made available for 
inspection or copying at the NRC Web site, http://www.nrc.gov, and/or at 
the NRC Public Document Room. The Secretary of the Commission shall also 
transmit a copy of the request to the U.S. Department of Energy, to the 
Governors of the States of the Compact region where the waste is 
generated, to the Governors of the States with operating non-Federal 
low-level radioactive waste disposal facilities, to the Compact 
Commissions with operating regional low-level radioactive waste disposal 
facilities, and to the Governors of the States in the Compact 
Commissions with operating disposal facilities.
    (c) Upon receipt of a request for a determination based on a serious 
and immediate threat to the common defense and security, the Commission 
will notify DOD and/or DOE and provide a copy of the request as needed 
for their consideration.
    (d) Fees applicable to a request for a Commission determination 
under this part will be determined in accordance with the procedures set 
forth for special projects under category 12 of Sec. 170.31 of this 
chapter.
    (e) In the event that the allocations or limitations established in 
section 5(b) or 6(h) of the Act are met at all operating non-Federal or 
regional LLW disposal facilities, the Commission may suspend the 
processing or acceptance of requests for emergency access determinations 
until additional LLW disposal capacity is authorized by Congress.

[54 FR 5420, Feb. 3, 1989, as amended at 64 FR 48954, Sept. 9, 1999; 68 
FR 58814, Oct. 10, 2003]



Sec. 62.12  Contents of a request for emergency access: 
General information.

    A request for a Commission determination under this part must 
include the following information for each generator to which the 
request applies:
    (a) Name and address of the person making the request;
    (b) Name and address of the person(s) or company(ies) generating the 
low-

[[Page 240]]

level radioactive waste for which the determination is sought;
    (c) A statement indicating whether the generator is basing the 
request on the grounds of a serious and immediate threat to the public 
health and safety or the common defense and security;
    (d) Certification that the radioactive waste for which emergency 
access is requested is low-level radioactive waste within Sec. 62.1(c) 
of this part;
    (e) The low-level waste generation facility(ies) producing the waste 
for which the request is being made;
    (f) A description of the activity that generated the waste;
    (g) Name of the disposal facility or facilities which had been 
receiving the waste stream of concern before the generator was denied 
access;
    (h) A description of the low-level radioactive waste for which 
emergency access is requested, including--
    (1) The characteristics and composition of the waste, including, but 
not limited to--
    (i) Type of waste (e.g. solidified oil, scintillation fluid, failed 
equipment);
    (ii) Principal chemical composition;
    (iii) Physical state (solid, liquid, gas);
    (iv) Type of solidification media; and
    (v) Concentrations and percentages of any hazardous or toxic 
chemicals, chelating agents, or infectious or biological agents 
associated with the waste;
    (2) The radiological characteristics of the waste such as--
    (i) The classification of the waste in accordance with 61.55;
    (ii) A list of the radionuclides present or potentially present in 
the waste, their concentration or contamination levels, and total 
quantity;
    (iii) Distribution of the radionuclides within the waste (surface or 
volume distribution);
    (iv) Amount of transuranics (nanocuries/gram);
    (3) The minimum volume of the waste requiring emergency access to 
eliminate the threat to the public health and safety or the common 
defense and security;
    (4) The time duration for which emergency access is requested (not 
to exceed 180 days);
    (5) Type of disposal container or packaging (55 gallon drum, box, 
liner, etc.); and
    (6) Description of the volume reduction and waste minimization 
techniques applied to the waste which assure that it is reduced to the 
maximum extent practicable, and the actual reduction in volume that 
occurred;
    (i) Basis for requesting the determination set out in this part, 
including--
    (1) The circumstances that led to the denial of access to existing 
low-level radioactive waste disposal facilities;
    (2) A description of the situation that is responsible for creating 
the serious and immediate threat to the public health and safety or the 
common defense and security, including the date when the need for 
emergency access was identified;
    (3) A chronology and description of the actions taken by the person 
requesting emergency access to prevent the need for making such a 
request, including consideration of all alternatives set forth in Sec. 
62.13 of this part, and any supporting documentation as appropriate;
    (4) An explanation of the impacts of the waste on the public health 
and safety or the common defense and security if emergency access is not 
granted, and the basis for concluding that these impacts constitute a 
serious and immediate threat to the public health and safety or the 
common defense and security. The impacts to the public health and safety 
or the common defense and security should also be addressed if the 
generator's services, including research activities, were to be 
curtailed, either for a limited period of time or indefinitely;
    (5) Other consequences if emergency access is not granted;
    (j) Steps taken by the person requesting emergency access to correct 
the situation requiring emergency access and the person's plans to 
eliminate the need for additional or future emergency access requests;
    (k) Documentation certifying that access has been denied;
    (l) Documentation that the waste for which emergency access is 
requested could not otherwise qualify for disposal

[[Page 241]]

pursuant to the Unusual Volumes provision (Section 5(c)(5) of the Act) 
or is not simultaneously under consideration by the Department of Energy 
(DOE) for access through the Unusual Volumes allocation;
    (m) Date by which access is required;
    (n) Any other information which the Commission should consider in 
making its determination.



Sec. 62.13  Contents of a request for emergency access: Alternatives.

    (a) A request for emergency access under this part must include 
information on alternatives to emergency access. The request shall 
include a discussion of the consideration given to any alternatives, 
including, but not limited to, the following:
    (1) Storage of low-level radioactive waste at the site of 
generation;
    (2) Storage of low-level radioactive waste in a licensed storage 
facility;
    (3) Obtaining access to a disposal facility by voluntary agreement;
    (4) Purchasing disposal capacity available for assignment pursuant 
to the Act;
    (5) Requesting disposal at a Federal low-level radioactive waste 
disposal facility in the case of a Federal or defense related generator 
of LLW;
    (6) Reducing the volume of the waste;
    (7) Ceasing activities that generate low-level radioactive waste; 
and
    (8) Other alternatives identified under paragraph (b) of this 
section.
    (b) The request must identify all of the alternatives to emergency 
access considered, including any that would require State or Compact 
action, or any others that are not specified in paragraph (a) of this 
section. The request should also include a description of the process 
used to identify the alternatives, a description of the factors that 
were considered in identifying and evaluating them, a chronology of 
actions taken to identify and implement alternatives during the process, 
and a discussion of any actions that were considered, but not 
implemented.
    (c) The evaluation of each alternative must consider:
    (1) Its potential for mitigating the serious and immediate threat to 
public health and safety or the common defense and security posed by 
lack of access to disposal;
    (2) The adverse effects on public health and safety and the common 
defense and security, if any, of implementing each alternative, 
including the curtailment or cessation of any essential services 
affecting the public health and safety or the common defense and 
security;
    (3) The technical and economic feasibility of each alternative 
including the person's financial capability to implement the 
alternatives;
    (4) Any other pertinent societal costs and benefits;
    (5) Impacts to the environment;
    (6) Any legal impediments to implementation of each alternative, 
including whether the alternatives will comply with applicable NRC and 
NRC Agreement States regulatory requirements; and
    (7) The time required to develop and implement each alternative.
    (d) The request must include the basis for:
    (1) Rejecting each alternative; and
    (2) Concluding that no alternative is available.



Sec. 62.14  Contents of a request for an extension of emergency
access.

    A request for an extension of emergency access must include:
    (a) Updates of the information required in Sec. Sec. 62.12 and 
62.13; and
    (b) Documentation that the generator of the low-level radioactive 
waste granted emergency access and the State in which the low-level 
radioactive waste was generated have diligently, though unsuccessfully, 
acted during the period of the initial grant to eliminate the need for 
emergency access. Documentation must include:
    (1) An identification of additional alternatives that have been 
evaluated during the period of the initial grant, and
    (2) A discussion of any reevaluation of previously considered 
alternatives, including verification of continued attempts to gain 
access to a disposal facility by voluntary agreement.



Sec. 62.15  Additional information.

    (a) The Commission may require additional information from a person

[[Page 242]]

making a request for a Commission determination under this part 
concerning any portion of the request.
    (b) The Commission shall deny a request for a Commission 
determination under this part if the person making the request fails to 
respond to a request for additional information under paragraph (a) of 
this section within ten (10) days from the date of the request for 
additional information, or any other time that the Commission may 
specify. This denial will not prejudice the right of the person making 
the request to file another request for a Commission determination under 
this part.



Sec. 62.16  Withdrawal of a determination request.

    (a) A person may withdraw a request for a Commission determination 
under this part without prejudice at any time prior to the issuance of 
an initial determination under Sec. 62.21 of this part.
    (b) The Secretary of the Commission will cause to be published in 
the Federal Register a notice of the withdrawal of a request for a 
Commission determination under this part.



Sec. 62.17  Elimination of repetition.

    In any request under this part, the person making the request may 
incorporate by reference information contained in a previous 
application, Statement, or report filed with the Commission provided 
that these references are updated, clear, and specific.



Sec. 62.18  Denial of request.

    If a request for a determination is based on circumstances that are 
too remote and speculative to allow an informed determination, the 
Commission may deny the request.



            Subpart C_Issuance of a Commission Determination



Sec. 62.21  Determination for granting emergency access.

    (a) Not later than (45) days after the receipt of a request for a 
Commission determination under this part from any generator of low-level 
radioactive waste, or any Governor on behalf of any generator or 
generators located in his or her State, the Commission shall determine 
whether--
    (1) Emergency access to a regional disposal facility or a non-
Federal disposal facility within a State that is not a member of a 
Compact for specific low-level radioactive waste is necessary because of 
an immediate and serious threat--
    (i) To the public health and safety or
    (ii) The common defense and security; and
    (2) The threat cannot be mitigated by any alternative consistent 
with the public health and safety, including those identified in Sec. 
62.13.
    (b) In making a determination under this section, the Commission 
shall be guided by the criteria set forth in Sec. 62.25 of this part.
    (c) A determination under this section must be in writing and 
contain a full explanation of the facts upon which the determination is 
based and the reasons for granting or denying the request. An 
affirmative determination must designate an appropriate non-Federal or 
regional LLW disposal facility or facilities for the disposal of wastes, 
specifically describe the low-level radioactive waste as to source, 
physical and radiological characteristics, and the minimum volume and 
duration (not to exceed 180 days) necessary to eliminate the immediate 
threat to public health and safety or the common defense and security. 
It may also contain conditions upon which the determination is 
dependent.



Sec. 62.22  Notice of issuance of a determination.

    (a) Upon the issuance of a Commission determination the Secretary of 
the Commission will notify in writing the following persons of the final 
determination: The person making the request, the Governor of the State 
in which the low-level radioactive waste requiring emergency access was 
generated, the Governor of the State in which the designated disposal 
facility is located, and if pertinent, the appropriate Compact 
Commission for such approval as is specified as necessary in section 
6(g) of the Act. For the Governor of the State in which the designated 
disposal facility is located and for the appropriate Compact Commission, 
the notification must set forth the reasons that emergency access was

[[Page 243]]

granted and specifically describe the low-level radioactive waste as to 
source, physical and radiological characteristics, and the minimum 
volume and duration (not to exceed 180 days) necessary to alleviate the 
immediate and serious threat to public health and safety or the common 
defense and security. For the Governor of the State in which the low-
level waste was generated, the notification must indicate that no 
extension of emergency access will be granted under Sec. 62.24 of this 
part absent diligent State and generator action during the period of the 
initial grant.
    (b) The Secretary of the Commission will cause to be published in 
the Federal Register a notice of the issuance of the determination.
    (c) The Secretary of the Commission shall make a copy of the final 
determination available for inspection at the NRC Web site, http://
www.nrc.gov.

[54 FR 5420, Feb. 3, 1989, as amended at 64 FR 48954, Sept. 9, 1999]



Sec. 62.23  Determination for granting temporary emergency access.

    (a) The Commission may grant temporary emergency access to an 
appropriate non-Federal or regional disposal facility or facilities 
provided that the determination required under Sec. 62.21(a)(1) of this 
part is made;
    (b) The notification procedures under Sec. 62.22 of this part are 
complied with; and
    (c) The temporary emergency access duration will not exceed forty-
five (45) days.



Sec. 62.24  Extension of emergency access.

    (a) After the receipt of a request from any generator of low-level 
waste, or any Governor on behalf of any generator or generators in his 
or her State, for an extension of emergency access that was initially 
granted under Sec. 62.21, the Commission shall make an initial 
determination of whether--
    (1) Emergency access continues to be necessary because of an 
immediate and serious threat to the public health and safety or the 
common defense and security;
    (2) The threat cannot be mitigated by any alternative that is 
consistent with public health and safety; and
    (3) The generator of low-level waste and the State have diligently 
though unsuccessfully acted during the period of the initial grant to 
eliminate the need for emergency access.
    (b) After making a determination pursuant to paragraph (a) of this 
section, the requirements specified in Sec. Sec. 62.21(c) and 62.22 of 
this part, must be followed.



Sec. 62.25  Criteria for a Commission determination.

    (a) In making the determination required by Sec. 62.21(a) of this 
part, the Commission will determine whether the circumstances described 
in the request for emergency access create a serious and immediate 
threat to the public health and safety or the common defense and 
security.
    (b) In making the determination that a serious and immediate threat 
exists to the public health and safety, the Commission will consider, 
notwithstanding the availability of any alternative identified in Sec. 
62.13 of this part:
    (1) The nature and extent of the radiation hazard that would result 
from the denial of emergency access, including consideration of--
    (i) The standards for radiation protection contained in part 20 of 
this chapter;
    (ii) Any standards governing the release of radioactive materials to 
the general environment that are applicable to the facility that 
generated the low level waste; and
    (iii) Any other Commission requirements specifically applicable to 
the facility or activity that is the subject of the emergency access 
request; and
    (2) The extent to which essential services affecting the public 
health and safety (such as medical, therapeutic, diagnostic, or research 
activities) will be disrupted by the denial of emergency access.
    (c) For purposes of granting temporary emergency access under Sec. 
62.23 of this part, the Commission will consider the criteria contained 
in the Commission's Policy Statement (45 FR 10950, February 24, 1977) 
for determining whether an event at a facility or activity licensed or 
otherwise regulated by the Commission is an abnormal occurrence within 
the purview of

[[Page 244]]

section 208 of the Energy Reorganization Act of 1974.
    (d) In making the determination that a serious and immediate threat 
to the common defense and security exists, the Commission will consider, 
notwithstanding the availability of any alternative identified in Sec. 
62.13 of this part:
    (1) Whether the activity generating the wastes is necessary to the 
protection of the common defense and security, and
    (2) Whether the lack of access to a disposal site would result in a 
significant disruption in that activity that would seriously threaten 
the common defense and security.

The Commission will consider the views of the Department of Defense 
(DOD) and or the Department of Energy (DOE) regarding the importance of 
the activities responsible for generating the LLW to the common defense 
and security, when evaluating requests based all, or in part, on a 
serious and immediate threat to the common defense and security.
    (e) In making the determination required by Sec. 62.21(a)(2) of 
this part, the Commission will consider whether the person submitting 
the request--
    (1) Has identified and evaluated any alternative that could mitigate 
the need for emergency access; and
    (2) Has considered all pertinent factors in its evaluation of 
alternatives including state-of-the-art technology and impacts on public 
health and safety.
    (f) In making the determination required by Sec. 62.21(a)(2) of 
this part, the Commission will consider implementation of an alternative 
to be unreasonable if:
    (1) It adversely affects public health and safety, the environment, 
or the common defense and security; or
    (2) It results in a significant curtailment or cessation of 
essential services, affecting public health and safety or the common 
defense and security; or
    (3) It is beyond the technical and economic capabilities of the 
person requesting emergency access; or
    (4) Implementation of the alternative would conflict with applicable 
State or local or Federal laws and regulations; or
    (5) It cannot be implemented in a timely manner.
    (g) The Commission shall make an affirmative determination under 
Sec. 62.21(a) of this part only if all of the alternatives that were 
considered are found to be unreasonable.
    (h) As part of its mandated evaluation of the alternatives that were 
considered by the generator, the Commission shall consider the 
characteristics of the wastes (including: physical properties, chemical 
properties, radioactivity, pathogenicity, infectiousness, and toxicity, 
pyrophoricity, and explosive potential); condition of current container; 
potential for contaminating the disposal site; the technologies or 
combination of technologies available for treatment of the waste 
(including incinerators; evaporators-crystallizers; fluidized bed 
dryers; thin film evaporators; extruders, evaporators; and Compactors); 
the suitability of volume reduction equipment to the circumstances 
(specific activity considerations, actual volume reduction factors, 
generation of secondary wastes, equipment contamination, effluent 
releases, worker exposure, and equipment availability); and the 
administrative controls which could be applied, in making a 
determination whether waste to be delivered for disposal under this part 
has been reduced in volume to the maximum extent practicable using 
available technology.



Sec. 62.26  Criteria for designating a disposal facility.

    (a) The Commission shall designate an appropriate non-Federal or 
regional disposal facility if an affirmative determination is made 
pursuant to Sec. Sec. 62.21, 62.23, or 62.24 of this part.
    (b) The Commission will exclude a disposal facility from 
consideration if:
    (1) The low-level radioactive wastes of the generator do not meet 
the criteria established by the license agreement or the license 
agreement of the facility; or
    (2) The disposal facility is in excess of its approved capacity; or
    (3) Granting emergency access would delay the closing of the 
disposal facility pursuant to plans established before the receipt of 
the request for emergency access; or

[[Page 245]]

    (4) The volume of waste requiring emergency access exceeds 20 
percent of the total volume of low-level radioactive waste accepted for 
disposal at the facility during the previous calendar year.
    (c) If, after applying the exclusionary criteria in paragraph (b) of 
this section, more than one disposal facility is identified as 
appropriate for designation, the Commission will then consider 
additional factors in designating a facility or facilities including--
    (1) Type of waste and its characteristics,
    (2) Previous disposal practices,
    (3) Transportation
    (4) Radiological effects,
    (5) Site capability for handling waste,
    (6) The volume of emergency access waste previously accepted by each 
site both for the particular year and overall, and
    (7) Any other considerations deemed appropriate by the Commission.
    (d) The Commission, in making its designation, will also consider 
any information submitted by the operating non-Federal or regional LLW 
disposal sites, or any information submitted by the public in response 
to a Federal Register notice requesting comment, as provided in 
paragraph (b) of Sec. 62.11 of this part.



                Subpart D_Termination of Emergency Access



Sec. 62.31  Termination of emergency access.

    (a) The Commission may terminate a grant of emergency access when 
emergency access is no longer necessary to eliminate an immediate threat 
to public health and safety or the common defense and security.
    (b) The Commission may terminate a grant of emergency access if an 
applicant has provided inaccurate information in its application for 
emergency access or if the applicant has failed to comply with this part 
or any conditions set by the Commission pursuant to this part.



PART 63_DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC 
REPOSITORY AT YUCCA MOUNTAIN, NEVADA--Table of Contents



                      Subpart A_General Provisions

Sec.
63.1 Purpose and scope.
63.2 Definitions.
63.3 License required.
63.4 Communications and records.
63.5 Interpretations.
63.6 Exemptions.
63.7 License not required for certain preliminary activities.
63.8 Information collection requirements: OMB approval.
63.9 Employee protection.
63.10 Completeness and accuracy of information.
63.11 Deliberate misconduct.

                           Subpart B_Licenses

                          Preapplication Review

63.15 Site characterization.
63.16 Review of site characterization activities.

                           License Application

63.21 Content of application.
63.22 Filing and distribution of application.
63.23 Elimination of repetition.
63.24 Updating of application and environmental impact statement.

                       Construction Authorization

63.31 Construction authorization.
63.32 Conditions of construction authorization.
63.33 Amendment of construction authorization.

                     License Issuance and Amendment

63.41 Standards for issuance of a license.
63.42 Conditions of license.
63.43 License specification.
63.44 Changes, tests, and experiments.
63.45 Amendment of license.
63.46 Particular activities requiring license amendment.

                      US/IAEA Safeguards Agreement

63.47 Facility information and verification.

                            Permanent Closure

63.51 License amendment for permanent closure.

[[Page 246]]

63.52 Termination of license.

  Subpart C_Participation by State Government, Affected Units of Local 
                 Government, and Affected Indian Tribes

63.61 Provision of information.
63.62 Site review.
63.63 Participation in license reviews.
63.64 Notice to State.
63.65 Representation.

           Subpart D_Records, Reports, Tests, and Inspections

63.71 Records and reports.
63.72 Construction records.
63.73 Reports of deficiencies.
63.74 Tests.
63.75 Inspections.
63.78 Material control and accounting records and reports.

                      Subpart E_Technical Criteria

63.101 Purpose and nature of findings.
63.102 Concepts.

                    Preclosure Performance Objectives

63.111 Performance objectives for the geologic repository operations 
          area through permanent closure.

                       Preclosure Safety Analysis

63.112 Requirements for preclosure safety analysis of the geologic 
          repository operations area.

                   Postclosure Performance Objectives

63.113 Performance objectives for the geologic repository after 
          permanent closure.

                   Postclosure Performance Assessment

63.114 Requirements for performance assessment.
63.115 Requirements for multiple barriers.

                       Land Ownership and Control

63.121 Requirements for ownership and control of interests in land.

               Subpart F_Performance Confirmation Program

63.131 General requirements.
63.132 Confirmation of geotechnical and design parameters.
63.133 Design testing.
63.134 Monitoring and testing waste packages.

                       Subpart G_Quality Assurance

63.141 Scope.
63.142 Quality assurance criteria.
63.143 Implementation.
63.144 Quality assurance program change.

            Subpart H_Training and Certification of Personnel

63.151 General requirements.
63.152 Training and certification program.
63.153 Physical requirements.

                  Subpart I_Emergency Planning Criteria

63.161 Emergency plan for the geologic repository operations area 
          through permanent closure.

                          Subpart J_Violations

63.171 Violations.
63.172 Criminal penalties.

     Subpart K_Preclosure Public Health and Environmental Standards

63.201 Purpose and scope.
63.202 Definitions for Subpart K.
63.203 Implementation of Subpart K.
63.204 Preclosure standard.

     Subpart L_Postclosure Public Health and Environmental Standards

63.301 Purpose and scope.
63.302 Definitions for Subpart L.
63.303 Implementation of Subpart L.
63.304 Reasonable expectation.
63.305 Required characteristics of the reference biosphere.

               Postclosure Individual Protection Standard

63.311 Individual protection standard after permanent closure.
63.312 Required characteristics of the reasonably maximally exposed 
          individual.

                        Human Intrusion Standard

63.321 Individual protection standard for human intrusion.
63.322 Human intrusion scenario.

                    Groundwater Protection Standards

63.331 Separate standards for protection of groundwater.
63.332 Representative volume.

                          Additional Provisions

63.342 Limits on performance assessments.
63.343 Severability of individual protection and groundwater protection 
          standards.

    Authority: Atomic Energy Act of 1954, secs. 51, 53, 62, 63, 65, 81, 
161, 182, 183, 223, 234 (42 U.S.C. 2071, 2073, 2092, 2093, 2095, 2111, 
2201, 2232, 2233, 2273, 2282); Energy Reorganization Act of 1974, secs. 
201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); 42 U.S.C. 2021a; 
National Environmental Policy Act of 1969 (42 U.S.C.

[[Page 247]]

4332); Nuclear Waste Policy Act of 1982, secs. 114, 117, 121 (42 U.S.C. 
10134, 10137, 10141); 44 U.S.C. 3504 note.

    Source: 66 FR 55792, Nov. 2, 2001, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 63 appear at 81 FR 
86909, Dec. 2, 2016.



                      Subpart A_General Provisions



Sec. 63.1  Purpose and scope.

    This part prescribes rules governing the licensing (including 
issuance of a construction authorization) of the U.S. Department of 
Energy to receive and possess source, special nuclear, and byproduct 
material at a geologic repository operations area sited, constructed, or 
operated at Yucca Mountain, Nevada, in accordance with the Nuclear Waste 
Policy Act of 1982, as amended, and the Energy Policy Act of 1992. As 
provided in 10 CFR 60.1, the regulations in part 60 of this chapter do 
not apply to any activity licensed under another part of this chapter. 
This part also gives notice to all persons who knowingly provide to any 
licensee, applicant, contractor, or subcontractor, components, 
equipment, materials, or other goods or services, that relate to a 
licensee's or applicant's activities subject to this part, that they may 
be individually subject to NRC enforcement action for violation of Sec. 
63.11.

[69 FR 2280, Jan. 14, 2004]



Sec. 63.2  Definitions.

    As used in this part:
    Affected Indian Tribe means any Indian Tribe within whose 
reservation boundaries a repository for high-level radioactive waste or 
spent fuel is proposed to be located; or whose Federally-defined 
possessory or usage rights to other lands outside of the reservation's 
boundaries arising out of Congressionally-ratified treaties or other 
Federal law may be substantially and adversely affected by the location 
of the facility if the Secretary of the Interior finds, on the petition 
of the appropriate governmental officials of the Tribe, that the effects 
are both substantial and adverse to the Tribe.
    Barrier means any material, structure, or feature that, for a period 
to be determined by NRC, prevents or substantially reduces the rate of 
movement of water or radionuclides from the Yucca Mountain repository to 
the accessible environment, or prevents the release or substantially 
reduces the release rate of radionuclides from the waste. For example, a 
barrier may be a geologic feature, an engineered structure, a canister, 
a waste form with physical and chemical characteristics that 
significantly decrease the mobility of radionuclides, or a material 
placed over and around the waste, provided that the material 
substantially delays movement of water or radionuclides.
    Commencement of construction means clearing of land, surface or 
subsurface excavation, or other substantial action that would adversely 
affect the environment of a site. It does not include changes desirable 
for the temporary use of the land for public recreational uses, site 
characterization activities, other preconstruction monitoring and 
investigation necessary to establish background information related to 
the suitability of the Yucca Mountain site or to the protection of 
environmental values, or procurement or manufacture of components of the 
geologic repository operations area.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Containment means the confinement of radioactive waste within a 
designated boundary.
    Design bases means that information that identifies the specific 
functions to be performed by a structure, system, or component of a 
facility and the specific values or ranges of values chosen for 
controlling parameters as reference bounds for design. These values may 
be constraints derived from generally accepted ``state-of-the-art'' 
practices for achieving functional goals or requirements derived from 
analysis (based on calculation or experiments) of the effects of a 
postulated event under which a structure, system, or component must meet 
its functional goals. The values for controlling parameters for external 
events include:
    (1) Estimates of severe natural events to be used for deriving 
design bases that will be based on consideration of

[[Page 248]]

historical data on the associated parameters, physical data, or analysis 
of upper limits of the physical processes involved; and
    (2) Estimates of severe external human-induced events to be used for 
deriving design bases, that will be based on analysis of human activity 
in the region, taking into account the site characteristics and the 
risks associated with the event.
    Director means the Director of the Nuclear Regulatory Commission's 
Office of Nuclear Material Safety and Safeguards.
    Disposal means the emplacement of radioactive waste in a geologic 
repository with the intent of leaving it there permanently.
    DOE means the U.S. Department of Energy or its duly authorized 
representatives.
    Engineered barrier system means the waste packages, including 
engineered components and systems other than the waste package (e.g., 
drip shields), and the underground facility.
    Event sequence means a series of actions and/or occurrences within 
the natural and engineered components of a geologic repository 
operations area that could potentially lead to exposure of individuals 
to radiation. An event sequence includes one or more initiating events 
and associated combinations of repository system component failures, 
including those produced by the action or inaction of operating 
personnel. Those event sequences that are expected to occur one or more 
times before permanent closure of the geologic repository operations 
area are referred to as Category 1 event sequences. Other event 
sequences that have at least one chance in 10,000 of occurring before 
permanent closure are referred to as Category 2 event sequences.
    Geologic repository means a system that is intended to be used for, 
or may be used for, the disposal of radioactive wastes in excavated 
geologic media. A geologic repository includes the engineered barrier 
system and the portion of the geologic setting that provides isolation 
of the radioactive waste.
    Geologic repository operations area means a high-level radioactive 
waste facility that is part of a geologic repository, including both 
surface and subsurface areas, where waste handling activities are 
conducted.
    Geologic setting means the geologic, hydrologic, and geochemical 
systems of the region in which a geologic repository is or may be 
located.
    High-level radioactive waste or HLW means:
    (1) The highly radioactive material resulting from the reprocessing 
of spent nuclear fuel, including liquid waste produced directly in 
reprocessing and any solid material derived from such liquid waste that 
contains fission products in sufficient concentrations;
    (2) Irradiated reactor fuel; and
    (3) Other highly radioactive material that the Commission, 
consistent with existing law, determines by rule requires permanent 
isolation.
    HLW facility means a facility subject to the licensing and related 
regulatory authority of the Commission pursuant to sections 202(3) and 
202(4) of the Energy Reorganization Act of 1974 (88 Stat. 1244). \1\
---------------------------------------------------------------------------

    \1\ These are DOE ``facilities used primarily for the receipt and 
storage of high-level radioactive wastes resulting from activities 
licensed under such Act (the Atomic Energy Act)'' and ``Retrievable 
Surface Storage Facilities and other facilities authorized for the 
express purpose of subsequent long-term storage of high-level 
radioactive wastes generated by (DOE), which are not used for, or are 
part of, research and development activities.''
---------------------------------------------------------------------------

    Host rock means the geologic medium in which the waste is emplaced.
    Important to safety, with reference to structures, systems, and 
components, means those engineered features of the geologic repository 
operations area whose function is:
    (1) To provide reasonable assurance that high-level waste can be 
received, handled, packaged, stored, emplaced, and retrieved without 
exceeding the requirements of Sec. 63.111(b)(1) for Category 1 event 
sequences; or
    (2) To prevent or mitigate Category 2 event sequences that could 
result in radiological exposures exceeding the values specified at Sec. 
63.111(b)(2) to any individual located on or beyond any point on the 
boundary of the site.

[[Page 249]]

    Important to waste isolation, with reference to design of the 
engineered barrier system and characterization of natural barriers, 
means those engineered and natural barriers whose function is to provide 
a reasonable expectation that high-level waste can be disposed of 
without exceeding the requirements of Sec. 63.113(b) and (c).
    Initiating event means a natural or human induced event that causes 
an event sequence.
    Isolation means inhibiting the transport of radioactive material to:
    (1) The location of the reasonably maximally exposed individual so 
that radiological exposures will not exceed the requirements of Sec. 
63.113(b); and
    (2) The accessible environment so that releases of radionuclides 
into the accessible environment will not exceed the requirements of 
Sec. 63.113(c).
    Performance assessment means an analysis that:
    (1) Identifies the features, events, processes (except human 
intrusion), and sequences of events and processes (except human 
intrusion) that might affect the Yucca Mountain disposal system and 
their probabilities of occurring;
    (2) Examines the effects of those features, events, processes, and 
sequences of events and processes upon the performance of the Yucca 
Mountain disposal system; and
    (3) Estimates the dose incurred by the reasonably maximally exposed 
individual, including the associated uncertainties, as a result of 
releases caused by all significant features, events, processes, and 
sequences of events and processes, weighted by their probability of 
occurrence.
    Performance confirmation means the program of tests, experiments, 
and analyses that is conducted to evaluate the adequacy of the 
information used to demonstrate compliance with the performance 
objectives in subpart E of this part.
    Permanent closure means final backfilling of the underground 
facility, if appropriate, and the sealing of shafts, ramps, and 
boreholes.
    Preclosure safety analysis means a systematic examination of the 
site; the design; and the potential hazards, initiating events and event 
sequences and their consequences (e.g., radiological exposures to 
workers and the public). The analysis identifies structures, systems, 
and components important to safety.
    Public Document Room means the place at One White Flint North, 11555 
Rockville Pike, Room O-1F13, Rockville, MD, at which records of the 
Commission will ordinarily be made available for public inspection and 
any other place, the location of which has been published in the Federal 
Register, at which public records of the Commission pertaining to a 
geologic repository at the Yucca Mountain site are made available for 
public inspection.
    Publicly Available Records System (PARS) Library means the 
electronic library generated by the NRC's Agencywide Documents Access 
and Management System (ADAMS) to provide access to public documents. 
PARS has full text documents which can be searched using specific fields 
and parameters. The public can search, download, print, create reports, 
and order documents online. The PARS Library contains publicly available 
documents created or received by NRC since November 1, 1999, as well as 
some older documents that the NRC has retrofit into the collection. PARS 
is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm.html.
    Radioactive waste or waste means HLW and radioactive materials other 
than HLW that are received for emplacement in a geologic repository.
    Reasonably maximally exposed individual means the hypothetical 
person meeting the criteria specified at Sec. 63.312.
    Reference biosphere means the description of the environment 
inhabited by the reasonably maximally exposed individual. The reference 
biosphere comprises the set of specific biotic and abiotic 
characteristics of the environment, including, but not necessarily 
limited to, climate, topography, soils, flora, fauna, and human 
activities.
    Restricted area means an area, access to which is limited by the 
licensee for the purpose of protecting individuals against undue risks 
from exposure to radiation and radioactive materials. Restricted area 
does not include areas

[[Page 250]]

used as residential quarters, but separate rooms in a residential 
building may be set aside as a restricted area.
    Retrieval means the act of permanently removing radioactive waste 
from the underground location at which the waste had been previously 
emplaced for disposal.
    Saturated zone means that part of the earth's crust beneath the 
regional water table in which statistically all voids, large and small, 
are filled with water under pressure greater than atmospheric.
    Site means that area surrounding the geologic repository operations 
area for which DOE exercises authority over its use in accordance with 
the provisions of this part.
    Site characterization means the program of exploration and research, 
both in the laboratory and in the field, undertaken to establish the 
geologic conditions and the ranges of those parameters of the Yucca 
Mountain site, and the surrounding region to the extent necessary, 
relevant to the procedures under this part. Site characterization 
includes borings, surface excavations, excavation of exploratory shafts 
and/or ramps, limited subsurface lateral excavations and borings, and in 
situ testing at depth needed to determine the suitability of the site 
for a geologic repository.
    Total effective dose equivalent (TEDE) means the sum of the 
effective dose equivalent (for external exposures) and the committed 
effective dose equivalent (for internal exposures).
    Underground facility means the underground structure, backfill 
materials, if any, and openings that penetrate the underground structure 
(e.g., ramps, shafts, and boreholes, including their seals).
    Unrestricted area means an area, access to which is neither limited 
nor controlled by the licensee.
    Unsaturated zone means the zone between the land surface and the 
regional water table. Generally, fluid pressure in this zone is less 
than atmospheric pressure, and some of the voids may contain air or 
other gases at atmospheric pressure. Beneath flooded areas or in perched 
water bodies, the fluid pressure locally may be greater than 
atmospheric.
    Waste form means the radioactive waste materials and any 
encapsulating or stabilizing matrix.
    Waste package means the waste form and any containers, shielding, 
packing, and other absorbent materials immediately surrounding an 
individual waste container.
    Water table means that surface in a groundwater body, separating the 
unsaturated zone from the saturated zone, at which the water pressure is 
atmospheric.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003; 74 
FR 10828, Mar. 13, 2009]



Sec. 63.3  License required.

    (a) DOE may not receive nor possess source, special nuclear, or 
byproduct material at a geologic repository operations area at the Yucca 
Mountain site except as authorized by a license issued by the Commission 
under this part.
    (b) DOE may not begin construction of a geologic repository 
operations area at the Yucca Mountain site unless it has filed an 
application with the Commission and has obtained construction 
authorization as provided in this part. Failure to comply with this 
requirement is grounds for denial of a license.



Sec. 63.4  Communications and records.

    (a) Except as otherwise specified, in this part or in subpart J of 
part 2 of this chapter, all communications and reports concerning the 
regulations in this part and applications filed under them should be 
sent to the NRC as follows:
    (1) By mail addressed: ATTN: Document Control Desk; Director, Office 
of Nuclear Material Safety and Safeguards; U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001;
    (2) By hand delivery to the NRC's offices at 11555 Rockville Pike, 
Rockville, Maryland; ATTN: Document Control Desk: Director, Office of 
Nuclear Material Safety and Safeguards; or,
    (3) Where practicable, by electronic submission, for example, via 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a

[[Page 251]]

time. Detailed guidance on making electronic submissions can be obtained 
by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-
submittals.html; by e-mail to [email protected]; or by writing the 
Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. The guidance discusses, among 
other topics, the formats the NRC can accept, the use of electronic 
signatures, and the treatment of nonpublic information.
    (b) Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform if the copy or 
microform is authenticated by authorized personnel and the microform is 
capable of producing a clear copy throughout the required retention 
period. The record may also be stored in electronic media with the 
capability for producing legible, accurate, and complete records during 
the required retention period. Records such as letters, drawings, and 
specifications must include all pertinent information such as stamps, 
initials, and signatures. The licensee shall maintain adequate 
safeguards against tampering with and loss of records.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003; 74 
FR 62683, Dec. 1, 2009; 80 FR 74981, Dec. 1, 2015]



Sec. 63.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel is binding on the Commission.



Sec. 63.6  Exemptions.

    The Commission may, upon application by DOE, any interested person, 
or upon its own initiative, grant an exemption from the requirements of 
this part if it determines that the exemption is authorized by law, does 
not endanger life nor property nor the common defense and security, and 
is otherwise in the public interest.



Sec. 63.7  License not required for certain preliminary activities.

    The requirement for a license set forth in Sec. 63.3(a) is not 
applicable to the extent that DOE receives and possesses source, special 
nuclear, and byproduct material at a geologic repository at the Yucca 
Mountain site:
    (a) For purposes of site characterization; or
    (b) For use, during site characterization or construction, as 
components of radiographic, radiation monitoring, or similar equipment 
or instrumentation.



Sec. 63.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501, et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0199.
    (b) The approved information collection requirements contained in 
this Part appear in Sec. Sec. 63.47, 63.62, 63.63, and 63.65.
    (c) In Sec. 63.47, Form N-71 and associated forms are approved 
under control number 3150-0056, and DOC/NRC Forms AP-1, AP-A, and 
associated forms are approved under control numbers 0694-0135.

[66 FR 55792, Nov. 2, 2001, as amended at 73 FR 78606, Dec. 23, 2008]



Sec. 63.9  Employee protection.

    (a) Discrimination by a Commission licensee, an applicant for a 
Commission license, or a contractor or subcontractor of a Commission 
licensee or applicant, against an employee, for engaging in certain 
protected activities, is prohibited. Discrimination includes discharge 
and other actions that relate to compensation, terms, conditions, or 
privileges of employment. The protected activities are established in 
section 211 of the Energy Reorganization

[[Page 252]]

Act of 1974, as amended, and in general are related to the 
administration or enforcement of a requirement imposed under the Atomic 
Energy Act or the Energy Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission, or his or her employer, information 
about alleged violations of either of the statutes named in paragraph 
(a) of this section or possible violations of requirements imposed under 
either of those aforementioned statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) of this section, or under these 
requirements, if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) of this 
section;
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section does not apply to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, an applicant for a Commission license, or a 
contractor or subcontractor of a Commission licensee or applicant may be 
grounds for--
    (1) Denial, revocation, or suspension of the license;
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant; or
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, that adversely affect 
an employee, may be predicated on nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee and each applicant for a license shall 
prominently post the revision of NRC Form 3, ``Notice to Employees,'' 
referenced in Sec. 19.11(c) of this chapter. This form must be posted 
at locations sufficient to permit employees protected by this section to 
observe a copy on the way to or from their place of work. Premises must 
be posted not later than 30 days after an application is docketed and 
remain posted while the application is pending before the Commission, 
during the term of the license, and for 30 days following license 
termination.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.

[[Page 253]]

    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision that would prohibit, restrict, or otherwise discourage an 
employee from participating in a protected activity as defined in 
paragraph (a)(1) of this section, including, but not limited to, 
providing information to NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003; 72 
FR 63974, Nov. 14, 2007; 73 FR 30459, May 28, 2008; 79 FR 66605, Nov. 
10, 2014]



Sec. 63.10  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
license or by a licensee, or information required by statute, or 
required by the Commission's regulations, orders, or license conditions 
to be maintained by the applicant or the licensee must be complete and 
accurate in all material respects.
    (b) The applicant or licensee shall notify the Commission of 
information identified by the applicant or licensee as having, for the 
regulated activity, a significant implication for public health and 
safety or common defense and security. An applicant or licensee violates 
this paragraph only if the applicant or licensee fails to notify the 
Commission of information that the applicant or licensee has identified 
as having a significant implication for public health and safety or 
common defense and security. Notification must be provided to the 
Director of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, within 2 working days of identifying the 
information. This requirement is not applicable to information that is 
already required to be provided to the Commission by other reporting or 
updating requirements.



Sec. 63.11  Deliberate misconduct.

    (a) Any licensee, applicant for a license, employee of a licensee or 
applicant; or any contractor (including a supplier or consultant), 
subcontractor, employee of a contractor or subcontractor of any licensee 
or applicant for a license, who knowingly provides to any licensee, 
applicant, contractor, or subcontractor, any components, equipment, 
materials, or other goods or services that relate to a licensee's or 
applicant's activities in this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee or applicant to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation of 
any license issued by the Commission; or
    (2) Deliberately submit to NRC, a licensee, an applicant, or a 
licensee's or applicant's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee or applicant to be in violation of any 
rule, regulation, or order; or any term, condition, or limitation, of 
any license issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
applicant, contractor, or subcontractor.



                           Subpart B_Licenses

                          Preapplication Review



Sec. 63.15  Site characterization.

    (a) DOE shall conduct a program of site characterization with 
respect to the Yucca Mountain site before it submits an application for 
a license to be issued under this part.

[[Page 254]]

    (b) DOE shall conduct the investigations to obtain the required 
information in a manner that limits adverse effects on the long-term 
performance of the geologic repository at Yucca Mountain to the extent 
practical.



Sec. 63.16  Review of site characterization activities. \2\
---------------------------------------------------------------------------

    \2\ In addition to the review of site characterization activities 
specified in this section, the Commission contemplates an ongoing review 
of other information on site investigation and site characterization, to 
allow early identification of potential licensing issues for timely 
resolution at the staff level.
---------------------------------------------------------------------------

    (a) If DOE's planned site characterization activities include onsite 
testing with radioactive material, including radioactive tracers, the 
Commission shall determine whether the proposed use of such radioactive 
material is necessary to provide data for the preparation of the 
environmental reports required by law and for an application to be 
submitted under Sec. 63.22.
    (b) During the conduct of site characterization activities at the 
Yucca Mountain site, DOE shall report the nature and extent of the 
activities, the information that has been developed, and the progress of 
waste form and waste package research and development to the Commission 
not less than once every 6 months. The semiannual reports must include 
the results of site characterization studies, the identification of new 
issues, plans for additional studies to resolve new issues, elimination 
of planned studies no longer necessary, identification of decision 
points reached, and modifications to schedules, where appropriate. DOE 
shall also report its progress in developing the design of a geologic 
repository operations area appropriate for the area being characterized, 
noting when key design parameters or features that depend on the results 
of site characterization will be established. Other topics related to 
site characterization must also be covered if requested by the Director.
    (c) During the conduct of site characterization activities at the 
Yucca Mountain site, NRC staff shall be permitted to visit and inspect 
the locations at which such activities are carried out and to observe 
excavations, borings, and in situ tests, as they are done.
    (d) The Director may comment at any time in writing to DOE, 
expressing current views on any aspect of site characterization or 
performance assessment at the Yucca Mountain site. In particular, the 
Director shall comment whenever he or she determines that there are 
substantial grounds for making recommendations or stating objections to 
DOE's site characterization program. The Director shall invite public 
comment on any comments that the Director makes to DOE on review of the 
DOE semiannual reports or on any other comments that the Director makes 
to DOE on site characterization and performance assessment by placing 
the comments in a public forum to allow the public to comment on them 
after the Director's comments are sent to DOE.
    (e) The Director shall transmit copies of all comments to DOE made 
by the Director under this section to the Governor and legislature of 
the State of Nevada and to the governing body of any affected Indian 
Tribe.
    (f) The NRC shall place all correspondence between DOE and NRC 
resulting from the requirements of this section, including the reports 
described in paragraph (b) of this section, in the Publicly Available 
Records System (PARS) Library.
    (g) The activities described in paragraphs (a) through (f) of this 
section constitute informal conference between a prospective applicant 
and the NRC staff, as described in Sec. 2.101(a)(1) of this chapter, 
and are not part of a proceeding under the Atomic Energy Act of 1954, as 
amended. Accordingly, the issuance of the Director's comments made under 
this section does not constitute a commitment to issue any authorization 
or license, or in any way affect the authority of the Commission, Atomic 
Safety and Licensing Board, other presiding officers, or the Director, 
in any such proceeding.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003]

[[Page 255]]

                           License Application



Sec. 63.21  Content of application.

    (a) An application consists of general information and a Safety 
Analysis Report. An environmental impact statement must be prepared in 
accordance with the Nuclear Waste Policy Act of 1982, as amended, and 
must accompany the application. Any Restricted Data or National Security 
Information must be separated from unclassified information. The 
application must be as complete as possible in the light of information 
that is reasonably available at the time of docketing.
    (b) The general information must include:
    (1) A general description of the proposed geologic repository at the 
Yucca Mountain site, identifying the location of the geologic repository 
operations area, the general character of the proposed activities, and 
the basis for the exercise of the Commission's licensing authority.
    (2) Proposed schedules for construction, receipt of waste, and 
emplacement of wastes at the proposed geologic repository operations 
area.
    (3) A description of the detailed security measures for physical 
protection of high-level radioactive waste in accordance with Sec. 
73.51 of this chapter. This plan must include the design for physical 
protection, the licensee's safeguards contingency plan, and security 
organization personnel training and qualification plan. The plan must 
list tests, inspections, audits, and other means to be used to 
demonstrate compliance with such requirements.
    (4) A description of the material control and accounting program to 
meet the requirements of Sec. 63.78.
    (5) A description of work conducted to characterize the Yucca 
Mountain site.
    (c) The Safety Analysis Report must include:
    (1) A description of the Yucca Mountain site, with appropriate 
attention to those features, events, and processes of the site that 
might affect design of the geologic repository operations area and 
performance of the geologic repository. The description of the site must 
include information regarding features, events, and processes outside of 
the site to the extent the information is relevant and material to 
safety or performance of the geologic repository. The information 
referred to in this paragraph must include:
    (i) The location of the geologic repository operations area with 
respect to the boundary of the site;
    (ii) Information regarding the geology, hydrology, and geochemistry 
of the site, including geomechanical properties and conditions of the 
host rock;
    (iii) Information regarding surface water hydrology, climatology, 
and meteorology of the site; and
    (iv) Information regarding the location of the reasonably maximally 
exposed individual, and regarding local human behaviors and 
characteristics, as needed to support selection of conceptual models and 
parameters used for the reference biosphere and reasonably maximally 
exposed individual.
    (2) Information relative to materials of construction of the 
geologic repository operations area (including geologic media, general 
arrangement, and approximate dimensions), and codes and standards that 
DOE proposes to apply to the design and construction of the geologic 
repository operations area.
    (3) A description and discussion of the design of the various 
components of the geologic repository operations area and the engineered 
barrier system including:
    (i) Dimensions, material properties, specifications, analytical and 
design methods used along with any applicable codes and standards;
    (ii) The design criteria used and their relationships to the 
preclosure and postclosure performance objectives specified at Sec. 
63.111(b), Sec. 63.113(b), and Sec. 63.113(c); and
    (iii) The design bases and their relation to the design criteria.
    (4) A description of the kind, amount, and specifications of the 
radioactive material proposed to be received and possessed at the 
geologic repository operations area at the Yucca Mountain site.
    (5) A preclosure safety analysis of the geologic repository 
operations area, for the period before permanent closure, to ensure 
compliance with Sec. 63.111(a), as required by Sec. 63.111(c). For the 
purposes

[[Page 256]]

of this analysis, it is assumed that operations at the geologic 
repository operations area will be carried out at the maximum capacity 
and rate of receipt of radioactive waste stated in the application.
    (6) A description of the program for control and monitoring of 
radioactive effluents and occupational radiological exposures to 
maintain such effluents and exposures in accordance with the 
requirements of Sec. 63.111.
    (7) A description of plans for retrieval and alternate storage of 
the radioactive wastes, should retrieval be necessary.
    (8) A description of design considerations that are intended to 
facilitate permanent closure and decontamination or decontamination and 
dismantlement of surface facilities.
    (9) An assessment to determine the degree to which those features, 
events, and processes of the site that are expected to materially affect 
compliance with Sec. 63.113--whether beneficial or potentially adverse 
to performance of the geologic repository--have been characterized, and 
the extent to which they affect waste isolation. Investigations must 
extend from the surface to a depth sufficient to determine principal 
pathways for radionuclide migration from the underground facility. 
Specific features, events, and processes of the geologic setting must be 
investigated outside of the site if they affect performance of the 
geologic repository.
    (10) An assessment of the anticipated response of the geomechanical, 
hydrogeologic, and geochemical systems to the range of design thermal 
loadings under consideration, given the pattern of fractures and other 
discontinuities and the heat transfer properties of the rock mass and 
water.
    (11) An assessment of the ability of the proposed geologic 
repository to limit radiological exposures to the reasonably maximally 
exposed individual for the period after permanent closure, as required 
by Sec. 63.113(b).
    (12) An assessment of the ability of the proposed geologic 
repository to limit releases of radionuclides into the accessible 
environment as required by Sec. 63.113(c).
    (13) An assessment of the ability of the proposed geologic 
repository to limit radiological exposures to the reasonably maximally 
exposed individual for the period after permanent closure in the event 
of human intrusion into the engineered barrier system as required by 
Sec. 63.113(d).
    (14) An evaluation of the natural features of the geologic setting 
and design features of the engineered barrier system that are considered 
barriers important to waste isolation as required by Sec. 63.115.
    (15) An explanation of measures used to support the models used to 
provide the information required in paragraphs (c)(9) through (c)(14) of 
this section. Analyses and models that will be used to assess 
performance of the geologic repository must be supported by using an 
appropriate combination of such methods as field tests, in situ tests, 
laboratory tests that are representative of field conditions, monitoring 
data, and natural analog studies.
    (16) An identification of those structures, systems, and components 
of the geologic repository, both surface and subsurface, that require 
research and development to confirm the adequacy of design. For 
structures, systems, and components important to safety and for the 
engineered and natural barriers important to waste isolation, DOE shall 
provide a detailed description of the programs designed to resolve 
safety questions, including a schedule indicating when these questions 
would be resolved.
    (17) A description of the performance confirmation program that 
meets the requirements of subpart F of this part.
    (18) An identification and justification for the selection of those 
variables, conditions, or other items that are determined to be probable 
subjects of license specifications. Special attention must be given to 
those items that may significantly influence the final design.
    (19) An explanation of how expert elicitation was used.
    (20) A description of the quality assurance program to be applied to 
the structures, systems, and components important to safety and to the 
engineered and natural barriers important to waste isolation. The 
description of the quality assurance program must

[[Page 257]]

include a discussion of how the applicable requirements of Sec. 63.142 
will be satisfied.
    (21) A description of the plan for responding to, and recovering 
from, radiological emergencies that may occur at any time before 
permanent closure and decontamination or decontamination and 
dismantlement of surface facilities, as required by Sec. 63.161.
    (22) The following information concerning activities at the geologic 
repository operations area:
    (i) The organizational structure of DOE as it pertains to 
construction and operation of the geologic repository operations area, 
including a description of any delegations of authority and assignments 
of responsibilities, whether in the form of regulations, administrative 
directives, contract provisions, or otherwise.
    (ii) Identification of key positions that are assigned 
responsibility for safety at and operation of the geologic repository 
operations area.
    (iii) Personnel qualifications and training requirements.
    (iv) Plans for startup activities and startup testing.
    (v) Plans for conduct of normal activities, including maintenance, 
surveillance, and periodic testing of structures, systems, and 
components of the geologic repository operations area.
    (vi) Plans for permanent closure and plans for the decontamination 
or decontamination and dismantlement of surface facilities.
    (vii) Plans for any uses of the geologic repository operations area 
at the Yucca Mountain site for purposes other than disposal of 
radioactive wastes, with an analysis of the effects, if any, that such 
uses may have on the operation of the structures, systems, and 
components important to safety and the engineered and natural barriers 
important to waste isolation.
    (23) A description of the program to be used to maintain the records 
described in Sec. Sec. 63.71 and 63.72.
    (24) A description of the controls that DOE will apply to restrict 
access and to regulate land use at the Yucca Mountain site and adjacent 
areas, including a conceptual design of monuments that would be used to 
identify the site after permanent closure.
    (d) The applicant for a license to receive and possess source, 
special nuclear, and byproduct material at a geologic repository at 
Yucca Mountain, Nevada, shall protect Safeguards Information in 
accordance with the requirements in Sec. 73.21, and the requirements in 
Sec. 73.22, or Sec. 73.23 of this chapter, as applicable, and shall 
protect classified information in accordance with the requirements of 
parts 25 and 95 of this chapter, as applicable.

[66 FR 55792, Nov. 2, 2001, as amended at 73 FR 63572, Oct. 24, 2008]



Sec. 63.22  Filing and distribution of application.

    (a) An application for a construction authorization for a high-level 
radioactive waste repository at a geologic repository operations area at 
Yucca Mountain, and an application for a license to receive and possess 
source, special nuclear, or byproduct material at a geologic repository 
operations area at the Yucca Mountain site that has been characterized, 
any amendments to the application, and an accompanying environmental 
impact statement and any supplements, must be signed by the Secretary of 
Energy or the Secretary's authorized representative and must be filed 
with the Director in triplicate on paper and optical storage media.
    (b) DOE shall submit 30 additional copies, on paper and optical 
storage media, of each portion of the application and any amendments, 
and each environmental impact statement and any supplements. DOE shall 
maintain the capability to generate additional copies for distribution 
in accordance with written instructions from the Director or the 
Director's designee.
    (c) On notification of the appointment of an Atomic Safety and 
Licensing Board, DOE shall update the application, eliminating all 
superseded information, and supplement the environmental impact 
statement if necessary, and serve the updated application and 
environmental impact statement (as it may have been supplemented) as 
directed by the Board. Any subsequent amendments to the application or 
supplements to the environmental impact statement must be served in the 
same manner.

[[Page 258]]

    (d) When an application, and any amendment to it is filed, copies on 
paper and optical storage media must be made available in appropriate 
locations near the proposed geologic repository operations areas at the 
Yucca Mountain site for inspection by the public. These copies must be 
updated as amendments to the application are made. The environmental 
impact statement and any supplements to it must be made available in the 
same manner. An updated copy of the application, and the environmental 
impact statement and supplements, must be produced at any public hearing 
held by the Commission on the application for use by any party to the 
proceeding.
    (e) DOE shall certify that the updated copies of the application, 
and the environmental impact statement as it may have been supplemented, 
as referred to in paragraphs (c) and (d) of this section, contain the 
current contents of these documents submitted as required by this part.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003; 69 
FR 2280, Jan. 14, 2004]



Sec. 63.23  Elimination of repetition.

    In its application or environmental impact statement, DOE may 
incorporate, by reference, information contained in previous 
applications, statements, or reports filed with the Commission, if the 
references are clear and specific and copies of the information 
incorporated are made available to the public locations near the site of 
the proposed geologic repository, as specified in Sec. 63.22(d).



Sec. 63.24  Updating of application and environmental impact statement.

    (a) The application must be as complete as possible in light of the 
information that is reasonably available at the time of docketing.
    (b) DOE shall update its application in a timely manner so as to 
permit the Commission to review, before issuance of a license--
    (1) Additional geologic, geophysical, geochemical, hydrologic, 
meteorologic, materials, design, and other data obtained during 
construction;
    (2) Conformance of construction of structures, systems, and 
components with the design;
    (3) Results of research programs carried out to confirm the adequacy 
of designs, conceptual models, parameter values, and estimates of 
performance of the geologic repository.
    (4) Other information bearing on the Commission's issuance of a 
license that was not available at the time a construction authorization 
was issued.
    (c) DOE shall supplement its environmental impact statement in a 
timely manner so as to take into account the environmental impacts of 
any substantial changes in its proposed actions or any significant new 
circumstances or information relevant to environmental concerns bearing 
on the proposed action or its impacts.

                       Construction Authorization



Sec. 63.31  Construction authorization.

    On review and consideration of an application and environmental 
impact statement submitted under this part, the Commission may authorize 
construction of a geologic repository operations area at the Yucca 
Mountain site if it determines:
    (a) Safety. (1) That there is reasonable assurance that the types 
and amounts of radioactive materials described in the application can be 
received and possessed in a geologic repository operations area of the 
design proposed without unreasonable risk to the health and safety of 
the public; and
    (2) That there is reasonable expectation that the materials can be 
disposed of without unreasonable risk to the health and safety of the 
public.
    (3) In arriving at these determinations, the Commission shall 
consider whether--
    (i) DOE has described the proposed geologic repository as specified 
at Sec. 63.21;
    (ii) The site and design comply with the performance objectives and 
requirements contained in subpart E of this part;
    (iii) DOE's quality assurance program complies with the requirements 
of subpart G of this part;

[[Page 259]]

    (iv) DOE's personnel training program complies with the criteria 
contained in subpart H of this part;
    (v) DOE's emergency plan complies with the criteria contained in 
subpart I of this part; and
    (vi) DOE's proposed operating procedures to protect health and to 
minimize danger to life or property are adequate.
    (b) Common defense and security. That there is reasonable assurance 
that the activities proposed in the application will not be inimical to 
the common defense and security.
    (c) Environmental. That, after weighing the environmental, economic, 
technical, and other benefits against environmental costs, and 
considering available alternatives, the action called for is the 
issuance of the construction authorization, with any appropriate 
conditions to protect environmental values.



Sec. 63.32  Conditions of construction authorization.

    (a) In a construction authorization for a geologic repository 
operations area at the Yucca Mountain site, the Commission shall include 
any conditions it considers necessary to protect the health and safety 
of the public, the common defense and security, or environmental values.
    (b) The Commission shall incorporate provisions in the construction 
authorization requiring DOE to furnish periodic or special reports 
regarding:
    (1) Progress of construction;
    (2) Any data about the site, obtained during construction, that are 
not within the predicted limits on which the facility design was based;
    (3) Any deficiencies, in design and construction, that, if 
uncorrected, could adversely affect safety at any future time; and
    (4) Results of research and development programs being conducted to 
resolve safety questions.
    (c) The construction authorization for a geologic repository 
operations area at the Yucca Mountain site will include restrictions on 
subsequent changes to the features of the geologic repository and the 
procedures authorized. The restrictions that may be imposed under this 
paragraph can include measures to prevent adverse effects on the 
geologic setting as well as measures related to the design and 
construction of the geologic repository operations area. These 
restrictions will fall into three categories of descending importance to 
public health and safety, as follows:
    (1) Those features and procedures that may not be changed without--
    (i) 60 days prior notice to the Commission;
    (ii) 30 days notice of opportunity for a prior hearing; and
    (iii) Prior Commission approval;
    (2) Those features and procedures that may not be changed without--
    (i) 60 days prior notice to the Commission; and
    (ii) Prior Commission approval; and
    (3) Those features and procedures that may not be changed without 60 
days notice to the Commission. Features and procedures falling in this 
paragraph section may not be changed without prior Commission approval 
if the Commission, after having received the required notice, so orders.
    (d) A construction authorization must be subject to the limitation 
that a license to receive and possess source, special nuclear, or 
byproduct material at the Yucca Mountain site geologic repository 
operations area may not be issued by the Commission until;
    (1) DOE has updated its application, as specified at Sec. 63.24; 
and
    (2) The Commission has made the findings stated in Sec. 63.41.



Sec. 63.33  Amendment of construction authorization.

    (a) An application for amendment of a construction authorization 
must be filed with the Commission that fully describes any desired 
changes and follows, as far as applicable, the content requirements 
prescribed in Sec. 63.21.
    (b) In determining whether an amendment of a construction 
authorization will be approved, the Commission will be guided by the 
considerations that govern the issuance of the initial construction 
authorization, to the extent applicable.

[[Page 260]]

                     License Issuance and Amendment



Sec. 63.41  Standards for issuance of a license.

    A license to receive and possess source, special nuclear, or 
byproduct material at a geologic repository operations area at the Yucca 
Mountain site may be issued by the Commission on finding that--
    (a) Construction of the geologic repository operations area has been 
substantially completed in conformity with the application as amended, 
the provisions of the Atomic Energy Act, and the rules and regulations 
of the Commission. Construction may be considered substantially complete 
for the purposes of this paragraph if the construction of--
    (1) Surface and interconnecting structures, systems, and components; 
and
    (2) Any underground storage space required for initial operation, 
are substantially complete.
    (b) The activities to be conducted at the geologic repository 
operations area will be in conformity with the application as amended, 
the provisions of the Atomic Energy Act and the Energy Reorganization 
Act, and the rules and regulations of the Commission.
    (c) The issuance of the license will not be inimical to the common 
defense and security and will not constitute an unreasonable risk to the 
health and safety of the public.
    (d) Adequate protective measures can and will be taken in the event 
of a radiological emergency at any time before permanent closure and 
decontamination or decontamination and dismantlement of surface 
facilities.
    (e) All applicable requirements of part 51 of this chapter have been 
satisfied.



Sec. 63.42  Conditions of license.

    (a) The Commission shall include any conditions, including license 
specifications, it considers necessary to protect the health and safety 
of the public, the common defense and security, and environmental values 
in a license issued under this part.
    (b) Whether stated in the license or not, the following are 
considered to be conditions in every license issued:
    (1) The license is subject to revocation, suspension, modification, 
or amendment for cause, as provided by the Atomic Energy Act and the 
Commission's regulations.
    (2) DOE shall, at any time while the license is in effect, on 
written request of the Commission, submit written statements to enable 
the Commission to determine whether or not the license should be 
modified, suspended, or revoked.
    (3) The license is subject to the provisions of the Atomic Energy 
Act now or hereafter in effect and to all rules, regulations, and orders 
of the Commission. The terms and conditions of the license are subject 
to amendment, revision, or modification, by reason of amendments to or 
by reason of rules, regulations, and orders issued in accordance with 
the terms of the Atomic Energy Act.
    (c) Each license includes the provisions set forth in section 183 b-
d, inclusive, of the Atomic Energy Act, whether or not these provisions 
are expressly set forth in the license.
    (d) A license issued under this part includes the provisions set 
forth in section 114(d) of the Nuclear Waste Policy Act, as amended, 
defining the quantity of solidified high-level radioactive waste and 
spent nuclear fuel, until such time as a second repository is in 
operation, whether or not these provisions are expressly set forth in 
the license.
    (e) The licensee (Department of Energy) shall ensure that Safeguards 
Information is protected against unauthorized disclosure in accordance 
with the requirements in Sec. 73.21, and the requirements in Sec. 
73.22, or Sec. 73.23 of this chapter, as applicable, and shall protect 
classified information in accordance with the requirements of parts 25 
and 95 of this chapter, as applicable.

[66 FR 55792, Nov. 2, 2001, as amended at 73 FR 63572, Oct. 24, 2008]



Sec. 63.43  License specification.

    (a) A license issued under this part includes license conditions 
derived from the analyses and evaluations included in the application, 
including amendments made before a license is issued, together with any 
additional

[[Page 261]]

conditions the Commission finds appropriate.
    (b) License conditions include items in the following categories:
    (1) Restrictions as to the physical and chemical form and 
radioisotopic content of radioactive waste.
    (2) Restrictions as to size, shape, and materials and methods of 
construction of radioactive waste packaging.
    (3) Restrictions as to the amount of waste permitted per unit volume 
of storage space, considering the physical characteristics of both the 
waste and the host rock.
    (4) Requirements relating to test, calibration, or inspection, to 
assure that the foregoing restrictions are observed.
    (5) Controls to be applied to restrict access and to avoid 
disturbance to the site and to areas outside the site where conditions 
may affect compliance with Sec. Sec. 63.111 and 63.113.
    (6) Administrative controls, which are the provisions relating to 
organization and management, procedures, recordkeeping, review and 
audit, and reporting necessary to assure that activities at the facility 
are conducted in a safe manner and in conformity with the other license 
specifications.



Sec. 63.44  Changes, tests, and experiments.

    (a) Definitions for the purposes of this section:
    (1) Change means a modification or addition to, or removal from, the 
geologic repository operations area design or procedures that affects a 
design function, event sequence, method of performing or controlling the 
function, or an evaluation that demonstrates that intended functions 
will be accomplished.
    (2) Departure from a method of evaluation described in the Safety 
Analysis Report (SAR) (as updated) used in establishing the preclosure 
safety analyses or performance assessment means:
    (i) Changing any of the elements of the method described in the SAR 
(as updated) unless the results of the analysis are conservative or 
essentially the same; or
    (ii) Changing from a method described in the SAR to another method 
unless that method has been approved by NRC for the intended 
application, addition or removal.
    (3) Safety Analysis Report (SAR) (as updated) means the Safety 
Analysis Report for the geologic repository, submitted in accordance 
with Sec. 63.21, as updated in accordance with Sec. 63.24.
    (4) Geologic repository operations area as described in the SAR (as 
updated) means:
    (i) The structures, systems, and components important to safety or 
barriers important to waste isolation that are described in the SAR (as 
updated); and
    (ii) The design and performance requirements for such structures, 
systems, and components described in the SAR (as updated).
    (5) Procedures as described in the SAR (as updated) means those 
procedures that contain information described in the SAR (as updated) 
such as how structures, systems, and components important to safety, or 
important to waste isolation, are operated or controlled.
    (6) Tests or experiments not described in the SAR (as updated) means 
any condition where the geologic repository operations area or any of 
its structures, systems, and components important to safety, or 
important to waste isolation, are utilized, controlled, or altered in a 
manner which is either:
    (i) Outside the reference bounds of the design bases as described in 
the SAR (as updated); or
    (ii) Inconsistent with the analyses or descriptions in the SAR (as 
updated).
    (b)(1) DOE may make changes in the geologic repository operations 
area as described in the SAR (as updated), make changes in the 
procedures as described in the SAR (as updated), and conduct tests or 
experiments not described in the SAR (as updated), without obtaining 
either an amendment of construction authorization under Sec. 63.33 or a 
license amendment under Sec. 63.45, if:
    (i) A change in the conditions incorporated in the construction 
authorization or license is not required; and
    (ii) The change, test, or experiment does not meet any of the 
criteria in paragraph (b)(2) of this section.
    (2) DOE shall obtain an amendment of construction authorization 
under Sec. 63.33 or a license amendment under

[[Page 262]]

Sec. 63.45, before implementing a change, test, or experiment if it 
would:
    (i) Result in more than a minimal increase in the frequency of 
occurrence of an event sequence previously evaluated in the SAR (as 
updated);
    (ii) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of structures, systems, components important 
to safety, or important to waste isolation, which were previously 
evaluated in the SAR (as updated);
    (iii) Result in more than a minimal increase in the consequences of 
an event sequence previously evaluated in the SAR (as updated);
    (iv) Result in more than a minimal increase in the consequences of 
malfunction of structures, systems, components important to safety, or 
important to waste isolation, which were previously evaluated in the SAR 
(as updated);
    (v) Create the possibility for an event sequence, or of a pathway 
for release of radionuclides, of a different type than any evaluated 
previously in the SAR (as updated);
    (vi) Create the possibility for a malfunction of structures, 
systems, and components important to safety, or important to waste 
isolation, with a different result than any evaluated previously in the 
SAR (as updated);
    (vii) Result in a departure from a method of evaluation described in 
the SAR (as updated) used in establishing the preclosure safety analysis 
or the performance assessment.
    (3) In implementing this paragraph, the SAR (as updated) is 
considered to include SAR changes resulting from evaluations performed 
pursuant to this section and from safety analyses performed under Sec. 
63.33 or Sec. 63.45, as applicable, after the last Safety Analysis 
Report was updated under Sec. 63.24.
    (4) The provisions in this section do not apply to changes to the 
geologic repository operations area or procedures when the applicable 
regulations establish more specific criteria for accomplishing such 
changes.
    (c)(1) DOE shall maintain records of changes in the geologic 
repository operations area at the Yucca Mountain site, of changes in 
procedures, and of tests and experiments made under paragraph (b) of 
this section. These records must include a written evaluation that 
provides the bases for the determination that the change, test, or 
experiment does not require an amendment of construction authorization 
or license amendment under paragraph (b) of this section.
    (2) No less frequently than every 24 months, DOE shall prepare a 
report containing a brief description of such changes, tests, and 
experiments, including a summary of the evaluation of each. These 
written reports must be sent to the NRC using an appropriate method 
listed in Sec. 63.4; addressed: ATTN: Document Control Desk; Director, 
Office of Nuclear Material Safety and Safeguards; U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-001; and DOE shall furnish 
the report to the appropriate NRC Regional Office shown in appendix D to 
part 20 of this chapter. Any report submitted under this paragraph must 
be made a part of the public record of the licensing proceedings.
    (d) Changes to the quality assurance program description required by 
Sec. 63.21(c)(20) must be processed in accordance with Sec. 63.144.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003]



Sec. 63.45  Amendment of license.

    (a) An application for amendment of a license may be filed with the 
Commission fully describing the changes desired and following as far as 
applicable the format prescribed for license applications.
    (b) In determining whether an amendment of a license will be 
approved, the Commission will be guided by the considerations that 
govern the issuance of the initial license, to the extent applicable.



Sec. 63.46  Particular activities requiring license amendment.

    (a) Unless expressly authorized in the license, a license amendment 
is required for any of the following activities:
    (1) Any action that would make emplaced high-level radioactive waste 
irretrievable or that would substantially increase the difficulty of 
retrieving the emplaced waste;

[[Page 263]]

    (2) Dismantling of structures;
    (3) Removal or reduction of controls applied to restrict access to 
or avoid disturbance of the site and to areas outside the site where 
conditions may affect compliance with Sec. Sec. 63.111 and 63.113;
    (4) Destruction or disposal of records required to be maintained 
under the provisions of this part;
    (5) Any substantial change to the design or operating procedures 
from that specified in the license, except as authorized in Sec. 63.44; 
and
    (6) Permanent closure.
    (b) An application for an amendment must be filed, and will be 
reviewed, as specified in Sec. 63.45.

                      US/IAEA Safeguards Agreement



Sec. 63.47  Facility information and verification.

    (a) In response to a written request by the Commission, each 
applicant for a construction authorization or license and each recipient 
of a construction authorization or a license shall submit facility 
information, as described in Sec. 75.10 of this chapter, on Form N-71 
and associated forms and site information on DOC/NRC Form AP-A and 
associated forms;
    (b) As required by the Additional Protocol, applicants and licensees 
specified in paragraph (a) of this section shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms;
    (c) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA) and take other action as necessary to implement the 
US/IAEA Safeguards Agreement, as described in Part 75 of this chapter.

[73 FR 78606, Dec. 23, 2008]

                            Permanent Closure



Sec. 63.51  License amendment for permanent closure.

    (a) DOE shall submit an application to amend the license before 
permanent closure of a geologic repository at the Yucca Mountain site. 
The submission must consist of an update of the license application 
submitted under Sec. Sec. 63.21 and 63.22, including:
    (1) An update of the assessment of the performance of the geologic 
repository for the period after permanent closure. The updated 
assessment must include any performance confirmation data collected 
under the program required by subpart F, and pertinent to compliance 
with Sec. 63.113.
    (2) A description of the program for post-permanent closure 
monitoring of the geologic repository.
    (3) A detailed description of the measures to be employed--such as 
land use controls, construction of monuments, and preservation of 
records--to regulate or prevent activities that could impair the long-
term isolation of emplaced waste within the geologic repository and to 
assure that relevant information will be preserved for the use of future 
generations. As a minimum, these measures must include:
    (i) Identification of the site and geologic repository operations 
area by monuments that have been designed, fabricated, and emplaced to 
be as permanent as is practicable;
    (ii) Placement of records in the archives and land record systems of 
local, State, and Federal government agencies, and archives elsewhere in 
the world, that would be likely to be consulted by potential human 
intruders--such records to identify the location of the geologic 
repository operations area, including the underground facility, 
boreholes, shafts and ramps, and the boundaries of the site, and the 
nature and hazard of the waste; and
    (iii) A program for continued oversight, to prevent any activity at 
the site that poses an unreasonable risk of breaching the geologic 
repository's engineered barriers; or increasing the exposure of 
individual members of the public to radiation beyond allowable limits.
    (4) Geologic, geophysical, geochemical, hydrologic, and other site 
data that are obtained during the operational period, pertinent to 
compliance with Sec. 63.113.
    (5) The results of tests, experiments, and any other analyses 
relating to backfill of excavated areas, shaft, borehole, or ramp 
sealing, drip shields, waste packages, interactions between natural and 
engineered systems, and

[[Page 264]]

any other tests, experiments, or analyses pertinent to compliance with 
Sec. 63.113.
    (6) Any substantial revision of plans for permanent closure.
    (7) Other information bearing on permanent closure that was not 
available at the time a license was issued.
    (b) If necessary, to take into account the environmental impact of 
any substantial changes in the permanent closure activities proposed to 
be carried out or any significant new information regarding the 
environmental impacts of permanent closure, DOE shall also supplement 
its environmental impact statement and submit this statement, as 
supplemented, with the application for license amendment.



Sec. 63.52  Termination of license.

    (a) Following permanent closure and the decontamination or 
decontamination and dismantlement of surface facilities at the Yucca 
Mountain site, DOE may apply for an amendment to terminate the license.
    (b) The application must be filed and will be reviewed in accordance 
with the provisions of Sec. 63.45 and this section.
    (c) A license may be terminated only when the Commission finds with 
respect to the geologic repository:
    (1) That the final disposition of radioactive wastes has been made 
in conformance with DOE's plan, as amended and approved as part of the 
license.
    (2) That the final state of the geologic repository operations area 
conforms to DOE's plans for permanent closure and DOE's plans for the 
decontamination or decontamination and dismantlement of surface 
facilities, as amended and approved as part of the license.
    (3) That the termination of the license is authorized by law, 
including sections 57, 62, and 81 of the Atomic Energy Act, as amended.



  Subpart C_Participation by State Government, Affected Units of Local 
                 Government, and Affected Indian Tribes



Sec. 63.61  Provision of information.

    (a) The Director shall provide the Governor and the Nevada State 
legislature, affected units of local government, and the governing body 
of any affected Indian Tribe, with timely and complete information 
regarding determinations or plans made by the Commission with respect to 
the Yucca Mountain site. Information must be provided concerning the 
site characterization, siting, development, design, licensing, 
construction, operation, regulation, permanent closure, or 
decontamination and dismantlement of surface facilities of the geologic 
repository operations area at the site.
    (b) Notwithstanding paragraph (a) of this section, the Director is 
not required to distribute any document to any entity if, with respect 
to the document, that entity or its counsel is included on a service 
list prepared under part 2 of this chapter.
    (c) The NRC shall place communications by the Director under this 
section in the Publicly Available Records System (PARS) Library and 
furnish copies to DOE.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003]



Sec. 63.62  Site review.

    (a) The Director shall make the NRC staff available to consult with 
representatives of the State of Nevada, affected units of local 
government, and affected Indian Tribes regarding the status of site 
characterization at the Yucca Mountain site.
    (b) Requests for consultation must be made in writing to the 
Director.
    (c) Consultation under this section may include:
    (1) Keeping the parties informed of the Director's views on the 
progress of site characterization.
    (2) Review of applicable NRC regulations, licensing procedures, 
schedules, and opportunities for State, affected units of local 
government, and Tribe participation in the Commission's regulatory 
activities.
    (3) Cooperation in development of proposals for State, affected 
units of local government, and Tribal participation in license reviews.



Sec. 63.63  Participation in license reviews.

    (a) The State, affected units of local government, and affected 
Indian Tribes

[[Page 265]]

may participate in license reviews as provided in subpart J of part 2 of 
this chapter.
    (b) In addition, a State, or an affected unit of local government, 
or an affected Indian Tribe may submit a proposal to the Director to 
facilitate its participation in the review of the license application. 
The proposal may be submitted at any time and must contain a description 
and schedule of how the State, or affected unit of local government, or 
affected Indian Tribe wishes to participate in the review, or what 
services or activities the State, or affected unit of local government, 
or affected Indian Tribe wishes the NRC to carry out, and how the 
services or activities proposed to be carried out by the NRC would 
contribute to this participation. The proposal may include educational 
or information services (seminars, public meetings) or other actions on 
the part of NRC, such as establishing additional public document rooms 
or employment or exchange of State personnel under the Intergovernmental 
Personnel Act.
    (c) The Director shall arrange for a meeting between the 
representatives of the State, or affected unit of local government, or 
affected Indian Tribe and the NRC staff, to discuss any proposal 
submitted under paragraph (b) of this section, with a view to 
identifying any modifications that may contribute to the effective 
participation by such State, or affected unit of local government, or 
Tribe.
    (d) Subject to the availability of funds, the Director shall approve 
all or any part of a proposal, as it may be modified through the meeting 
described in paragraph (c) of this section, if it is determined that:
    (1) The proposed activities are suitable in light of the type and 
magnitude of impacts that the State, or affected unit of local 
government, or affected Indian Tribe may bear;
    (2) The proposed activities--
    (i) Will enhance communications between NRC and the State, or 
affected unit of local government, or affected Indian Tribe;
    (ii) Will make a productive and timely contribution to the review; 
and
    (iii) Are authorized by law.
    (e) The Director shall advise the State, or affected unit of local 
government, or affected Indian Tribe whether its proposal has been 
accepted or denied. If all or any part of a proposal is denied, the 
Director shall state the reason for the denial.
    (f) The NRC shall place all proposals submitted under this section, 
and responses to them, in the Publicly Available Records System (PARS) 
Library.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58816, Oct. 10, 2003]



Sec. 63.64  Notice to State.

    If the Governor and legislature of the State of Nevada have jointly 
designated, on their behalf, a single person or entity to receive notice 
and information from the Commission under this part, the Commission will 
provide the notice and information to the jointly designated person or 
entity instead of the Governor and legislature separately.



Sec. 63.65  Representation.

    Any person who acts under this subpart as a representative for the 
State of Nevada (or for the Governor or legislature of Nevada), for an 
affected unit of local government, or for an affected Indian Tribe shall 
include in the request or other submission, or at the request of the 
Commission, a statement of the basis of his or her authority to act in 
this capacity.



           Subpart D_Records, Reports, Tests, and Inspections



Sec. 63.71  Records and reports.

    (a) DOE shall maintain records and make reports in connection with 
the licensed activity that are required by the conditions of the license 
or by rules, regulations, and orders of the Commission, as authorized by 
the Atomic Energy Act and the Energy Reorganization Act.
    (b) Records of the receipt, handling, and disposition of radioactive 
waste at a geologic repository operations area at the Yucca Mountain 
site must contain sufficient information to provide a complete history 
of the movement of the waste from the shipper through all phases of 
storage and disposal. DOE

[[Page 266]]

shall retain these records in a manner that ensures their usability for 
future generations in accordance with Sec. 63.51(a)(3).



Sec. 63.72  Construction records.

    (a) DOE shall maintain records of construction of the geologic 
repository operations area at the Yucca Mountain site in a manner that 
ensures their usability for future generations in accordance with Sec. 
63.51(a)(3).
    (b) The records required under paragraph (a) of this section must 
include at least the following--
    (1) Surveys of the underground facility excavations, shafts, ramps, 
and boreholes referenced to readily identifiable surface features or 
monuments;
    (2) A description of the materials encountered;
    (3) Geologic maps and geologic cross-sections;
    (4) Locations and amount of seepage;
    (5) Details of equipment, methods, progress, and sequence of work;
    (6) Construction problems;
    (7) Anomalous conditions encountered;
    (8) Instrument locations, readings, and analysis;
    (9) Location and description of structural support systems;
    (10) Location and description of dewatering systems;
    (11) Details, methods of emplacement, and location of seals used; 
and
    (12) Facility design records (e.g, design specifications and ``as 
built'' drawings).



Sec. 63.73  Reports of deficiencies.

    (a) DOE shall promptly notify the Commission of each deficiency 
found in the characteristics of the Yucca Mountain site, and design, and 
construction of the geologic repository operations area that, were it to 
remain uncorrected, could--
    (1) Adversely affect safety at any future time;
    (2) Represent a significant deviation from the design criteria and 
design basis stated in the design application; or
    (3) Represent a deviation from the conditions stated in the terms of 
a construction authorization or the license, including license 
specifications.
    (b) DOE shall implement a program for evaluating and reporting 
deviations and failures to comply, to identify defects and failures to 
comply associated with substantial safety hazards, based on the 
applicable requirements in 10 CFR 50.55(e) as it applies to the 
construction authorization and design of the geologic repository 
operations area at the Yucca Mountain site.
    (c) DOE shall implement a program of reporting specific events and 
conditions that is the same as that specified in 10 CFR 72.75.
    (d) The requisite notification must be as specified in the 
applicable regulation. By an appropriate method listed in Sec. 63.4 of 
this chapter, written reports must be submitted to NRC addressed: ATTN: 
Document Control Desk; Director, Office of Nuclear Material Safety and 
Safeguards; U.S. Nuclear Regulatory Commission, Washington, DC 20555-
001; and to the NRC onsite representative. DOE shall also furnish the 
report to the appropriate NRC Regional Office shown in appendix D to 
part 20 of this chapter.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58815, Oct. 10, 2003]



Sec. 63.74  Tests.

    (a) DOE shall perform, or permit the Commission to perform, those 
tests the Commission considers appropriate or necessary for the 
administration of the regulations in this part. This may include tests 
of--
    (1) Radioactive waste,
    (2) The geologic repository, including portions of the geologic 
setting and the structures, systems, and components constructed or 
placed therein,
    (3) Radiation detection and monitoring instruments, and
    (4) Other equipment and devices used in connection with the receipt, 
handling, or storage of radioactive waste.
    (b) The tests required under this section must include a performance 
confirmation program carried out in accordance with subpart F of this 
part.



Sec. 63.75  Inspections.

    (a) DOE shall allow the Commission to inspect the premises of the 
geologic repository operations area at the Yucca Mountain site and 
adjacent

[[Page 267]]

areas to which DOE has rights of access.
    (b) DOE shall make available to the Commission for inspection, on 
reasonable notice, records kept by DOE pertaining to activities under 
this part.
    (c)(1) DOE shall, on requests by the Director, Office of Nuclear 
Material Safety and Safeguards, provide rent-free office space for the 
exclusive use of the Commission inspection personnel. Heat, air-
conditioning, light, electrical outlets, and janitorial services must be 
furnished by DOE. The office must be convenient to and have full access 
to the facility and must provide the inspector both visual and acoustic 
privacy.
    (2) The space provided must be adequate to accommodate two full-time 
inspectors, and other transient NRC personnel and will be generally 
commensurate with other office facilities at the Yucca Mountain site 
geologic repository operations area. A space of 250 square feet either 
within the geologic repository operations area's office complex or in an 
office trailer or other onsite space at the geologic repository 
operations area is suggested as a guide. For locations at which 
activities are carried out under licenses issued under other parts of 
this chapter, additional space may be requested to accommodate 
additional full-time inspectors. The office space provided is subject to 
the approval of the Director, Office of Nuclear Material Safety and 
Safeguards. All furniture, supplies, and communication equipment will be 
furnished by the Commission.
    (3) DOE shall afford any NRC resident inspector assigned to the 
Yucca Mountain site or other NRC inspectors identified by the Regional 
Administrator as likely to inspect the Yucca Mountain facility, 
immediate unfettered access, equivalent to access provided regular 
employees, after proper identification and compliance with applicable 
access control measures for security, radiological protection, and 
personal safety.



Sec. 63.78  Material control and accounting records and reports.

    DOE shall implement a program of material control and accounting 
(and accidental criticality reporting) that is the same as that 
specified in Sec. Sec. 72.72, 72.74, 72.76, and 72.78 of this chapter.



                      Subpart E_Technical Criteria



Sec. 63.101  Purpose and nature of findings.

    (a)(1) Subpart B prescribes the standards for issuance of a license 
to receive and possess source, special nuclear, or byproduct material at 
a geologic repository operations area at the Yucca Mountain site. In 
particular, Sec. 63.41(c) requires a finding that the issuance of a 
license will not constitute an unreasonable risk to the health and 
safety of the public. The purpose of this subpart is to set out the 
performance objectives for postclosure performance of the geologic 
repository and other criteria that, if satisfied, support a finding of 
no unreasonable risk. Postclosure performance objectives for the 
geologic repository include a requirement to limit radiological 
exposures to the reasonably maximally exposed individual, a requirement 
to limit releases of radionuclides to the accessible environment to 
protect groundwater, and a requirement to limit radiological exposures 
to the reasonably maximally exposed individual in the event of human 
intrusion (see Sec. 63.113(b), (c), and (d), respectively).
    (2) Although the postclosure performance objectives specified at 
Sec. 63.113 are generally stated in unqualified terms, it is not 
expected that complete assurance that the requirements will be met can 
be presented. A reasonable expectation, on the basis of the record 
before the Commission, that the postclosure performance objectives will 
be met, is the general standard required. Proof that the geologic 
repository will conform with the objectives for postclosure performance 
is not to be had in the ordinary sense of the word because of the 
uncertainties inherent in the understanding of the evolution of the 
geologic setting, biosphere, and engineered barrier system. For such 
long-term performance, what is required is reasonable expectation, 
making allowance for the time period, hazards, and uncertainties 
involved, that the outcome will conform with the objectives for 
postclosure performance

[[Page 268]]

for the geologic repository. Demonstrating compliance will involve the 
use of complex predictive models that are supported by limited data from 
field and laboratory tests, site-specific monitoring, and natural analog 
studies that may be supplemented with prevalent expert judgment. 
Compliance demonstrations should not exclude important parameters from 
assessments and analyses simply because they are difficult to precisely 
quantify to a high degree of confidence. The performance assessments and 
analyses should focus upon the full range of defensible and reasonable 
parameter distributions rather than only upon extreme physical 
situations and parameter values. Further, in reaching a determination of 
reasonable expectation, the Commission may supplement numerical analyses 
with qualitative judgments including, for example, consideration of the 
degree of diversity among the multiple barriers as a measure of the 
resiliency of the geologic repository.
    (b) Subpart B lists findings that must be made in support of an 
authorization to construct a geologic repository operations area at the 
Yucca Mountain site. Prior to closure, Sec. 63.31(a)(1) requires a 
finding that there is reasonable assurance that the types and amounts of 
radioactive materials described in the application can be received, 
possessed, and stored in a geologic repository operations area of the 
design proposed without unreasonable risk to the health and safety of 
the public. After permanent closure, Sec. 63.31(a)(2) requires the 
Commission to consider whether there is a reasonable expectation the 
site and design comply with the postclosure performance objectives. Once 
again, although the criteria may be written in unqualified terms, the 
demonstration of compliance must take uncertainties and gaps in 
knowledge into account so that the Commission can make the specified 
finding with respect to paragraph (a)(2) of Sec. 63.31.



Sec. 63.102  Concepts.

    This section provides a functional overview of this Subpart E. In 
the event of any inconsistency, the definitions in Sec. 63.2 prevail.
    (a) The HLW facility at the Yucca Mountain site. NRC exercises 
licensing and related regulatory authority over those facilities 
described in section 202 (3) and (4) of the Energy Reorganization Act of 
1974, including the site at Yucca Mountain, as designated by the Energy 
Policy Act of 1992.
    (b) The geologic repository operations area. (1) These regulations 
deal with the exercise of authority with respect to a particular class 
of HLW facility--namely, a geologic repository operations area at Yucca 
Mountain.
    (2) A geologic repository operations area consists of those surface 
and subsurface areas of the site that are part of a geologic repository 
where radioactive waste handling activities are conducted. The 
underground structure, backfill materials, if any, and openings that 
penetrate the underground structure (e.g., ramps, shafts and boreholes, 
including their seals), are designated the underground facility.
    (3) The exercise of Commission authority requires that the geologic 
repository operations area be used for storage (which includes disposal) 
of high-level radioactive wastes (HLW).
    (4) HLW includes irradiated reactor fuel as well as reprocessing 
wastes. However, if DOE proposes to use the geologic repository 
operations area for storage of radioactive waste other than HLW, the 
storage of this radioactive waste is subject to the requirements of this 
part.
    (c) Stages in the licensing process. There are several stages in the 
licensing process. The site characterization stage, when the performance 
confirmation program is started, begins before submission of a license 
application, and may result in consequences requiring evaluation in the 
license review. The construction stage would follow after the issuance 
of a construction authorization. A period of operations follows the 
Commission's issuance of a license. The period of operations includes 
the time during which emplacement of wastes occurs; any subsequent 
period before permanent closure during which the emplaced wastes are 
retrievable; and permanent closure, which includes sealing openings to 
the repository. Permanent closure represents the end of the performance 
confirmation

[[Page 269]]

program; final backfilling of the underground facility, if appropriate; 
and the sealing of shafts, ramps, and boreholes.
    (d) Areas related to isolation. Although the activities subject to 
regulation under this part are those to be carried out at the geologic 
repository operations area, the licensing process also considers 
characteristics of adjacent areas that are defined in other ways. There 
must be an area surrounding the geologic repository operations area, 
that could include either a portion or all of the site, within which DOE 
shall exercise specified controls to prevent adverse human actions after 
permanent closure. There is an area, designated the geologic setting, 
which includes the geologic, hydrologic, and geochemical systems of the 
region in which the site and geologic repository operations area are 
located. The geologic repository operations area, plus the portion of 
the geologic setting that provides isolation of the radioactive waste, 
make up the geologic repository.
    (e) Performance objectives through permanent closure. Before 
permanent closure, the geologic repository operations area is required 
to limit radiation levels and radiological exposures, in both restricted 
and unrestricted areas, and releases of radioactive materials to 
unrestricted areas, as specified at Sec. 63.111(a).
    (f) Preclosure safety analysis. Section 63.111 includes performance 
objectives for the geologic repository operations area for the period 
before permanent closure and decontamination or permanent closure, 
decontamination, and dismantlement of surface facilities. The preclosure 
safety analysis is a systematic examination of the site; the design; and 
the potential hazards, initiating events and their resulting event 
sequences and potential radiological exposures to workers and the 
public. Initiating events are to be considered for inclusion in the 
preclosure safety analysis for determining event sequences only if they 
are reasonable (i.e., based on the characteristics of the geologic 
setting and the human environment, and consistent with precedents 
adopted for nuclear facilities with comparable or higher risks to 
workers and the public). The analysis identifies structures, systems, 
and components important to safety.
    (g) Performance objectives after permanent closure. After permanent 
closure, the geologic repository is required to:
    (1) Limit radiological exposures to the reasonably maximally exposed 
individual, as specified at Sec. 63.113(b);
    (2) Limit releases of radionuclides to the accessible environment to 
protect groundwater, as specified at Sec. 63.113(c); and
    (3) Limit radiological exposures to the reasonably maximally exposed 
individual in the event of human intrusion, as specified at Sec. 
63.113(d).
    (h) Multiple barriers. Section 63.113(a) requires that the geologic 
repository include multiple barriers, both natural and engineered. 
Geologic disposal of HLW is predicated on the expectation that one or 
more aspects of the geologic setting will be capable of contributing to 
the isolation of radioactive waste and thus be a barrier important to 
waste isolation. Although there is an extensive geologic record ranging 
from thousands to millions of years, this record is subject to 
interpretation and includes many uncertainties. In addition, there are 
uncertainties in the isolation capability and performance of engineered 
barriers. Although the composition and configuration of engineered 
structures (barriers) can be defined with a degree of precision not 
possible for natural barriers, it is recognized that except for a few 
archaeologic and natural analogs, there is a limited experience base for 
the performance of complex, engineered structures over periods longer 
than a few hundred years, considering the uncertainty in characterizing 
and modeling individual barriers. These uncertainties are addressed by 
requiring the use of a multiple barrier approach; specifically, an 
engineered barrier system is required in addition to the natural 
barriers provided by the geologic setting. The performance assessment 
provides an evaluation of the repository performance based on credible 
models and parameters including the consideration of uncertainty in the 
behavior of the repository system. Thus

[[Page 270]]

the performance assessment results reflect the capability of each of the 
barriers to cope with a variety of challenges (e.g., combinations of 
parameters leading to less favorable performance for individual barriers 
and combinations of barriers). A description of each barrier's 
capability (e.g., retardation of radionuclides in the saturated zone, 
waste package lifetime, matrix diffusion in the unsaturated zone), as 
reflected in the performance assessment, provides an understanding of 
how the natural barriers and the engineered barrier system work in 
combination to enhance the resiliency of the geologic repository. The 
Commission believes that this understanding can increase confidence that 
the postclosure performance objectives specified at Sec. 63.113(b) and 
(c) will be achieved and that DOE's design includes a system of multiple 
barriers.
    (i) Reference biosphere and reasonably maximally exposed individual. 
The performance assessment will estimate the amount of radioactive 
material released to water or air at various locations and times in the 
future. To estimate the potential for future human exposures resulting 
from release of radioactive material from a geologic repository at Yucca 
Mountain, it is necessary to make certain assumptions about the location 
and characteristics of the reasonably maximally exposed individual. The 
environment inhabited by the reasonably maximally exposed individual, 
along with associated human exposure pathways and parameters, make up 
the reference biosphere, as described in Sec. 63.305. The reasonably 
maximally exposed individual, as a hypothetical person living in a 
community with characteristics of the Town of Amargosa Valley, is a 
representative person using water with average concentrations of 
radionuclides as described at Sec. 63.312. The reasonably maximally 
exposed individual is selected to represent those persons in the 
vicinity of Yucca Mountain who are reasonably expected to receive the 
greatest exposure to radioactive material released from a geologic 
repository at Yucca Mountain. Characteristics of the reference biosphere 
and the reasonably maximally exposed individual are to be based on 
current human behavior and biospheric conditions in the region, as 
described in Sec. 63.305 and Sec. 63.312.
    (j) Performance assessment. Demonstrating compliance with the 
postclosure performance objective specified at Sec. 63.113(b) requires 
a performance assessment to quantitatively estimate radiological 
exposures to the reasonably maximally exposed individual at any time 
during the compliance period. The performance assessment is a systematic 
analysis that identifies the features, events, and processes (i.e., 
specific conditions or attributes of the geologic setting, degradation, 
deterioration, or alteration processes of engineered barriers, and 
interactions between the natural and engineered barriers) that might 
affect performance of the geologic repository; examines their effects on 
performance; and estimates the radiological exposures to the reasonably 
maximally exposed individual. The features, events, and processes 
considered in the performance assessment should represent a wide range 
of both beneficial and potentially adverse effects on performance (e.g., 
beneficial effects of radionuclide sorption; potentially adverse effects 
of fracture flow or a criticality event). Those features, events, and 
processes expected to materially affect compliance with Sec. 63.113(b) 
or be potentially adverse to performance are included, while events 
(event classes or scenario classes) that are very unlikely (less than 
one chance in 10,000 over 10,000 years) can be excluded from the 
analysis. An event class consists of all possible specific initiating 
events that are caused by a common natural process (e.g., the event 
class for seismicity includes the range of credible earthquakes for the 
Yucca Mountain site). Radiological exposures to the reasonably maximally 
exposed individual are estimated using the selected features, events, 
and processes, and incorporating the probability that the estimated 
exposures will occur. Additionally, performance assessment methods are 
appropriate for use in demonstrating compliance with the postclosure 
performance objectives for groundwater protection and human intrusion, 
and are subject to the requirements for performance assessments

[[Page 271]]

specified at Sec. 63.114 and applicable criteria in Subpart L (e.g., 
criteria for evaluating compliance with groundwater protection and 
individual protection standards).
    (k) Institutional controls. Active and passive institutional 
controls will be maintained over the Yucca Mountain site, and are 
expected to reduce significantly, but not eliminate, the potential for 
human activity that could inadvertently cause or accelerate the release 
of radioactive material. However, because it is not possible to make 
scientifically sound forecasts of the long-term reliability of 
institutional controls, it is not appropriate to include consideration 
of human intrusion into a fully risk-based performance assessment for 
purposes of evaluating the ability of the geologic repository to achieve 
the performance objective at Sec. 63.113(b). Hence, human intrusion is 
addressed in a stylized manner as described in paragraph (l) of this 
section.
    (l) Human intrusion. In contrast to events unrelated to human 
activity, the probability and characteristics of human intrusion 
occurring many hundreds or thousands of years into the future cannot be 
estimated by examining either the historic or geologic record. Rather 
than speculating on the nature and probability of future intrusion, it 
is more useful to assess how resilient the geologic repository would be 
against a human intrusion event. Although the consequences of an assumed 
intrusion event would be a separate analysis, the analysis is similar to 
the performance assessment required by Sec. 63.113(b) but subject to 
specific requirements for evaluation of human intrusion specified at 
Sec. Sec. 63.321, 63.322 and 63.342 of subpart L of this part.
    (m) Performance confirmation. A performance confirmation program 
will be conducted to evaluate the adequacy of assumptions, data, and 
analyses that led to the findings that permitted construction of the 
repository and subsequent emplacement of the wastes. Key geotechnical 
and design parameters, including any interactions between natural and 
engineered systems and components, will be monitored throughout site 
characterization, construction, emplacement, and operation to identify 
any significant changes in the conditions assumed in the license 
application that may affect compliance with the performance objectives 
specified at Sec. 63.113(b) and (c).
    (n) Groundwater protection. Separate groundwater protection 
standards are designed to protect the groundwater resources in the 
vicinity of Yucca Mountain. These standards, specified at Sec. 63.331, 
require the estimation of groundwater concentrations in the 
representative volume of water. Depending on the radionuclide, the 
estimated concentrations must either be below a specified concentration 
or result in an annual, drinking water dose to the whole body or any 
organ of no greater than 0.04 mSv (4 mrem). Although the estimation of 
radionuclide concentrations in the representative volume would be a 
separate analysis, the analysis is similar to the performance assessment 
required by Sec. 63.113(b) but subject to specific requirements for 
evaluation of groundwater protection specified at Sec. Sec. 63.331, 
63.332 and 63.342 of subpart L of this part.
    (o) Implementation of TEDE. When external exposure is determined by 
measurement with an external personal monitoring device, the deep-dose 
equivalent must be used in place of the effective dose equivalent, 
unless the effective dose equivalent is determined by a dosimetry method 
approved by the NRC. The assigned deep-dose equivalent must be for the 
part of the body receiving the highest exposure. The assigned shallow-
dose equivalent must be the dose averaged over the contiguous 10 square 
centimeters of skin receiving the highest exposure. The radiation and 
organ or tissue weighting factors in Appendix A of 40 CFR part 197 are 
to be used to calculate TEDE. After the effective date of this 
regulation, the Commission may allow DOE to use updated factors, which 
have been issued by consensus scientific organizations and incorporated 
by EPA into Federal radiation guidance. Additionally, as scientific 
models and methodologies for estimating doses are updated, DOE may use 
the most current and appropriate (e.g., those accepted by the 
International Commission on Radiological Protection) scientific models 
and methodologies to calculate the TEDE. The weighting factors used in

[[Page 272]]

the calculation of TEDE must be consistent with the methodology used to 
perform the calculation.

[66 FR 55792, Nov. 2, 2001, as amended at 74 FR 10828, Mar. 13, 2009]

                    Preclosure Performance Objectives



Sec. 63.111  Performance objectives for the geologic repository
operations area through permanent closure.

    (a) Protection against radiation exposures and releases of 
radioactive material. (1) The geologic repository operations area must 
meet the requirements of part 20 of this chapter.
    (2) During normal operations, and for Category 1 event sequences, 
the annual TEDE (hereafter referred to as ``dose'') to any real member 
of the public located beyond the boundary of the site may not exceed the 
preclosure standard specified at Sec. 63.204.
    (b) Numerical guides for design objectives. (1) The geologic 
repository operations area must be designed so that, taking into 
consideration Category 1 event sequences and until permanent closure has 
been completed, the aggregate radiation exposures and the aggregate 
radiation levels in both restricted and unrestricted areas, and the 
aggregate releases of radioactive materials to unrestricted areas, will 
be maintained within the limits specified in paragraph (a) of this 
section.
    (2) The geologic repository operations area must be designed so 
that, taking into consideration any single Category 2 event sequence and 
until permanent closure has been completed, no individual located on, or 
beyond, any point on the boundary of the site will receive, as a result 
of the single Category 2 event sequence, the more limiting of a TEDE of 
0.05 Sv (5 rem), or the sum of the deep dose equivalent and the 
committed dose equivalent to any individual organ or tissue (other than 
the lens of the eye) of 0.5 Sv (50 rem). The lens dose equivalent may 
not exceed 0.15 Sv (15 rem), and the shallow dose equivalent to skin may 
not exceed 0.5 Sv (50 rem).
    (c) Preclosure safety analysis. A preclosure safety analysis of the 
geologic repository operations area that meets the requirements 
specified at Sec. 63.112 must be performed. This analysis must 
demonstrate that:
    (1) The requirements of Sec. 63.111(a) will be met; and
    (2) The design meets the requirements of Sec. 63.111(b).
    (d) Performance confirmation. The geologic repository operations 
area must be designed so as to permit implementation of a performance 
confirmation program that meets the requirements of subpart F of this 
part.
    (e) Retrievability of waste. (1) The geologic repository operations 
area must be designed to preserve the option of waste retrieval 
throughout the period during which wastes are being emplaced and 
thereafter, until the completion of a performance confirmation program 
and Commission review of the information obtained from such a program. 
To satisfy this objective, the geologic repository operations area must 
be designed so that any or all of the emplaced waste could be retrieved 
on a reasonable schedule starting at any time up to 50 years after waste 
emplacement operations are initiated, unless a different time period is 
approved or specified by the Commission. This different time period may 
be established on a case-by-case basis consistent with the emplacement 
schedule and the planned performance confirmation program.
    (2) This requirement may not preclude decisions by the Commission to 
allow backfilling part, or all of, or permanent closure of the geologic 
repository operations area, before the end of the period of design for 
retrievability.
    (3) For purposes of paragraph (e) of this section, a reasonable 
schedule for retrieval is one that would permit retrieval in about the 
same time as that required to construct the geologic repository 
operations area and emplace waste.

                       Preclosure Safety Analysis



Sec. 63.112  Requirements for preclosure safety analysis of the 
geologic repository operations area.

    The preclosure safety analysis of the geologic repository operations 
area must include:

[[Page 273]]

    (a) A general description of the structures, systems, components, 
equipment, and process activities at the geologic repository operations 
area;
    (b) An identification and systematic analysis of naturally occurring 
and human-induced hazards at the geologic repository operations area, 
including a comprehensive identification of potential event sequences;
    (c) Data pertaining to the Yucca Mountain site, and the surrounding 
region to the extent necessary, used to identify naturally occurring and 
human-induced hazards at the geologic repository operations area;
    (d) The technical basis for either inclusion or exclusion of 
specific, naturally occurring and human-induced hazards in the safety 
analysis;
    (e) An analysis of the performance of the structures, systems, and 
components to identify those that are important to safety. This analysis 
identifies and describes the controls that are relied on to limit or 
prevent potential event sequences or mitigate their consequences. This 
analysis also identifies measures taken to ensure the availability of 
safety systems. The analysis required in this paragraph must include, 
but not necessarily be limited to, consideration of--
    (1) Means to limit concentration of radioactive material in air;
    (2) Means to limit the time required to perform work in the vicinity 
of radioactive materials;
    (3) Suitable shielding;
    (4) Means to monitor and control the dispersal of radioactive 
contamination;
    (5) Means to control access to high radiation areas or airborne 
radioactivity areas;
    (6) Means to prevent and control criticality;
    (7) Radiation alarm system to warn of significant increases of 
radiation levels, concentrations of radioactive material in air, and 
increased radioactivity in effluents;
    (8) Ability of structures, systems, and components to perform their 
intended safety functions, assuming the occurrence of event sequences;
    (9) Explosion and fire detection systems and appropriate suppression 
systems;
    (10) Means to control radioactive waste and radioactive effluents, 
and permit prompt termination of operations and evacuation of personnel 
during an emergency;
    (11) Means to provide reliable and timely emergency power to 
instruments, utility service systems, and operating systems important to 
safety if there is a loss of primary electric power;
    (12) Means to provide redundant systems necessary to maintain, with 
adequate capacity, the ability of utility services important to safety; 
and
    (13) Means to inspect, test, and maintain structures, systems, and 
components important to safety, as necessary, to ensure their continued 
functioning and readiness.
    (f) A description and discussion of the design, both surface and 
subsurface, of the geologic repository operations area, including--
    (1) The relationship between design criteria and the requirements 
specified at Sec. 63.111(a) and (b); and
    (2) The design bases and their relation to the design criteria.

                   Postclosure Performance Objectives



Sec. 63.113  Performance objectives for the geologic repository after
permanent closure.

    (a) The geologic repository must include multiple barriers, 
consisting of both natural barriers and an engineered barrier system.
    (b) The engineered barrier system must be designed so that, working 
in combination with natural barriers, radiological exposures to the 
reasonably maximally exposed individual are within the limits specified 
at Sec. 63.311 of subpart L of this part. Compliance with this 
paragraph must be demonstrated through a performance assessment that 
meets the requirements specified at Sec. 63.114 of this subpart, and 
Sec. Sec. 63.303, 63.305, 63.312 and 63.342 of Subpart L of this part.
    (c) The engineered barrier system must be designed so that, working 
in combination with natural barriers, releases of radionuclides into the 
accessible environment are within the limits specified at Sec. 63.331 
of subpart L of this part. Compliance with this paragraph

[[Page 274]]

must be demonstrated through a performance assessment that meets the 
requirements specified at Sec. 63.114 of this subpart and Sec. Sec. 
63.303, 63.332 and 63.342 of subpart L of this part.
    (d) The ability of the geologic repository to limit radiological 
exposures to the reasonably maximally exposed individual, in the event 
of human intrusion into the engineered barrier system, must be 
demonstrated through an analysis that meets the requirements at 
Sec. Sec. 63.321 and 63.322 of subpart L of this part. Estimating 
radiological exposures to the reasonably maximally exposed individual 
requires a performance assessment that meets the requirements specified 
at Sec. 63.114 of this subpart, and Sec. Sec. 63.303, 63.305, 63.312 
and 63.342 of subpart L of this part.

                   Postclosure Performance Assessment



Sec. 63.114  Requirements for performance assessment.

    (a) Any performance assessment used to demonstrate compliance with 
Sec. 63.113 for 10,000 years after disposal must:
    (1) Include data related to the geology, hydrology, and geochemistry 
(including disruptive processes and events) of the Yucca Mountain site, 
and the surrounding region to the extent necessary, and information on 
the design of the engineered barrier system used to define, for 10,000 
years after disposal, parameters and conceptual models used in the 
assessment.
    (2) Account for uncertainties and variabilities in parameter values, 
for 10,000 years after disposal, and provide for the technical basis for 
parameter ranges, probability distributions, or bounding values used in 
the performance assessment.
    (3) Consider alternative conceptual models of features and 
processes, for 10,000 years after disposal, that are consistent with 
available data and current scientific understanding and evaluate the 
effects that alternative conceptual models have on the performance of 
the geologic repository.
    (4) Consider only features, events, and processes consistent with 
the limits on performance assessment specified at Sec. 63.342.
    (5) Provide the technical basis for either inclusion or exclusion of 
specific features, events, and processes in the performance assessment. 
Specific features, events, and processes must be evaluated in detail if 
the magnitude and time of the resulting radiological exposures to the 
reasonably maximally exposed individual, or radionuclide releases to the 
accessible environment, for 10,000 years after disposal, would be 
significantly changed by their omission.
    (6) Provide the technical basis for either inclusion or exclusion of 
degradation, deterioration, or alteration processes of engineered 
barriers in the performance assessment, including those processes that 
would adversely affect the performance of natural barriers. Degradation, 
deterioration, or alteration processes of engineered barriers must be 
evaluated in detail if the magnitude and time of the resulting 
radiological exposures to the reasonably maximally exposed individual, 
or radionuclide releases to the accessible environment, for 10,000 years 
after disposal, would be significantly changed by their omission.
    (7) Provide the technical basis for models used to represent the 
10,000 years after disposal in the performance assessment, such as 
comparisons made with outputs of detailed process-level models and/or 
empirical observations (e.g., laboratory testing, field investigations, 
and natural analogs).
    (b) The performance assessment methods used to satisfy the 
requirements of paragraph (a) of this section are considered sufficient 
for the performance assessment for the period of time after 10,000 years 
and through the period of geologic stability.

[74 FR 10828, Mar. 13, 2009]



Sec. 63.115  Requirements for multiple barriers.

    Demonstration of compliance with Sec. 63.113(a) must:
    (a) Identify those design features of the engineered barrier system, 
and natural features of the geologic setting, that are considered 
barriers important to waste isolation.
    (b) Describe the capability of barriers, identified as important to 
waste isolation, to isolate waste, taking into

[[Page 275]]

account uncertainties in characterizing and modeling the behavior of the 
barriers.
    (c) Provide the technical basis for the description of the 
capability of barriers, identified as important to waste isolation, to 
isolate waste. The technical basis for each barrier's capability shall 
be based on and consistent with the technical basis for the performance 
assessments used to demonstrate compliance with Sec. 63.113(b) and (c).

                       Land Ownership and Control



Sec. 63.121  Requirements for ownership and control of interests in land.

    (a) Ownership of land. (1) The geologic repository operations area 
must be located in and on lands that are either acquired lands under the 
jurisdiction and control of DOE, or lands permanently withdrawn and 
reserved for its use.
    (2) These lands must be held free and clear of all encumbrances, if 
significant, such as:
    (i) Rights arising under the general mining laws;
    (ii) Easements for right-of-way; and
    (iii) All other rights arising under lease, rights of entry, deed, 
patent, mortgage, appropriation, prescription, or otherwise.
    (b) Additional controls for permanent closure. Appropriate controls 
must be established outside of the geologic repository operations area. 
DOE shall exercise any jurisdiction and control over surface and 
subsurface estates necessary to prevent adverse human actions that could 
significantly reduce the geologic repository's ability to achieve 
isolation. The rights of DOE may take the form of appropriate possessory 
interests, servitudes, or withdrawals from location or patent under the 
general mining laws.
    (c) Additional controls through permanent closure. Appropriate 
controls must be established outside the geologic repository operations 
area. DOE shall exercise any jurisdiction or control of activities 
necessary to ensure the requirements at Sec. 63.111(a) and (b) are met. 
Control includes the authority to exclude members of the public, if 
necessary.
    (d) Water rights. (1) DOE shall also have obtained such water rights 
as may be needed to accomplish the purpose of the geologic repository 
operations area.
    (2) Water rights are included in the additional controls to be 
established under paragraph (b) of this section.



               Subpart F_Performance Confirmation Program



Sec. 63.131  General requirements.

    (a) The performance confirmation program must provide data that 
indicate, where practicable, whether:
    (1) Actual subsurface conditions encountered and changes in those 
conditions during construction and waste emplacement operations are 
within the limits assumed in the licensing review; and
    (2) Natural and engineered systems and components required for 
repository operation, and that are designed or assumed to operate as 
barriers after permanent closure, are functioning as intended and 
anticipated.
    (b) The program must have been started during site characterization, 
and it will continue until permanent closure.
    (c) The program must include in situ monitoring, laboratory and 
field testing, and in situ experiments, as may be appropriate to provide 
the data required by paragraph (a) of this section.
    (d) The program must be implemented so that:
    (1) It does not adversely affect the ability of the geologic and 
engineered elements of the geologic repository to meet the performance 
objectives.
    (2) It provides baseline information and analysis of that 
information on those parameters and natural processes pertaining to the 
geologic setting that may be changed by site characterization, 
construction, and operational activities.
    (3) It monitors and analyzes changes from the baseline condition of 
parameters that could affect the performance of a geologic repository.



Sec. 63.132  Confirmation of geotechnical and design parameters.

    (a) During repository construction and operation, a continuing 
program of

[[Page 276]]

surveillance, measurement, testing, and geologic mapping must be 
conducted to ensure that geotechnical and design parameters are 
confirmed and to ensure that appropriate action is taken to inform the 
Commission of design changes needed to accommodate actual field 
conditions encountered.
    (b) Subsurface conditions must be monitored and evaluated against 
design assumptions.
    (c) Specific geotechnical and design parameters to be measured or 
observed, including any interactions between natural and engineered 
systems and components, must be identified in the performance 
confirmation plan.
    (d) These measurements and observations must be compared with the 
original design bases and assumptions. If significant differences exist 
between the measurements and observations and the original design bases 
and assumptions, the need for modifications to the design or in 
construction methods must be determined and these differences, their 
significance to repository performance, and the recommended changes 
reported to the Commission.
    (e) In situ monitoring of the thermomechanical response of the 
underground facility must be conducted until permanent closure, to 
ensure that the performance of the geologic and engineering features is 
within design limits.



Sec. 63.133  Design testing.

    (a) During the early or developmental stages of construction, a 
program for testing of engineered systems and components used in the 
design, such as, for example, borehole and shaft seals, backfill, and 
drip shields, as well as the thermal interaction effects of the waste 
packages, backfill, drip shields, rock, and unsaturated zone and 
saturated zone water, must be conducted.
    (b) The testing must be initiated as early as practicable.
    (c) If backfill is included in the repository design, a test must be 
conducted to evaluate the effectiveness of backfill placement and 
compaction procedures against design requirements before permanent 
backfill placement is begun.
    (d) Tests must be conducted to evaluate the effectiveness of 
borehole, shaft, and ramp seals before full-scale operation proceeds to 
seal boreholes, shafts, and ramps.



Sec. 63.134  Monitoring and testing waste packages.

    (a) A program must be established at the geologic repository 
operations area for monitoring the condition of the waste packages. 
Waste packages chosen for the program must be representative of those to 
be emplaced in the underground facility.
    (b) Consistent with safe operation at the geologic repository 
operations area, the environment of the waste packages selected for the 
waste package monitoring program must be representative of the 
environment in which the wastes are to be emplaced.
    (c) The waste package monitoring program must include laboratory 
experiments that focus on the internal condition of the waste packages. 
To the extent practical, the environment experienced by the emplaced 
waste packages within the underground facility during the waste package 
monitoring program must be duplicated in the laboratory experiments.
    (d) The waste package monitoring program must continue as long as 
practical up to the time of permanent closure.



                       Subpart G_Quality Assurance



Sec. 63.141  Scope.

    As used in this part, quality assurance comprises all those planned 
and systematic actions necessary to provide adequate confidence that the 
geologic repository and its structures, systems, or components will 
perform satisfactorily in service. Quality assurance includes quality 
control, which comprises those quality assurance actions related to the 
physical characteristics of a material, structure, component, or system 
that provide a means to control the quality of the material, structure, 
component, or system to predetermined requirements.



Sec. 63.142  Quality assurance criteria.

    (a) Introduction and Applicability. DOE is required by Sec. 
63.21(c)(20) to include in

[[Page 277]]

its safety analysis report a description of the quality assurance 
program to be applied to all structures, systems, and components 
important to safety, to design and characterization of barriers 
important to waste isolation, and to related activities. These 
activities include: site characterization; acquisition, control, and 
analyses of samples and data; tests and experiments; scientific studies; 
facility and equipment design and construction; facility operation; 
performance confirmation; permanent closure; and decontamination and 
dismantling of surface facilities. The description must indicate how the 
applicable quality assurance requirements will be satisfied. DOE shall 
include information pertaining to the managerial and administrative 
controls to be used to ensure safe operation in its safety analysis 
report. High-level waste repositories include structures, systems, and 
components that prevent or mitigate the consequences of postulated event 
sequences or that are important to waste isolation capabilities that 
could cause undue risk to the health and safety of the public. The 
pertinent requirements of this subpart apply to all activities that are 
important to waste isolation and important to safety functions of those 
structures, systems, and components. These activities include designing, 
purchasing, fabricating, handling, shipping, storing, cleaning, 
erecting, installing, inspecting, testing, operating, maintaining, 
repairing, modifying, site characterization, performance confirmation, 
permanent closure, decontamination, and dismantling of surface 
facilities.
    (b) Organization. DOE shall establish and execute a quality 
assurance program. DOE may delegate to others, such as contractors, 
agents, or consultants, the work of establishing and executing the 
quality assurance program, or any part of it, but DOE retains 
responsibility for it.
    (1) The authority and duties of persons and organizations performing 
activities affecting the functions of structures, systems, and 
components that are important to waste isolation and important to safety 
must be clearly established and delineated in writing. These activities 
include both the performing functions of attaining quality objectives 
and the quality assurance functions. The quality assurance functions are 
those of:
    (i) Assuring that an appropriate quality assurance program is 
established and effectively executed; and
    (ii) Verifying that activities important to waste isolation and 
important to safety functions have been correctly performed by checking, 
auditing, and inspection of structures, systems, and components.
    (2) The persons and organizations performing quality assurance 
functions shall have sufficient authority and organizational freedom to 
identify quality problems; to initiate, recommend, or provide solutions; 
and to verify implementation of solutions. The persons and organizations 
performing quality assurance functions shall report to a management 
level so that the required authority and organizational freedom, 
including sufficient independence from cost and schedule when opposed to 
safety considerations, are provided.
    (3) Because of the many variables involved, such as the number of 
personnel, the type of activity being performed, and the location or 
locations where activities are performed, the organizational structure 
for executing the quality assurance program may take various forms 
provided that the persons and organizations assigned the quality 
assurance functions have this required authority and organizational 
freedom. Irrespective of the organizational structure, the individual(s) 
assigned the responsibility for assuring effective execution of any 
portion of the quality assurance program at any location where 
activities subject to 10 CFR part 63 are being performed must have 
direct access to the levels of management as may be necessary to perform 
this function.
    (c) Quality assurance program. DOE shall establish a quality 
assurance program that complies with the requirements of this subpart at 
the earliest practicable time, consistent with the schedule for 
accomplishing the activities. This program must be documented by written 
policies, procedures, or instructions and must be carried out throughout 
facility life in accordance

[[Page 278]]

with those policies, procedures, or instructions.
    (1) DOE shall identify the structures, systems, and components to be 
covered by the quality assurance program and the major organizations 
participating in the program, together with the designated functions of 
these organizations. The quality assurance program must control 
activities affecting the quality of the identified structures, systems, 
and components, to an extent consistent with their importance to safety.
    (2) Activities affecting quality must be accomplished under suitably 
controlled conditions. Controlled conditions include the use of 
appropriate equipment; suitable environmental conditions for 
accomplishing the activity, such as adequate cleanness; and assurance 
that all prerequisites for the given activity have been satisfied.
    (3) The program must take into account the need for special 
controls, processes, test equipment, tools, and skills to attain the 
required quality, and the need for verification of quality by inspection 
and test. The program must provide for indoctrination and training of 
personnel performing activities affecting quality as necessary to assure 
that suitable proficiency is achieved and maintained.
    (4) DOE shall regularly review the status and adequacy of the 
quality assurance program. Management of other organizations 
participating in the quality assurance program shall regularly review 
the status and adequacy of that part of the quality assurance program 
which they are executing.
    (d) Design control. (1) DOE shall establish measures to assure that 
applicable regulatory requirements and the design basis, as defined in 
Sec. 63.2 and as specified in the license application, for those 
structures, systems, and components to which this subpart applies, are 
correctly translated into specifications, drawings, procedures, and 
instructions. These measures must assure that appropriate quality 
standards are specified and included in design documents and that 
deviations from such standards are controlled. Measures must also be 
established for the selection and review for suitability of application 
of materials, parts, equipment, and processes that are important to 
waste isolation and important to safety functions of the structures, 
systems and components.
    (2) DOE shall establish measures to identify and control design 
interfaces and for coordination among participating design 
organizations. These measures must include the establishment of 
procedures among participating design organizations for the review, 
approval, release, distribution, and revision of documents involving 
design interfaces.
    (i) The design control measures must provide for verifying or 
checking the adequacy of design, such as by the performance of design 
reviews, by the use of alternate or simplified calculational methods, or 
by the performance of a suitable testing program. The verifying or 
checking process must be performed by individuals or groups other than 
those who performed the original design. These individuals may be from 
the same organization. If a test program is used to verify the adequacy 
of a specific design feature in lieu of other verifying or checking 
processes, it must include suitable qualifications testing of a 
prototype unit under the most adverse design conditions. Design control 
measures must be applied to items such as: criticality physics, stress, 
thermal, hydraulic, and preclosure and postclosure analyses; 
compatibility of materials; accessibility for inservice inspection, 
maintenance and repair; and delineation of acceptance criteria for 
inspections and tests.
    (ii) Design changes, including field changes, must be subject to 
design control measures commensurate with those applied to the original 
design and be approved by the organization that performed the original 
design unless the applicant designates another responsible organization.
    (e) Procurement document control. DOE shall establish measures to 
assure that applicable regulatory requirements, design bases, and other 
requirements necessary to assure adequate quality are suitably included 
or referenced in the documents for procurement of material, equipment, 
and services, whether purchased by the licensee or applicant or by its 
contractors or subcontractors.

[[Page 279]]

To the extent necessary, procurement documents must require contractors 
or subcontractors to provide a quality assurance program consistent with 
the pertinent provisions of this section.
    (f) Instructions, procedures, and drawings. Activities affecting 
quality must be prescribed by documented instructions, procedures, or 
drawings of a type appropriate to the circumstances and must be 
accomplished in accordance with these instructions, procedures, or 
drawings. Instructions, procedures, or drawings must include appropriate 
quantitative or qualitative acceptance criteria for determining that 
important activities have been satisfactorily accomplished.
    (g) Document control. DOE shall establish measures to control the 
issuance of documents, such as instructions, procedures, and drawings, 
including changes to them that prescribe all activities affecting 
quality. These measures must assure that documents, including changes, 
are reviewed for adequacy and approved for release by authorized 
personnel and are distributed to and used at the location where the 
prescribed activity is performed. Changes to documents must be reviewed 
and approved by the same organizations that performed the original 
review and approval unless the applicant designates another responsible 
organization.
    (h) Control of purchased material, equipment, and services. DOE 
shall establish measures to assure that purchased material, equipment, 
and services, whether purchased directly or through contractors and 
subcontractors, conform to the procurement documents.
    (1) These measures must include appropriate provisions for source 
evaluation and selection, objective evidence of quality furnished by the 
contractor or subcontractor, inspection at the contractor or 
subcontractor source, and examination of products upon delivery.
    (2) Documentary evidence that material and equipment conform to the 
procurement requirements must be available at the high-level waste 
repository site before the material and equipment are installed or used. 
This documentary evidence must be retained at the high-level waste 
repository site and be sufficient to identify the specific requirements, 
such as codes, standards, or specifications, met by the purchased 
material and equipment.
    (3) The effectiveness of the control of quality by contractors and 
subcontractors must be assessed by the licensee or applicant or designee 
at intervals consistent with the importance, complexity, and quantity of 
the product or services.
    (i) Identification and control of materials, parts, and components. 
Measures must be established for the identification and control of 
materials, parts, and components, including partially fabricated 
assemblies. These measures must assure that identification of the item 
is maintained by heat number, part number, serial number, or other 
appropriate means, either on the item or on records traceable to the 
item, as required throughout fabrication, erection, installation, and 
use of the item. These identification and control measures must be 
designed to prevent the use of incorrect or defective material, parts, 
and components.
    (j) Control of special processes. DOE shall establish measures to 
assure that special processes, including welding, heat treating, and 
nondestructive testing, are controlled and accomplished by qualified 
personnel using qualified procedures in accordance with applicable 
codes, standards, specifications, criteria, and other special 
requirements.
    (k) Inspection. DOE shall establish and execute a program for 
inspection of activities affecting quality to verify conformance with 
the documented instructions, procedures, and drawings for accomplishing 
the activity. The inspection must be performed by individuals other than 
those who performed the activity being inspected.
    (1) Examinations, measurements, or tests of material or products 
processed must be performed for each work operation where necessary to 
assure quality. If inspection of processed material or products is 
impossible or disadvantageous, indirect control by monitoring processing 
methods, equipment, and personnel must be provided. Both inspection and 
process monitoring

[[Page 280]]

must be provided when control is inadequate without both.
    (2) If mandatory inspection hold points that require witnessing or 
inspecting by the applicant's designated representative and beyond which 
work may not proceed without the consent of its designated 
representative are required, the specific hold points must be indicated 
in appropriate documents.
    (l) Test control. DOE shall establish a test program to assure that 
all testing required to demonstrate that structures, systems, and 
components important to safety will perform satisfactorily in service is 
identified and performed in accordance with written test procedures 
which incorporate the requirements and acceptance limits contained in 
applicable design documents.
    (1) The test program must include, as appropriate, proof tests prior 
to installation, preoperational tests, and operational tests during 
repository operation, of structures, systems, and components.
    (2) Test procedures must include provisions for assuring that all 
prerequisites for the given test have been met, that adequate test 
instrumentation is available and used, and that the test is performed 
under suitable environmental conditions.
    (3) Test results must be documented and evaluated to assure that 
test requirements have been satisfied.
    (m) Control of measuring and test equipment. DOE shall establish 
measures to assure that tools, gages, instruments, and other measuring 
and testing devices used in activities affecting quality are properly 
controlled, calibrated, and adjusted at specified periods to maintain 
accuracy within necessary limits.
    (n) Handling, storage, and shipping. DOE shall establish measures to 
control the handling, storage, shipping, cleaning and preservation of 
material and equipment in accordance with work and inspection 
instructions to prevent damage or deterioration. When necessary for 
particular products, special protective environments, such as inert gas 
atmosphere, specific moisture content levels, and temperature levels, 
must be specified and provided.
    (o) Inspection, test, and operating status. DOE shall establish 
measures to indicate the status of inspections and tests performed on 
individual items of the high-level waste repository by markings such as 
stamps, tags, labels, routing cards, or other suitable means. These 
measures must provide for the identification of items that have 
satisfactorily passed required inspections and tests, where necessary to 
preclude inadvertent bypassing of such inspections and tests. Measures 
must also be established for indicating the operating status of 
structures, systems, and components of the high-level waste repository, 
such as by tagging valves and switches, to prevent inadvertent 
operation.
    (p) Nonconforming materials, parts, or components. DOE shall 
establish measures to control materials, parts, or components which do 
not conform to requirements in order to prevent their inadvertent use or 
installation. These measures must include, as appropriate, procedures 
for identification, documentation, segregation, disposition, and 
notification to affected organizations. Nonconforming items must be 
reviewed and accepted, rejected, repaired or reworked in accordance with 
documented procedures.
    (q) Corrective action. DOE shall establish measures to assure that 
conditions adverse to quality, such as failures, malfunctions, 
deficiencies, deviations, defective material and equipment, and 
nonconformances are promptly identified and corrected. If significant 
conditions are adverse to quality, the measures must assure that the 
cause of the condition is determined and corrective action taken to 
preclude repetition. The identification of the significant condition 
adverse to quality, the cause of the condition, and the corrective 
action taken must be documented and reported to appropriate levels of 
management.
    (r) Quality assurance records. DOE shall maintain sufficient records 
to furnish evidence of activities affecting quality.
    (1) The records must include at least the following: Operating logs 
and the results of reviews, inspections, tests, audits, monitoring of 
work performance, and materials analyses.

[[Page 281]]

    (2) The records must also include closely-related data such as 
qualifications of personnel, procedures, and equipment.
    (3) Inspection and test records must, at a minimum, identify the 
inspector or data recorder, the type of observation, the results, the 
acceptability, and the action taken in connection with any deficiencies 
noted.
    (4) Records must be identifiable and retrievable. Consistent with 
applicable regulatory requirements, the applicant shall establish 
requirements concerning record retention, such as duration, location, 
and assigned responsibility.
    (s) Audits. DOE shall carry out a comprehensive system of planned 
and periodic audits to verify compliance with all aspects of the quality 
assurance program and to determine the effectiveness of the program. The 
audits must be performed in accordance with the written procedures or 
check lists by appropriately trained personnel not having direct 
responsibilities in the areas being audited. Audit results must be 
documented and reviewed by management having responsibility in the area 
audited. Followup action, including reaudit of deficient areas, must be 
taken where indicated.



Sec. 63.143  Implementation.

    DOE shall implement a quality assurance program based on the 
criteria required by Sec. 63.142.



Sec. 63.144  Quality assurance program change.

    Changes to DOE's NRC-approved Safety Analysis Report quality 
assurance program description are processed as follows:
    (a) DOE may change a previously accepted quality assurance program 
description included or referenced in the Safety Analysis Report without 
prior NRC approval, if the change does not reduce the commitments in the 
program description previously accepted by the NRC. Changes to the 
quality assurance program description that do not reduce the commitments 
must be submitted every 24 months, in accordance with paragraph (b)(1) 
of this section. In addition to quality assurance program changes 
involving administrative improvements and clarifications, spelling 
corrections, punctuation, or editorial items, the following changes are 
not considered reductions in commitment:
    (1) The use of a quality assurance standard approved by the NRC 
which is more recent than the quality assurance standard in DOE's 
current quality assurance program at the time of the change;
    (2) The use of generic organizational position titles that clearly 
denote the position function, supplemented as necessary by descriptive 
text, rather than specific titles;
    (3) The use of generic organizational charts to indicate functional 
relationships, authorities, and responsibilities, or alternatively, the 
use of descriptive text;
    (4) The elimination of quality assurance program information that 
duplicates language in quality assurance regulatory guides and quality 
assurance standards to which the licensee is committed; and
    (5) Organizational revisions that ensure that persons and 
organizations performing quality assurance functions continue to have 
the requisite authority and organizational freedom, including sufficient 
independence from cost and schedule when opposed to safety 
considerations.
    (b) DOE shall submit changes made to the NRC-accepted Safety 
Analysis Report quality assurance program description that do reduce the 
commitments to the NRC and receive NRC approval prior to implementation, 
as follows:
    (1) By an appropriate method listed in Sec. 63.4 of this chapter, 
the signed document must be submitted to the Nuclear Regulatory 
Commission, addressed: ATTN: Document Control Desk; Director, Office of 
Nuclear Material and Safeguards; U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, and one copy to the appropriate NRC Resident 
Inspector, if one has been assigned to the site or facility.
    (2) The submittal of a change to the Safety Analysis Report quality 
assurance program description must include all pages affected by that 
change and must be accompanied by a forwarding

[[Page 282]]

letter identifying the change, the reason for the change, and the basis 
for concluding that the revised program incorporating the change 
continues to describe how the requirements of Sec. 63.142 will be 
satisfied and continues to satisfy the criteria of Sec. 63.142 and the 
Safety Analysis Report quality assurance program description previously 
accepted by the NRC (the letter need not provide the basis for changes 
that correct spelling, punctuation, or editorial items).
    (3) DOE shall maintain records of quality assurance program changes 
that do reduce commitments.

[66 FR 55792, Nov. 2, 2001, as amended at 68 FR 58816, Oct. 10, 2003]



            Subpart H_Training and Certification of Personnel



Sec. 63.151  General requirements.

    Operations of systems and components that have been identified as 
important to safety in the Safety Analysis Report and in the license 
must be performed only by trained and certified personnel or by 
personnel under the direct visual supervision of an individual with 
training and certification in such operation. Supervisory personnel who 
direct operations that are important to safety must also be certified in 
such operations.



Sec. 63.152  Training and certification program.

    DOE shall establish a program for training, proficiency testing, 
certification, and requalification of operating and supervisory 
personnel.



Sec. 63.153  Physical requirements.

    The physical condition and the general health of personnel certified 
for operations that are important to safety may not be such as might 
cause operational errors that could endanger the public health and 
safety. Any condition that might cause impaired judgment or motor 
coordination must be considered in the selection of personnel for 
activities that are important to safety. These conditions need not 
categorically disqualify a person, so long as appropriate provisions are 
made to accommodate the conditions.



                  Subpart I_Emergency Planning Criteria



Sec. 63.161  Emergency plan for the geologic repository operations
area through permanent closure.

    DOE shall develop and be prepared to implement a plan to cope with 
radiological accidents that may occur at the geologic repository 
operations area, at any time before permanent closure and 
decontamination or decontamination and dismantlement of surface 
facilities. The emergency plan must be based on the criteria of Sec. 
72.32(b) of this chapter.



                          Subpart J_Violations



Sec. 63.171  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued under those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued under the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.



Sec. 63.172  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223,

[[Page 283]]

all the regulations in this part 63 are issued under one or more of 
sections 161b, 161i, or 161o, except for the sections listed in 
paragraph (b) of this section.
    (b) The regulations in this part 63 that are not issued under 
sections 161b, 161i, or 161o for the purposes of Section 223 are as 
follows: Sec. Sec. 63.1, 63.2, 63.5, 63.6, 63.7, 63.8, 63.15, 63.16, 
63.21, 63.22, 63.23, 63.24, 63.31, 63.32, 63.33, 63.41, 63.42, 63.43, 
63.45, 63.46, 63.51, 63.52, 63.61, 63.62, 63.63, 63.64, 63.65, 63.101, 
63.102, 63.111, 63.112, 63.113, 63.114, 63.115, 63.121, 63.131, 63.132, 
63.133, 63.134, 63.141, 63.142, 63.143, 63.153, 63.161, 63.171, 63.172, 
63.201, 63.202, 63.203, 63.204, 63.301, 63.302, 63.303, 63.304, 63.305, 
63.311, 63.312, 63.321, 63.322, 63.331, 63.332, 63.341, and 63.342.



     Subpart K_Preclosure Public Health and Environmental Standards



Sec. 63.201  Purpose and scope.

    This subpart covers the storage of radioactive material by DOE in 
the Yucca Mountain repository and on the Yucca Mountain site. For the 
purposes of demonstrating compliance with this subpart, to the extent 
there may be any conflict with the requirements specified in this 
subpart and the requirements contained in Subparts A-J of this 
regulation, including definitions, the requirements in this subpart 
shall take precedence.



Sec. 63.202  Definitions for Subpart K.

    General environment means everywhere outside the Yucca Mountain 
site, the Nellis Air Force Range, and the Nevada Test Site.
    Member of the public means anyone who is not a radiation worker for 
purposes of worker protection.
    Radioactive material means matter composed of or containing 
radionuclides subject to the Atomic Energy Act of 1954, as amended (42 
U.S.C. sec. 2014 et seq.). Radioactive material includes, but is not 
limited to, high-level radioactive waste and spent nuclear fuel.
    Spent nuclear fuel means fuel that has been withdrawn from a nuclear 
reactor following irradiation, the constituent elements of which have 
not been separated by reprocessing.
    Storage means retention (and any associated activity, operation, or 
process necessary to carry out successful retention) of radioactive 
material with the intent or capability to readily access or retrieve 
such material.
    Yucca Mountain repository means the excavated portion of the 
facility constructed underground within the Yucca Mountain site.
    Yucca Mountain site means:
    (1) The site recommended by the Secretary of DOE to the President 
under section 112(b)(1)(B) of the Nuclear Waste Policy Act of 1982 (42 
U.S.C. 10132(b)(1)(B)) on May 27, 1986; or
    (2) The area under the control of DOE for the use of Yucca Mountain 
activities at the time of licensing, if the site designated under the 
Nuclear Waste Policy Act is amended by Congress prior to the time of 
licensing.



Sec. 63.203  Implementation of Subpart K.

    DOE must demonstrate that normal operations at the Yucca Mountain 
site will and do occur in compliance with this subpart before the 
Commission grants or continues a license for DOE to receive and possess 
radioactive material within the Yucca Mountain site.



Sec. 63.204  Preclosure standard.

    DOE must ensure that no member of the public in the general 
environment receives more than an annual dose of 0.15 mSv (15 mrem) from 
the combination of:
    (a) Management and storage (as defined in 40 CFR 191.2) of 
radioactive material that:
    (1) Is subject to 40 CFR 191.3(a); and
    (2) Occurs outside of the Yucca Mountain repository but within the 
Yucca Mountain site; and
    (b) Storage (as defined in Sec. 63.202) of radioactive material 
inside the Yucca Mountain repository.



     Subpart L_Postclosure Public Health and Environmental Standards



Sec. 63.301  Purpose and scope.

    This subpart covers the disposal of radioactive material in the 
Yucca Mountain repository by DOE. For the purposes of demonstrating 
compliance

[[Page 284]]

with this subpart, to the extent that there may be any conflict with the 
requirements specified in this subpart and the requirements contained in 
Subparts A-J of this part, including definitions, the requirements in 
this subpart shall take precedence.



Sec. 63.302  Definitions for Subpart L.

    All definitions in subpart K of this part, and the following:
    Accessible environment means any point outside of the controlled 
area, including:
    (1) The atmosphere (including the atmosphere above the surface area 
of the controlled area);
    (2) Land surfaces;
    (3) Surface waters;
    (4) Oceans; and
    (5) The lithosphere.
    Aquifer means a water-bearing underground geological formation, 
group of formations, or part of a formation (excluding perched water 
bodies) that can yield a significant amount of groundwater to a well or 
spring.
    Controlled area means:
    (1) The surface area, identified by passive institutional controls, 
that encompasses no more than 300 square kilometers. It must not extend 
farther:
    (i) South than 36[deg]40[min]13.6661[sec] North latitude, in the 
predominant direction of groundwater flow; and
    (ii) Than five kilometers from the repository footprint in any other 
direction; and
    (2) The subsurface underlying the surface area.
    Disposal means the emplacement of radioactive material into the 
Yucca Mountain disposal system with the intent of isolating it for as 
long as reasonably possible and with no intent of recovery, whether or 
not the design of the disposal system permits the ready recovery of the 
material. Disposal of radioactive material in the Yucca Mountain 
disposal system begins when all of the ramps and other openings into the 
Yucca Mountain repository are sealed.
    Groundwater means water that is below the land surface and in a 
saturated zone.
    Human intrusion means breaching of any portion of the Yucca Mountain 
disposal system, within the repository footprint, by any human activity.
    Passive institutional controls means:
    (1) Markers, as permanent as practicable, placed on the Earth's 
surface;
    (2) Public records and archives;
    (3) Government ownership and regulations regarding land or resource 
use; and
    (4) Other reasonable methods of preserving knowledge about the 
location, design, and contents of the Yucca Mountain disposal system.
    Peak dose means the highest annual dose projected to be received by 
the reasonably maximally exposed individual.
    Period of geologic stability means the time during which the 
variability of geologic characteristics and their future behavior in and 
around the Yucca Mountain site can be bounded, that is, they can be 
projected within a reasonable range of possibilities. This period is 
defined to end at 1 million years after disposal.
    Plume of contamination means that volume of groundwater in the 
predominant direction of groundwater flow that contains radioactive 
contamination from releases from the Yucca Mountain repository. It does 
not include releases from any other potential sources on or near the 
Nevada Test Site.
    Repository footprint means the outline of the outermost locations of 
where the waste is emplaced in the Yucca Mountain repository.
    Slice of the plume means a cross-section of the plume of 
contamination with sufficient thickness parallel to the prevalent 
direction of flow of the plume that it contains the representative 
volume.
    Total dissolved solids means the total dissolved (filterable) solids 
in water as determined by use of the method specified in 40 CFR part 
136.
    Undisturbed performance means that human intrusion or the occurrence 
of unlikely natural features, events, and processes do not disturb the 
disposal system.
    Undisturbed Yucca Mountain disposal system means that the Yucca 
Mountain disposal system is not affected by human intrusion.

[[Page 285]]

    Waste means any radioactive material emplaced for disposal into the 
Yucca Mountain repository.
    Well-capture zone means the volume from which a well pumping at a 
defined rate is withdrawing water from an aquifer. The dimensions of the 
well-capture zone are determined by the pumping rate in combination with 
aquifer characteristics assumed for calculations, such as hydraulic 
conductivity, gradient, and the screened interval.
    Yucca Mountain disposal system means the combination of underground 
engineered and natural barriers within the controlled area that prevents 
or substantially reduces releases from the waste.

[66 FR 55792, Nov. 2, 2001, as amended at 74 FR 10829, Mar. 13, 2009]



Sec. 63.303  Implementation of Subpart L.

    (a) Compliance is based upon the arithmetic mean of the projected 
doses from DOE's performance assessments for the period within 1 million 
years after disposal, with:
    (1) Sections 63.311(a)(1) and 63.311(a)(2); and
    (2) Sections 63.321(b)(1), 63.321(b)(2), and 63.331, if performance 
assessment is used to demonstrate compliance with either or both of 
these sections.
    (b) [Reserved]

[74 FR 10829, Mar. 13, 2009]



Sec. 63.304  Reasonable expectation.

    Reasonable expectation means that the Commission is satisfied that 
compliance will be achieved based upon the full record before it. 
Characteristics of reasonable expectation include that it:
    (1) Requires less than absolute proof because absolute proof is 
impossible to attain for disposal due to the uncertainty of projecting 
long-term performance;
    (2) Accounts for the inherently greater uncertainties in making 
long-term projections of the performance of the Yucca Mountain disposal 
system;
    (3) Does not exclude important parameters from assessments and 
analyses simply because they are difficult to precisely quantify to a 
high degree of confidence; and
    (4) Focuses performance assessments and analyses on the full range 
of defensible and reasonable parameter distributions rather than only 
upon extreme physical situations and parameter values.



Sec. 63.305  Required characteristics of the reference biosphere.

    (a) Features, events, and processes that describe the reference 
biosphere must be consistent with present knowledge of the conditions in 
the region surrounding the Yucca Mountain site.
    (b) DOE should not project changes in society, the biosphere (other 
than climate), human biology, or increases or decreases of human 
knowledge or technology. In all analyses done to demonstrate compliance 
with this part, DOE must assume that all of those factors remain 
constant as they are at the time of submission of the license 
application.
    (c) DOE must vary factors related to the geology, hydrology, and 
climate based upon cautious, but reasonable assumptions of the changes 
in these factors that could affect the Yucca Mountain disposal system 
during the period of geologic stability, consistent with the 
requirements for performance assessments specified at Sec. 63.342.
    (d) Biosphere pathways must be consistent with arid or semi-arid 
conditions.

[66 FR 55792, Nov. 2, 2001, as amended at 74 FR 10829, Mar. 13, 2009]

               Postclosure Individual Protection Standard



Sec. 63.311  Individual protection standard after permanent closure.

    (a) DOE must demonstrate, using performance assessment, that there 
is a reasonable expectation that the reasonably maximally exposed 
individual receives no more than the following annual dose from releases 
from the undisturbed Yucca Mountain disposal system:
    (1) 0.15 mSv (15 mrem) for 10,000 years following disposal; and
    (2) 1.0 mSv (100 mrem) after 10,000 years, but within the period of 
geologic stability.
    (b) DOE's performance assessment must include all potential pathways 
of radionuclide transport and exposure.

[74 FR 10829, Mar. 13, 2009]

[[Page 286]]



Sec. 63.312  Required characteristics of the reasonably maximally 
exposed individual.

    The reasonably maximally exposed individual is a hypothetical person 
who meets the following criteria:
    (a) Lives in the accessible environment above the highest 
concentration of radionuclides in the plume of contamination;
    (b) Has a diet and living style representative of the people who now 
reside in the Town of Amargosa Valley, Nevada. DOE must use projections 
based upon surveys of the people residing in the Town of Amargosa 
Valley, Nevada, to determine their current diets and living styles and 
use the mean values of these factors in the assessments conducted for 
Sec. Sec. 63.311 and 63.321;
    (c) Uses well water with average concentrations of radionuclides 
based on an annual water demand of 3000 acre-feet;
    (d) Drinks 2 liters of water per day from wells drilled into the 
groundwater at the location specified in paragraph (a) of this section; 
and
    (e) Is an adult with metabolic and physiological considerations 
consistent with present knowledge of adults.

                        Human Intrusion Standard



Sec. 63.321  Individual protection standard for human intrusion.

    (a) DOE must determine the earliest time after disposal that the 
waste package would degrade sufficiently that a human intrusion (see 
Sec. 63.322) could occur without recognition by the drillers.
    (b) DOE must demonstrate that there is a reasonable expectation that 
the reasonably maximally exposed individual receives, as a result of the 
human intrusion, no more than the following annual dose:
    (1) 0.15 mSv (15 mrem) for 10,000 years following disposal; and
    (2) 1.0 mSv (100 mrem) after 10,000 years, but within the period of 
geologic stability.
    (c) DOE's analysis must include all potential environmental pathways 
of radionuclide transport and exposure, subject to the requirements of 
Sec. 63.322.

[74 FR 10829, Mar. 13, 2009]



Sec. 63.322  Human intrusion scenario.

    For the purposes of the analysis of human intrusion, DOE must make 
the following assumptions:
    (a) There is a single human intrusion as a result of exploratory 
drilling for groundwater;
    (b) The intruders drill a borehole directly through a degraded waste 
package into the uppermost aquifer underlying the Yucca Mountain 
repository;
    (c) The drillers use the common techniques and practices that are 
currently employed in exploratory drilling for groundwater in the region 
surrounding Yucca Mountain;
    (d) Careful sealing of the borehole does not occur, instead natural 
degradation processes gradually modify the borehole;
    (e) No particulate waste material falls into the borehole;
    (f) The exposure scenario includes only those radionuclides 
transported to the saturated zone by water (e.g., water enters the waste 
package, releases radionuclides, and transports radionuclides by way of 
the borehole to the saturated zone); and
    (g) No releases are included which are caused by unlikely natural 
processes and events.

                    Groundwater Protection Standards



Sec. 63.331  Separate standards for protection of groundwater.

    DOE must demonstrate that there is a reasonable expectation that, 
for 10,000 years of undisturbed performance after disposal, releases of 
radionuclides from waste in the Yucca Mountain disposal system into the 
accessible environment will not cause the level of radioactivity in the 
representative volume of groundwater to exceed the limits in the 
following Table 1:

      Table 1--Limits on Radionuclides in the Representative Volume
------------------------------------------------------------------------
                                                           Is natural
    Radionuclide or type of              Limit             background
       radiation emitted                                    included?
------------------------------------------------------------------------
Combined radium-226 and radium- 5 picocuries per liter  Yes.
 228.

[[Page 287]]

 
Gross alpha activity            15 picocuries per       Yes.
 (including radium-226 but       liter.
 excluding radon and uranium).
Combined beta and photon        0.04 mSv (4 mrem) per   No.
 emitting radionuclides.         year to the whole
                                 body or any organ,
                                 based on drinking 2
                                 liters of water per
                                 day from the
                                 representative volume.
------------------------------------------------------------------------



Sec. 63.332  Representative volume.

    (a) The representative volume is the volume of groundwater that 
would be withdrawn annually from an aquifer containing less than 10,000 
milligrams of total dissolved solids per liter of water to supply a 
given water demand. DOE must project the concentration of radionuclides 
released from the Yucca Mountain disposal system that will be in the 
representative volume. DOE must use the projected concentrations to 
demonstrate a reasonable expectation that the Yucca Mountain disposal 
system complies with Sec. 63.331. The DOE must make the following 
assumptions concerning the representative volume:
    (1) It includes the highest concentration level in the plume of 
contamination in the accessible environment;
    (2) Its position and dimensions in the aquifer are determined using 
average hydrologic characteristics which have cautious, but reasonable, 
values representative of the aquifers along the radionuclide migration 
path from the Yucca Mountain repository to the accessible environment as 
determined by site characterization; and
    (3) It contains 3,000 acre-feet of water (about 3,714,450,000 liters 
or 977,486,000 gallons).
    (b) DOE must use one of two alternative methods for determining the 
dimensions of the representative volume. The DOE must propose its chosen 
method, and any underlying assumptions, to NRC for approval.
    (1) DOE may calculate the dimensions as a well-capture zone. If DOE 
uses this approach, it must assume that the:
    (i) Water supply well(s) has (have) characteristics consistent with 
public water supply wells in the Town of Amargosa Valley, Nevada, for 
example, well-bore size and length of the screened intervals;
    (ii) Screened interval(s) include(s) the highest concentration in 
the plume of contamination in the accessible environment; and
    (iii) Pumping rates and the placement of the well(s) must be set to 
produce an annual withdrawal equal to the representative volume and to 
tap the highest concentration within the plume of contamination.
    (2) DOE may calculate the dimensions as a slice of the plume. If DOE 
uses this approach, it must:
    (i) Propose, for approval, where the location of the edge of the 
plume of contamination occurs. For example, the place where the 
concentration of radionuclides reaches 0.1% of the level of the highest 
concentration in the accessible environment;
    (ii) Assume that the slice of the plume is perpendicular to the 
prevalent direction of flow of the aquifer; and
    (iii) Assume that the volume of groundwater contained within the 
slice of the plume equals the representative volume.

                          Additional Provisions



Sec. 63.342  Limits on performance assessments.

    (a) DOE's performance assessments conducted to show compliance with 
Sec. Sec. 63.311(a)(1), 63.321(b)(1), and 63.331 shall not include 
consideration of very unlikely features, events, or processes, i.e., 
those that are estimated to have less than one chance in 100,000,000 per 
year of occurring. In addition, DOE's performance assessments need not 
evaluate the impacts resulting from any features, events, and processes 
or sequences of events and processes with a higher chance of occurring 
if the results of the performance assessments would not be changed 
significantly in the initial 10,000-year period after disposal.

[[Page 288]]

    (b) For performance assessments conducted to show compliance with 
Sec. Sec. 63.321(b)(1) and 63.331, DOE's performance assessments shall 
exclude the unlikely features, events, and processes, or sequences of 
events and processes, i.e., those that are estimated to have less than 
one chance in 100,000 per year of occurring and at least one chance in 
100,000,000 per year of occurring.
    (c) For performance assessments conducted to show compliance with 
Sec. Sec. 63.311(a)(2) and 63.321(b)(2), DOE's performance assessments 
shall project the continued effects of the features, events, and 
processes included in paragraph (a) of this section beyond the 10,000-
year post-disposal period through the period of geologic stability. DOE 
must evaluate all of the features, events, or processes included in 
paragraph (a) of this section, and also:
    (1) DOE must assess the effects of seismic and igneous activity 
scenarios, subject to the probability limits in paragraph (a) of this 
section for very unlikely features, events, and processes, or sequences 
of events and processes. Performance assessments conducted to show 
compliance with Sec. 63.321(b)(2) are also subject to the probability 
limits in paragraph (b) of this section for unlikely features, events, 
and processes, or sequences of events and processes.
    (i) The seismic analysis may be limited to the effects caused by 
damage to the drifts in the repository, failure of the waste packages, 
and changes in the elevation of the water table under Yucca Mountain 
(i.e., the magnitude of the water table rise under Yucca Mountain).
    (ii) The igneous activity analysis may be limited to the effects of 
a volcanic event directly intersecting the repository. The igneous event 
may be limited to that causing damage to the waste packages directly, 
causing releases of radionuclides to the biosphere, atmosphere, or 
groundwater.
    (2) DOE must assess the effects of climate change. The climate 
change analysis may be limited to the effects of increased water flow 
through the repository as a result of climate change, and the resulting 
transport and release of radionuclides to the accessible environment. 
The nature and degree of climate change may be represented by constant-
in-time climate conditions. The analysis may commence at 10,000 years 
after disposal and shall extend through the period of geologic 
stability. The constant-in-time values to be used to represent climate 
change are to be the spatial average of the deep percolation rate within 
the area bounded by the repository footprint. The constant-in-time deep 
percolation rates to be used to represent climate change shall be based 
on a lognormal distribution with an arithmetic mean of 41 mm/year (1.6 
in./year) and a standard deviation of 33 mm/year (1.3 in./year). The 
lognormal distribution is to be truncated so that the deep percolation 
rates vary between 10 and 100 mm/year (0.39 and 3.9 in./year).
    (3) DOE must assess the effects of general corrosion on engineered 
barriers. DOE may use a constant representative corrosion rate 
throughout the period of geologic stability or a distribution of 
corrosion rates correlated to other repository parameters.

[74 FR 10829, Mar. 13, 2009]



Sec. 63.343  Severability of individual protection and groundwater
protection standards.

    The individual protection and groundwater protection standards are 
severable.



PART 70_DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL--
Table of Contents



                      Subpart A_General Provisions

Sec.
70.1 Purpose.
70.2 Scope.
70.3 License requirements.
70.4 Definitions.
70.5 Communications.
70.6 Interpretations.
70.7 Employee protection.
70.8 Information collection requirements: OMB approval.
70.9 Completeness and accuracy of information.
70.10 Deliberate misconduct.

                          Subpart B_Exemptions

70.11 Persons using special nuclear material under certain Department of 
          Energy and Nuclear Regulatory Commission contracts.
70.12 Carriers.

[[Page 289]]

70.13 Department of Defense.
70.14 Foreign military aircraft.
70.17 Specific exemptions.

                       Subpart C_General Licenses

70.18 Types of licenses.
70.19 General license for calibration or reference sources.
70.20 General license to own special nuclear material.
70.20a General license to possess special nuclear material for 
          transport.
70.20b General license for carriers of transient shipments of formula 
          quantities of strategic special nuclear material, special 
          nuclear material of moderate strategic significance, special 
          nuclear material of low strategic significance, and irradiated 
          reactor fuel.

                     Subpart D_License Applications

70.21 Filing.
70.22 Contents of applications.
70.23 Requirements for the approval of applications.
70.23a Hearing required for uranium enrichment facility.
70.24 Criticality accident requirements.
70.25 Financial assurance and recordkeeping for decommissioning.

                           Subpart E_Licenses

70.31 Issuance of licenses.
70.32 Conditions of licenses.
70.33 Applications for renewal of licenses.
70.34 Amendment of licenses.
70.35 Commission action on applications to renew or amend.
70.36 Inalienability of licenses.
70.37 Disclaimer of warranties.
70.38 Expiration and termination of licenses and decommissioning of 
          sites and separate buildings or outdoor areas.
70.39 Specific licenses for the manufacture or initial transfer of 
          calibration or reference sources.
70.40 Ineligibility of certain applicants.

  Subpart F_Acquisition, Use and Transfer of Special Nuclear Material, 
                            Creditors' Rights

70.41 Authorized use of special nuclear material.
70.42 Transfer of special nuclear material.
70.44 Creditor regulations.

    Subpart G_Special Nuclear Material Control, Records, Reports and 
                               Inspections

70.50 Reporting requirements.
70.51 Records requirements.
70.52 Reports of accidental criticality.
70.55 Inspections.
70.56 Tests.
70.59 Effluent monitoring reporting requirements.

 Subpart H_Additional Requirements for Certain Licensees Authorized To 
           Possess a Critical Mass of Special Nuclear Material

70.60 Applicability.
70.61 Performance requirements.
70.62 Safety program and integrated safety analysis.
70.64 Requirements for new facilities or new processes at existing 
          facilities.
70.65 Additional content of applications.
70.66 Additional requirements for approval of license application.
70.72 Facility changes and change process.
70.73 Renewal of licenses.
70.74 Additional reporting requirements.
70.76 Backfitting.

            Subpart I_Modification and Revocation of Licenses

70.81 Modification and revocation of licenses.
70.82 Suspension and operation in war or national emergency.

                          Subpart J_Enforcement

70.91 Violations.
70.92 Criminal penalties.

Appendix A to Part 70--Reportable Safety Events

    Authority: Atomic Energy Act of 1954, secs. 51, 53, 57(d), 108, 122, 
161, 182, 183, 184, 186, 187, 193, 223, 234, 274, 1701 (42 U.S.C. 2071, 
2073, 2077(d), 2138, 2152, 2201, 2232, 2233, 2234, 2236, 2237, 2243, 
2273, 2282, 2021, 2297f); Energy Reorganization Act of 1974, secs. 201, 
202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy 
Act of 1982, secs. 135, 141 (42 U.S.C. 10155, 10161); 44 U.S.C. 3504 
note.
    Sections 70.1(c) and 70.20a(b) also issued under secs. 135, 141, 
Pub. L. 97-425, 96 Stat. 2232, 2241 (42 U.S.C. 10155, 10161).
    Section 70.21(g) also issued under Atomic Energy Act sec. 122 (42 
U.S.C. 2152).
    Section 70.31 also issued under Atomic Energy Act sec. 57(d) (42 
U.S.C. 2077(d)).
    Sections 70.36 and 70.44 also issued under Atomic Energy Act sec. 
184 (42 U.S.C. 2234).
    Section 70.81 also issued under Atomic Energy Act secs. 186, 187 (42 
U.S.C. 2236, 2237).
    Section 70.82 also issued under Atomic Energy Act sec. 108 (42 
U.S.C. 2138).

    Source: 21 FR 764, Feb. 3, 1956, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 70 appear at 81 FR 
86910, Dec. 2, 2016.

[[Page 290]]



                      Subpart A_General Provisions



Sec. 70.1  Purpose.

    (a) Except as provided in paragraphs (c) and (d) of this section, 
the regulations of this part establish procedures and criteria for the 
issuance of licenses to receive title to, own, acquire, deliver, 
receive, possess, use, and transfer special nuclear material; and 
establish and provide for the terms and conditions upon which the 
Commission will issue such licenses.
    (b) The regulations contained in this part are issued pursuant to 
the Atomic Energy Act of 1954, as amended (68 Stat. 919) and Title II of 
the Energy Reorganization Act of 1974 (88 Stat. 1242).
    (c) The regulations in part 72 of this chapter establish 
requirements, procedures, and criteria for the issuance of licenses to 
possess:
    (1) Spent fuel, power reactor-related Greater than Class C (GTCC) 
waste, and other radioactive materials associated with spent fuel 
storage in an independent spent fuel storage installation (ISFSI), or
    (2) Spent fuel, high-level radioactive waste, power reactor-related 
GTCC waste, and other radioactive materials associated with the storage 
in a monitored retrievable storage installation (MRS), and the terms and 
conditions under which the Commission will issue such licenses.
    (d) As provided in part 76 of this chapter, the regulations of this 
part establish procedures and criteria for physical security and 
material control and accounting for the issuance of a certificate of 
compliance or the approval of a compliance plan.
    (e) As provided in the Atomic Energy Act of 1954, as amended, the 
regulations in this part establish requirements, procedures, and 
criteria for the issuance of licenses to uranium enrichment facilities.

[21 FR 764, Feb. 3, 1956, as amended at 32 FR 4056, Mar. 15, 1967; 40 FR 
8791, Mar. 3, 1975; 43 FR 6924, Feb. 17, 1978; 45 FR 74712, Nov. 12, 
1980; 53 FR 31682, Aug. 19, 1988; 59 FR 48960, Sept. 23, 1994; 62 FR 
6669, Feb. 12, 1997; 66 FR 51838, Oct. 11, 2001]



Sec. 70.2  Scope.

    Except as provided in Sec. Sec. 70.11 to 70.13, inclusive, the 
regulations in this part apply to all persons in the United States. This 
part also gives notice to all persons who knowingly provide to any 
licensee, applicant, contractor, or subcontractor, components, 
equipment, materials, or other goods or services, that relate to a 
licensee's or applicant's activities subject to this part, that they may 
be individually subject to NRC enforcement action for violation of Sec. 
70.10.

[63 FR 1898, Jan. 13, 1998]



Sec. 70.3  License requirements.

    No person subject to the regulations in this part shall receive 
title to, own, acquire, deliver, receive, possess, use, or transfer 
special nuclear material except as authorized in a license issued by the 
Commission pursuant to these regulations.

[32 FR 2562, Feb. 7, 1967, as amended at 43 FR 6924, Feb. 17, 1978]



Sec. 70.4  Definitions.

    Act means the Atomic Energy Act of 1954 (68 Stat 919), including any 
amendments thereto;
    Acute, as used in this part, means a single radiation dose or 
chemical exposure event or multiple radiation dose or chemical exposure 
events occurring within a short time (24 hours or less).
    Agreement State as designated in part 150 of this chapter means any 
State with which the Commission has entered into an effective agreement 
under subsection 274b. of the Act. Non-agreement State means any other 
State.
    Alert means events may occur, are in progress, or have occurred that 
could lead to a release of radioactive material[s] but that the release 
is not expected to require a response by an offsite response 
organization to protect persons offsite.
    Atomic energy means all forms of energy released in the course of 
nuclear fission or nuclear transformation;
    Atomic weapon means any device utilizing atomic energy, exclusive of 
the means for transporting or propelling the device (where such means is 
a separable and divisible part of the device), the principal purpose of 
which is for use as, or for development of, a weapon, a weapon 
prototype, or a weapon test device;

[[Page 291]]

    Available and reliable to perform their function when needed, as 
used in subpart H of this part, means that, based on the analyzed, 
credible conditions in the integrated safety analysis, items relied on 
for safety will perform their intended safety function when needed, and 
management measures will be implemented that ensure compliance with the 
performance requirements of Sec. 70.61 of this part, considering 
factors such as necessary maintenance, operating limits, common-cause 
failures, and the likelihood and consequences of failure or degradation 
of the items and measures.
    Commencement of construction means taking any action defined as 
``construction'' or any other activity at the site of a facility subject 
to the regulations in this part that has a reasonable nexus to:
    (1) Radiological health and safety; or
    (2) Common defense and security.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives;
    Common defense and security means the common defense and security of 
the United States;
    Configuration management (CM) means a management measure that 
provides oversight and control of design information, safety 
information, and records of modifications (both temporary and permanent) 
that might impact the ability of items relied on for safety to perform 
their functions when needed.
    Construction means the installation of foundations, or in-place 
assembly, erection, fabrication, or testing for any structure, system, 
or component of a facility or activity subject to the regulations in 
this part that are related to radiological safety or security. The term 
``construction'' does not include:
    (1) Changes for temporary use of the land for public recreational 
purposes;
    (2) Site exploration, including necessary borings to determine 
foundation conditions or other preconstruction monitoring to establish 
background information related to the suitability of the site, the 
environmental impacts of construction or operation, or the protection of 
environmental values;
    (3) Preparation of the site for construction of the facility, 
including clearing of the site, grading, installation of drainage, 
erosion and other environmental mitigation measures, and construction of 
temporary roads and borrow areas;
    (4) Erection of fences and other access control measures that are 
not related to the safe use of, or security of, radiological materials 
subject to this part;
    (5) Excavation;
    (6) Erection of support buildings (e.g., construction equipment 
storage sheds, warehouse and shop facilities, utilities, concrete mixing 
plants, docking and unloading facilities, and office buildings) for use 
in connection with the construction of the facility;
    (7) Building of service facilities (e.g., paved roads, parking lots, 
railroad spurs, exterior utility and lighting systems, potable water 
systems, sanitary sewerage treatment facilities, and transmission 
lines);
    (8) Procurement or fabrication of components or portions of the 
proposed facility occurring at other than the final, in-place location 
at the facility; or
    (9) Taking any other action that has no reasonable nexus to:
    (i) Radiological health and safety, or
    (ii) Common defense and security.
    Contiguous sites means licensee controlled locations, deemed by the 
Commission to be in close enough proximity to each other, that the 
special nuclear material must be considered in the aggregate for the 
purpose of physical protection.
    Corporation means the United States Enrichment Corporation (USEC), 
or its successor, a Corporation that is authorized by statute to lease 
the gaseous diffusion enrichment plants in Paducah, Kentucky, and 
Piketon, Ohio, from the Department of Energy, or any person authorized 
to operate one or both of the gaseous diffusion plants, or other 
facilities, pursuant to a plan for the privatization of USEC that is 
approved by the President.
    Critical mass of special nuclear material (SNM), as used in Subpart 
H, means special nuclear material in a quantity exceeding 700 grams of 
contained uranium-235; 520 grams of uranium-233; 450

[[Page 292]]

grams of plutonium; 1500 grams of contained uranium-235, if no uranium 
enriched to more than 4 percent by weight of uranium-235 is present; 450 
grams of any combination thereof; or one-half such quantities if massive 
moderators or reflectors made of graphite, heavy water, or beryllium may 
be present.
    Decommission means to remove a facility or site safely from service 
and reduce residual radioactivity to a level that permits--
    (1) Release of the property for unrestricted use and termination of 
the license; or
    (2) Release of the property under restricted conditions and 
termination of the license.
    Department and Department of Energy means the Department of Energy 
Organization Act (Pub. L. 95-91, 91 Stat. 565, 42 U.S.C. 7101 et seq.), 
to the extent that the Department, or its duly authorized 
representatives, exercises functions formerly vested in the U.S. Atomic 
Energy Commission, its Chairman, members, officers and components and 
transferred to the U.S. Energy Research and Development Administration 
and to the Administrator thereof pursuant to sections 104(b), (c) and 
(d) of the Energy Reorganization Act of 1974 (Pub. L. 93-438, 88 Stat. 
1233 at 1237, 42 U.S.C. 5814) and retransferred to the Secretary of 
Energy pursuant to section 301(a) of the Department of Energy 
Organization Act (Pub. L. 95-91, 91 Stat. 565 at 577-578, 42 U.S.C. 
7151).
    Double contingency principle means that process designs should 
incorporate sufficient factors of safety to require at least two 
unlikely, independent, and concurrent changes in process conditions 
before a criticality accident is possible.
    Effective dose equivalent means the sum of the products of the dose 
equivalent to the body organ or tissue and the weighting factors 
applicable to each of the body organs or tissues that are irradiated. 
Weighting factors are: 0.25 for gonads, 0.15 for breast, 0.12 for red 
bone marrow, 0.12 for lungs, 0.03 for thyroid, 0.03 for bone surface, 
and 0.06 for each of the other five organs receiving the highest dose 
equivalent.
    Effective kilograms of special nuclear material means: (1) For 
plutonium and uranium-233 their weight in kilograms; (2) For uranium 
with an enrichment in the isotope U-235 of 0.01 (1%) and above, its 
element weight in kilograms multiplied by the square of its enrichment 
expressed as a decimal weight fraction; and (3) For uranium with an 
enrichment in the isotope U-235 below 0.01 (1%), by its element weight 
in kilograms multiplied by 0.0001.
    Formula quantity means strategic special nuclear material in any 
combination in a quantity of 5000 grams or more computed by the formula, 
grams = (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). 
This class of material is sometimes referred to as a Category I quantity 
of material.
    Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the Government;
    Hazardous chemicals produced from licensed materials means 
substances having licensed material as precursor compound(s) or 
substances that physically or chemically interact with licensed 
materials; and that are toxic, explosive, flammable, corrosive, or 
reactive to the extent that they can endanger life or health if not 
adequately controlled. These include substances commingled with licensed 
material, and include substances such as hydrogen fluoride that is 
produced by the reaction of uranium hexafluoride and water, but do not 
include substances prior to process addition to licensed material or 
after process separation from licensed material.
    Integrated safety analysis (ISA) means a systematic analysis to 
identify facility and external hazards and their potential for 
initiating accident sequences, the potential accident sequences, their 
likelihood and consequences, and the items relied on for safety. As used 
here, integrated means joint consideration of, and protection from, all 
relevant hazards, including radiological, nuclear criticality, fire, and 
chemical. However, with respect to compliance with the regulations of 
this

[[Page 293]]

part, the NRC requirement is limited to consideration of the effects of 
all relevant hazards on radiological safety, prevention of nuclear 
criticality accidents, or chemical hazards directly associated with NRC 
licensed radioactive material. An ISA can be performed process by 
process, but all processes must be integrated, and process interactions 
considered.
    Integrated safety analysis summary means a document or documents 
submitted with the license application, license amendment application, 
license renewal application, or pursuant to Sec. 70.62(c)(3)(ii) that 
provides a synopsis of the results of the integrated safety analysis and 
contains the information specified in Sec. 70.65(b). The ISA Summary 
can be submitted as one document for the entire facility, or as multiple 
documents that cover all portions and processes of the facility.
    Items relied on for safety mean structures, systems, equipment, 
components, and activities of personnel that are relied on to prevent 
potential accidents at a facility that could exceed the performance 
requirements in Sec. 70.61 or to mitigate their potential consequences. 
This does not limit the licensee from identifying additional structures, 
systems, equipment, components, or activities of personnel (i.e., beyond 
those in the minimum set necessary for compliance with the performance 
requirements) as items relied on for safety.
    License, except where otherwise specified, means a license issued 
pursuant to the regulations in this part;
    Management measures mean the functions performed by the licensee, 
generally on a continuing basis, that are applied to items relied on for 
safety, to ensure the items are available and reliable to perform their 
functions when needed. Management measures include configuration 
management, maintenance, training and qualifications, procedures, audits 
and assessments, incident investigations, records management, and other 
quality assurance elements.
    Person means (1) any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
Government agency other than the Commission or the Department, except 
that the Department shall be considered a person within the meaning of 
the regulations in this part to the extent that its facilities and 
activities are subject to the licensing and related regulatory authority 
of the Commission pursuant to section 202 of the Energy Reorganization 
Act of 1974 (88 Stat. 1244), any State or any political subdivision of 
or any political entity within a State, any foreign government or nation 
or any political subdivision of any such government or nation, or other 
entity; and (2) any legal successor, representative, agent, or agency of 
the foregoing;
    Plutonium processing and fuel fabrication plant means a plant in 
which the following operations or activities are conducted: (1) 
Operations for manufacture of reactor fuel containing plutonium 
including any of the following: (i) Preparation of fuel material; (ii) 
formation of fuel material into desired shapes; (iii) application of 
protective cladding; (iv) recovery of scrap material; and (v) storage 
associated with such operations; or (2) Research and development 
activities involving any of the operations described in paragraph (1) of 
this definition except for research and development activities utilizing 
unsubstantial amounts of plutonium.
    Principal activities, as used in this part, means activities 
authorized by the license which are essential to achieving the 
purpose(s) for which the license was issued or amended. Storage during 
which no licensed material is accessed for use or disposal and 
activities incidental to decontamination or decommissioning are not 
principal activities.
    Produce, when used in relation to special nuclear material, means 
(1) to manufacture, make, produce, or refine special nuclear material; 
(2) to separate special nuclear material from other substances in which 
such material may be contained; or (3) to make or to produce new special 
nuclear material;
    Research and development means (1) theoretical analysis, 
exploration, or experimentation; or (2) the extension of investigative 
findings and theories of a scientific or technical nature into practical 
application for experimental and demonstration purposes, including

[[Page 294]]

the experimental production and testing of models, devices, equipment, 
materials, and processes;
    Restricted Data means all data concerning (1) design, manufacture or 
utilization of atomic weapons; (2) the production of special nuclear 
material; or (3) the use of special nuclear material in the production 
of energy, but shall not include data declassified or removed from the 
Restricted Data category pursuant to section 142 of the Act;
    Sealed source means any special nuclear material that is encased in 
a capsule designed to prevent leakage or escape of the special nuclear 
material.
    Site Area emergency means events may occur, are in progress, or have 
occurred that could lead to a significant release of radioactive 
material and that could require a response by offsite response 
organizations to protect persons offsite.
    Source material means source material as defined in section 11z. of 
the Act and in the regulations contained in part 40 of this chapter;
    Special nuclear material means (1) plutonium, uranium 233, uranium 
enriched in the isotope 233 or in the isotope 235, and any other 
material which the Commission, pursuant to the provisions of section 51 
of the act, determines to be special nuclear material, but does not 
include source material; or (2) any material artificially enriched by 
any of the foregoing but does not include source material;
    Special nuclear material of low strategic significance means:
    (1) Less than an amount of special nuclear material of moderate 
strategic significance as defined in paragraph (1) of the definition of 
strategic nuclear material of moderate strategic significance in this 
section, but more than 15 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in U-235 isotope) or 15 grams of uranium-
233 or 15 grams of plutonium or the combination of 15 grams when 
computed by the equation, grams = (grams contained U-235) + (grams 
plutonium) + (grams U-233); or
    (2) Less than 10,000 grams but more than 1,000 grams of uranium-235 
(contained in uranium enriched to 10 percent or more but less than 20 
percent in the U-235 isotope); or
    (3) 10,000 grams or more of uranium-235 (contained in uranium 
enriched above natural but less than 10 percent in the U-235 isotope).

This class of material is sometimes referred to as a Category III 
quantity of material.
    Special nuclear material of moderate strategic significance means:
    (1) Less than a formula quantity of strategic special nuclear 
material but more than 1,000 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in the U-235 isotope) or more than 500 
grams of uranium-233 or plutonium, or in a combined quantity of more 
than 1,000 grams when computed by the equation, grams = (grams contained 
U-235) + 2 (grams U-233 + grams plutonium); or
    (2) 10,000 grams or more of uranium-235 (contained in uranium 
enriched to 10 percent or more but less than 20 percent in the U-235 
isotope).

This class of material is sometimes referred to as a Category II 
quantity of material.
    Special nuclear material scrap means the various forms of special 
nuclear material generated during chemical and mechanical processing, 
other than recycle material and normal process intermediates, which are 
unsuitable for use in their present form, but all or part of which will 
be used after further processing.
    Strategic special nuclear material means uranium-235 (contained in 
uranium enriched to 20 percent or more in the U\235\ isotope), uranium-
233, or plutonium.
    Transient shipment means a shipment of nuclear material, originating 
and terminating in foreign countries, on a vessel or aircraft which 
stops at a United States port.
    Unacceptable performance deficiencies mean deficiencies in the items 
relied on for safety or the management measures that need to be 
corrected to ensure an adequate level of protection as defined in 10 CFR 
70.61(b), (c), or (d).
    United States, when used in a geographical sense, includes Puerto 
Rico and all territories and possessions of the United States.
    Uranium enrichment facility means:

[[Page 295]]

    (1) Any facility used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or
    (2) Any equipment or device, or important component part especially 
designed for such equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.
    Worker, when used in Subpart H of this Part, means an individual who 
receives an occupational dose as defined in 10 CFR 20.1003.

[21 FR 764, Feb. 3, 1956]

    Editorial Note: For Federal Register citations affecting Sec. 70.4, 
see the List of CFR Sections Affected, which appears in the Finding Aids 
section of the printed volume and at www.fdsys.gov.



Sec. 70.5  Communications.

    (a) Unless otherwise specified or covered under the regional 
licensing program as provided in paragraph (b) of this section, any 
communication or report concerning the regulations in this part and any 
application filed under these regulations may be submitted to the 
Commission as follows:
    (1) By mail addressed to: ATTN: Document Control Desk, Director, 
Office of Nuclear Material Safety and Safeguards or Director, Division 
of Security Policy, Office of Nuclear Security and Incident Response, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
    (2) By hand delivery to the Director, Office of Nuclear Material 
Safety and Safeguards or Director, Division of Security Policy, Office 
of Nuclear Security and Incident Response at the NRC's offices at 11555 
Rockville Pike, Rockville, Maryland.
    (3) Where practicable, by electronic submission, for example, via 
Electronic Information Exchange, and CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.
    (4) Classified communications shall be transmitted to the NRC 
Headquarters' classified mailing address as specified in appendix A to 
part 73 of this chapter or delivered by hand in accordance with 
paragraph (a)(2) of this section.
    (b) The Commission has delegated to the four Regional Administrators 
licensing authority for selected parts of its decentralized licensing 
program for nuclear materials as described in paragraph (b)(1) of this 
section. Any communication, report, or application covered under this 
licensing program must be submitted to the appropriate Regional 
Administrator. The Administrators' jurisdictions and mailing addresses 
are listed in paragraph (b)(2) of this section.
    (1) The delegated licensing program includes authority to issue, 
renew, amend, cancel, modify, suspend, or revoke licenses for nuclear 
materials issued pursuant to 10 CFR parts 30 through 36, 39, 40, and 70 
to all persons for academic, medical, and industrial uses, with the 
following exceptions:
    (i) Activities in the fuel cycle and special nuclear material in 
quantities sufficient to constitute a critical mass in any room or area. 
This exception does not apply to license modifications relating to 
termination of special nuclear material licenses that authorize 
possession of larger quantities when the case is referred for action 
from NRC's Headquarters to the Regional Administrators.
    (ii) Health and safety design review of sealed sources and devices 
and approval, for licensing purposes, of sealed sources and devices.
    (iii) Processing of source material for extracting of metallic 
compounds (including Zirconium, Hafnium, Tantalum, Titanium, Niobium, 
etc.).
    (iv) Distribution of products containing radioactive material under 
Sec. Sec. 32.11 through 32.30 and 40.52 of this

[[Page 296]]

chapter to persons exempt from licensing requirements.
    (v) New uses or techniques for use of byproduct, source, or special 
nuclear material.
    (vi) Reviews pursuant to Sec. 70.32(c).
    (vii) Uranium enrichment facilities.
    (2) Submissions--(i) Region I. The regional licensing program 
involves all Federal facilities in the region and non-Federal licensees 
in the following Region I non-Agreement States and the District of 
Columbia: Connecticut, Delaware, and Vermont. All mailed or hand-
delivered inquiries, communications, and applications for a new license 
or an amendment or renewal of an existing license specified in paragraph 
(b)(1) of this section must use the following address: U.S. Nuclear 
Regulatory Commission, Region I, Nuclear Material Section B, 2100 
Renaissance Boulevard, Suite 100, King of Prussia, PA 19406-2713; where 
email is appropriate it should be addressed to 
[email protected].
    (ii) Region II. The regional licensing program involves all Federal 
facilities in the region and non-Federal licensees in the following 
Region II non-Agreement States and territories: West Virginia, Puerto 
Rico, and the Virgin Islands. All mailed or hand-delivered inquiries, 
communications, and applications for a new license or an amendment, 
renewal, or termination request of an existing license specified in 
paragraph (b)(1) of this section must use the following address: U.S. 
Nuclear Regulatory Commission, Region I, Nuclear Material Section B, 475 
Allendale Road, King of Prussia, PA 19406-1415; where e-mail is 
appropriate it should be addressed to 
[email protected].
    (iii) Region III. (A) The regional licensing program for mining and 
milling involves all Federal facilities in the region, and non-Federal 
licensees in the Region III non-Agreement States of Indiana, Michigan, 
Missouri and Region III Agreement States of Minnesota, Wisconsin, and 
Iowa. All mailed or hand-delivered inquiries, communications, and 
applications for a new license or an amendment, renewal, or termination 
request of an existing license specified in paragraph (b)(1) of this 
section must use the following address: U.S. Nuclear Regulatory 
Commission, Region III, Material Licensing Section, 2443 Warrenville 
Road, Suite 210, Lisle, IL 60532-4352; where e-mail is appropriate it 
should be addressed to [email protected].
    (B) Otherwise, the regional licensing program involves all Federal 
facilities in the region and non-Federal licensees in the following 
Region III non-Agreement States: Indiana, Michigan, and Missouri. All 
mailed or hand-delivered inquiries, communications, and applications for 
a new license or an amendment, or renewal of an existing license 
specified in paragraph (b)(1) of this section must use the following 
address: U.S. Nuclear Regulatory Commission, Region III, Material 
Licensing Section, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-
4352; where e-mail is appropriate it should be addressed to 
[email protected]. Outside of this jurisdiction, 
concerning the licensing program involving mining and milling, the 
Agreement States of Illinois and Ohio should be contacted.
    (iv) Region IV. (A) The regional licensing program for mining and 
milling involves all Federal facilities in the region, and non-Federal 
licensees in the Region IV non-Agreement States and territory of Alaska, 
Hawaii, Idaho, Montana, South Dakota, Wyoming and Guam and Region IV 
Agreement States of Oregon, California, Nevada, New Mexico, Louisiana, 
Mississippi, Arkansas, Oklahoma, Kansas, Nebraska, and North Dakota. All 
mailed or hand-delivered inquiries, communications, and applications for 
a new license or an amendment or renewal of an existing license 
specified in paragraph (b)(1) of this section must use the following 
address: U.S. Nuclear Regulatory Commission, Region IV, Division of 
Nuclear Materials Safety, 1600 E. Lamar Blvd., Arlington, TX 76011-4511; 
where email is appropriate, it should be addressed to 
[email protected].
    (B) Otherwise, the regional licensing program involves all Federal 
facilities in the region and non-Federal licensees in the following 
Region IV non-Agreement States and territory: Alaska, Hawaii, Idaho, 
Montana, South Dakota, Wyoming, and Guam. All mailed or

[[Page 297]]

hand-delivered inquiries, communications, and applications for a new 
license or an amendment or renewal of an existing license specified in 
paragraph (b)(1) of this section must use the following address: U.S. 
Nuclear Regulatory Commission, Region IV, Division of Nuclear Materials 
Safety, 1600 E. Lamar Blvd., Arlington, TX 76011-4511; where email is 
appropriate, it should be addressed to [email protected]. 
Outside of this jurisdiction, concerning the licensing program involving 
mining and milling, the Agreement States of Colorado, Utah, Texas and 
Washington should be contacted.

[48 FR 16032, Apr. 14, 1983]

    Editorial Note: For Federal Register citations affecting Sec. 70.5, 
see the List of CFR Sections Affected, which appears in the Finding Aids 
section of the printed volume and at www.fdsys.gov.



Sec. 70.6  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 70.7  Employee protection.

    (a) Discrimination by a Commission licensee, an applicant for a 
Commission license, or a contractor or subcontractor of a Commission 
licensee or applicant against an employee for engaging in certain 
protected activities is prohibited. Discrimination includes discharge 
and other actions that relate to compensation, terms, conditions, or 
privileges of employment. The protected activities are established in 
section 211 of the Energy Reorganization Act of 1974, as amended, and in 
general are related to the administration or enforcement of a 
requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) introductory text of this section or possible violations of 
requirements imposed under either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) introductory text or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) introductory 
text.
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraphs (a), (e), or (f) of this section by a 
Commission licensee, an applicant for a Commission license, or a 
contractor or subcontractor of a Commission licensee or applicant may be 
grounds for--

[[Page 298]]

    (1) Denial, revocation, or suspension of the license.
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant.
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each specific licensee, each applicant for a specific 
license, and each general licensee subject to part 19 shall prominently 
post the revision of NRC Form 3, ``Notice to Employees,'' referenced in 
10 CFR 19.11(c).
    (2) The posting of NRC Form 3 must be at locations sufficient to 
permit employees protected by this section to observe a copy on the way 
to or from their place of work. Premises must be posted not later than 
30 days after an application is docketed and remain posted while the 
application is pending before the Commission, during the term of the 
license, and for 30 days following license termination.
    (3) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[58 FR 52413, Oct. 8, 1993, as amended at 60 FR 24552, May 9, 1995; 61 
FR 6765, Feb. 22, 1996; 68 FR 58816, Oct. 10, 2003; 72 FR 63974, Nov. 
14, 2007; 73 FR 30459, May 28, 2008; 79 FR 66605, Nov. 10, 2014]



Sec. 70.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the office of 
Management and Budget (OMB) for approval as required by the Paperwork 
reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0009.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 70.9, 70.17, 70.19, 70.20a, 70.20b, 
70.21, 70.22, 70.24, 70.25, 70.32, 70.33, 70.34, 70.38, 70.39, 70.42, 
70.50, 70.51, 70.52, 70.59, 70.61, 70.62, 70.64, 70.65, 70.72, 70.73, 
70.74, and Appendix A.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. These information collection requirements 
and the control numbers under which they are approved are as follows:
    (1) In Sec. 70.21(g), Form N-71 and associated forms are approved 
under control number 3150-0056.
    (2) In Sec. 70.38, NRC form 314 is approved under control number 
3150-0028.
    (3) In Sec. 70.21(g), DOC/NRC Forms AP-1, AP-A, and associated 
forms are approved under control number 0694-0135.

[49 FR 19628, May 9, 1984, as amended at 52 FR 19305, May 22, 1987; 56 
FR 40769, Aug. 16, 1991; 57 FR 18392, Apr. 30, 1992; 58 FR 39634, July 
26, 1993; 62 FR 52189, Oct. 6, 1997; 65 FR 56225, Sept. 18, 2000; 67 FR 
78142, Dec. 23, 2003; 73 FR 78606, Dec. 23, 2008]

[[Page 299]]



Sec. 70.9  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
license or by a licensee or information required by statute or by the 
Commission's regulations, orders, or license conditions to be maintained 
by the applicant or the licensee shall be complete and accurate in all 
material respects.
    (b) Each applicant or licensee shall notify the Commission of 
information identified by the applicant or licensee as having for the 
regulated activity a significant implication for public health and 
safety or common defense and security. An applicant or licensee violates 
this paragraph only if the applicant or licensee fails to notify the 
Commission of information that the applicant or licensee has identified 
as having a significant implication for public health and safety or 
common defense and security. Notification shall be provided to the 
Administrator of the appropriate Regional Office within two working days 
of identifying the information. This requirement is not applicable to 
information which is already required to be provided to the Commission 
by other reporting or updating requirements.

[52 FR 49373, Dec. 31, 1987]



Sec. 70.10  Deliberate misconduct.

    (a) Any licensee, applicant for a license, employee of a licensee or 
applicant; or any contractor (including a supplier or consultant), 
subcontractor, employee of a contractor or subcontractor of any licensee 
or applicant for a license, who knowingly provides to any licensee, 
applicant, contractor, or subcontractor, any components, equipment, 
materials, or other goods or services that relate to a licensee's or 
applicant's activities in this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee or applicant to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation of 
any license issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, an applicant, or a 
licensee's or applicant's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For the purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee or applicant to be in violation of any 
rule, regulation, or order; or any term, condition, or limitation, of 
any license issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
applicant, contractor, or subcontractor.

[63 FR 1899, Jan. 13, 1998]



                          Subpart B_Exemptions



Sec. 70.11  Persons using special nuclear material under certain
Department of Energy and Nuclear Regulatory Commission contracts.

    Except to the extent that Department facilities or activities of the 
types subject to licensing pursuant to section 202 of the Energy 
Reorganization Act of 1974 are involved, any prime contractor of the 
Department is exempt from the requirements for a license set forth in 
section 53 of the Act and from the regulations in this part to the 
extent that such contractor, under his prime contract with the 
Department receives title to, owns, acquires, delivers, receives, 
possesses, uses, or transfers special nuclear material for:
    (a) The performance of work for the Department at a United States 
Government-owned or controlled site, including the transportation of 
special nuclear material to or from such site and the performance of 
contract services during temporary interruptions of such transportation; 
(b) research in, or development, manufacture, storage, testing or 
transportation of, atomic weapons or components thereof; or (c) the use 
or operation of nuclear reactors or other nuclear devices in a United

[[Page 300]]

States Government-owned vehicle or vessel. In addition to the foregoing 
exemptions, and subject to the requirement for licensing of Department 
facilities and activities pursuant to section 202 of the Energy 
Reorganization Act of 1974, any prime contractor or subcontractor of the 
Department or the Commission is exempt from the requirements for a 
license set forth in section 53 of the Act and from the regulations in 
this part to the extent that such prime contractor or subcontractor 
receives title to, owns, acquires, delivers, receives, possesses, uses, 
or transfers special nuclear material under his prime contract or 
subcontract when the Commission determines that the exemption of the 
prime contractor or subcontractor is authorized by law; and that, under 
the terms of the contract or subcontract there is adequate assurance 
that the work thereunder can be accomplished without undue risk to the 
public health and safety.

[40 FR 14085, Mar. 28, 1975; 40 FR 16047, Apr. 9, 1975, as amended at 43 
FR 6924, Feb. 17, 1978; 65 FR 54950, Sept. 12, 2000]



Sec. 70.12  Carriers.

    Common and contract carriers, freight forwarders, warehousemen, and 
the U.S. Postal Service are exempt from the regulations in this part to 
the extent that they transport special nuclear material in the regular 
course of carriage for another or storage incident thereto. This 
exemption does not apply to the storage in transit or transport of 
material by persons covered by the general license issued under Sec. 
70.20a and Sec. 70.20b.

[46 FR 12696, Feb. 18, 1981]



Sec. 70.13  Department of Defense.

    The regulations in this part do not apply to the Department of 
Defense to the extent that the Department receives, possesses and uses 
special nuclear material in accordance with the direction of the 
President pursuant to section 91 of the Act.



Sec. 70.14  Foreign military aircraft.

    The regulations in this part do not apply to persons who carry 
special nuclear material (other than plutonium) in aircraft of the armed 
forces of foreign nations subject to 49 U.S.C. 40103(d).

[71 FR 15012, Mar. 27, 2006]



Sec. 70.17  Specific exemptions.

    (a) The Commission may, upon application of any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
will not endanger life or property or the common defense and security 
and are otherwise in the public interest.
    (b) [Reserved]
    (c) The DOE is exempt from the requirements of the regulations in 
this part to the extent that its activities are subject to the 
requirements of part 60 or part 63 of this chapter.
    (d) Except as specifically provided in part 61 of this chapter, any 
licensee is exempt from the requirements of the regulations in this part 
to the extent that its activities are subject to the requirements of 
part 61 of this chapter.

[37 FR 5749, Mar. 21, 1972, as amended at 45 FR 65536, Oct. 3, 1980; 46 
FR 13987, Feb. 25, 1981; 47 FR 57481, Dec. 27, 1982; Redesignated at 65 
FR 56225, Sept. 18, 2000, as amended at 66 FR 55815, Nov. 2, 2001]



                       Subpart C_General Licenses



Sec. 70.18  Types of licenses.

    Licenses for special nuclear material are of two types: general and 
specific. Any general license provided in this part is effective without 
the filing of applications with the Commission or the issuance of 
licensing documents to particular persons. Specific licenses are issued 
to named persons upon applications filed pursuant to the regulations in 
this part.

[29 FR 5884, May 5, 1964]



Sec. 70.19  General license for calibration or reference sources.

    (a) A general license is hereby issued to those persons listed below 
to receive title to, own, acquire, deliver, receive, possess, use and 
transfer in accordance with the provisions of paragraphs (b) and (c) of 
this section, plutonium in the form of calibration or reference sources:

[[Page 301]]

    (1) Any person in a non-agreement State who holds a specific license 
issued by the Commission or the Atomic Energy Commission which 
authorizes him to receive, possess, use and transfer byproduct material, 
source material, or special nuclear material;
    (2) Any Government agency as defined in Sec. 70.4 that holds a 
specific license issued by the Commission that authorizes it to receive, 
possess, use, or transfer byproduct material, source material, or 
special nuclear material; and
    (3) Any person in an agreement State who holds a specific license 
issued by the Commission or the Atomic Energy Commission which 
authorizes him to receive, possess, use and transfer special nuclear 
material.
    (b) The general license in paragraph (a) of this section applies 
only to calibration or reference sources which have been manufactured or 
initially transferred in accordance with the specifications contained in 
a specific license issued pursuant to Sec. 70.39 or in accordance with 
the specifications contained in a specific license issued by an 
agreement State which authorizes manufacture of the sources for 
distribution to persons generally licensed by the agreement State.
    (c) The general license in paragraph (a) of this section is subject 
to the provisions of Sec. Sec. 70.32, 70.50, 70.55, 70.56, 70.91, 
70.81, and 70.82; the provisions of Sec. Sec. 74.11 and 74.19 of this 
chapter; and to the provisions of parts 19, 20, and 21 of this chapter. 
In addition, persons who receive title to own, acquire, deliver, 
receive, possess, use or transfer one or more calibration or reference 
sources under this general license:
    (1) Shall not possess at any one time, at any one location of 
storage or use, more than 5 microcuries of plutonium in such sources;
    (2) Shall not receive, possess, use or transfer such source unless 
the source, or the storage container, bears a label which includes the 
following statement or a substantially similar statement which contains 
the information called for in the following statement: \1\
---------------------------------------------------------------------------

    \1\ Sources generally licensed under this section prior to January 
19, 1975 may bear labels authorized by the regulations in effect on 
January 1, 1975.

    The receipt, possession, use and transfer of this source, Model ___, 
Serial No. ___, are subject to a general license and the regulations of 
the United States Nuclear Regulatory Commission or of a State with which 
the Commission has entered into an agreement for the exercise of 
regulatory authority. Do not remove this label.

 caution--radioactive material--this source contains plutonium. do not 
                touch radioactive portion of this source.

              (Name of Manufacturer or Initial Transferor)

    (3) Shall not transfer, abandon, or dispose of such source except by 
transfer to a person authorized by a license from the Commission or the 
Atomic Energy Commission or an Agreement State to receive the source.
    (4) Shall store such source, except when the source is being used, 
in a closed container adequately designed and constructed to contain 
plutonium which might otherwise escape during storage.
    (5) Shall not use such source for any purpose other than the 
calibration of radiation detectors or the standardization of other 
sources.
    (d) The general license in paragraph (a) of this section does not 
authorize the manufacture, import, or export of calibration or reference 
sources containing plutonium.

[29 FR 5884, May 5, 1964, as amended at 32 FR 8124, June 7, 1967; 38 FR 
22221, Aug. 17, 1973; 40 FR 8792, Mar. 3, 1975; 42 FR 28896, June 6, 
1977; 43 FR 6924, Feb. 17, 1978; 48 FR 32329, July 15, 1983; 56 FR 
40769, Aug. 16, 1991; 57 FR 33428, July 29, 1992; 67 FR 78142, Dec. 23, 
2002; 72 FR 35145, June 27, 2007]



Sec. 70.20  General license to own special nuclear material.

    A general license is hereby issued to receive title to and own 
special nuclear material without regard to quantity. Notwithstanding any 
other provision of this chapter, a general licensee under this section 
is not authorized to acquire, deliver, receive, possess, use, transfer, 
import, or export special nuclear material, except as authorized in a 
specific license.

[33 FR 9810, July 9, 1968]

[[Page 302]]



Sec. 70.20a  General license to possess special nuclear material
for transport.

    (a) A general license is issued to any person to possess formula 
quantities of strategic special nuclear material of the types and 
quantities subject to the requirements of Sec. Sec. 73.20, 73.25, 73.26 
and 73.27 of this chapter, and irradiated reactor fuel containing 
material of the types and quantities subject to the requirements of 
Sec. 73.37 of this chapter, in the regular course of carriage for 
another or storage incident. Carriers generally licensed under Sec. 
70.20b are exempt from the requirements of this section. Carriers of 
irradiated reactor fuel for the United States Department of Energy are 
also exempt from the requirements of this section. The general license 
is subject to the applicable provisions of Sec. Sec. 70.7 (a) through 
(e), 70.32 (a) and (b), and Sec. Sec. 70.42, 70.52, 70.55, 70.91, 
70.81, 70.82 and 10 CFR 74.11.
    (b) Notwithstanding any other provision of this chapter, the general 
license issued under this section does not authorize any person to 
conduct any activity that would be authorized by a license issued 
pursuant to parts 30 through 36, 39, 40, 50, 72, 110, or other sections 
of this part.
    (c) Notwithstanding any other provision of this chapter, the duties 
of a general licensee under this section while in possession of formula 
quantities of strategic special nuclear material or irradiated reactor 
fuel in the regular course of carriage for another or storage incident 
thereto shall be limited to providing for the physical protection of 
such material against theft or sabotage. Unless otherwise provided by 
this section, a general license under this section is not subject to the 
requirements of parts 19, 20, 70 and 73.
    (d) Any person who possesses formula quantities of strategic special 
nuclear material under this general license:
    (1) Shall have submitted and received approval of a transportation 
security plan. The security plan shall outline the procedures that will 
be used to meet the requirements of Sec. Sec. 73.20, 73.25, 73.26, 
73.27 and 73.70(g) of this chapter including a plan for the selection, 
qualification, and training of armed escorts, or the specification and 
design of a specially designed truck or trailer as appropriate.
    (2) Shall assure that the transportation is in accordance with the 
applicable physical protection requirements of Sec. Sec. 73.20, 73.25, 
73.26, 73.27 and 73.70(g) of this chapter and the applicable approved 
transportation security plan.
    (3) Shall be subject to part 26 and Sec. 73.80 of this chapter.
    (e) Any person who possesses irradiated reactor fuel under this 
general license shall:
    (1) Assure or receive certification from the shipper that the 
transportation is in accordance with the applicable physical protection 
requirements of Sec. 73.37 of this chapter; and
    (2) Comply with the reporting requirements of Sec. 73.71 of this 
chapter.

[44 FR 26851, May 8, 1979, as amended at 44 FR 68186, Nov. 28, 1979; 46 
FR 12696, Feb. 18, 1981; 47 FR 30458, July 14, 1982; 53 FR 31682, Aug. 
19, 1988; 58 FR 7737, Feb. 9, 1993; 58 FR 31471, June 3, 1993; 67 FR 
78142, Dec. 23, 2002; 72 FR 35145, June 27, 2007]



Sec. 70.20b  General license for carriers of transient shipments of
formula quantities of strategic special nuclear material, special
nuclear material of moderate strategic significance, special nuclear
material of low strategic significance, and irradiated reactor fuel.

    (a) A general license is hereby issued to any person to possess 
transient shipments of the following kinds and quantities of special 
nuclear material:
    (1) A formula quantity of special nuclear material of the types and 
quantities subject to the requirements of Sec. Sec. 73.20, 73.25, 
73.26, and 73.27 of this chapter.
    (2) Special nuclear material of moderate and low strategic 
significance of the types and quantities subject to the requirements of 
Sec. 73.67 of this chapter.
    (3) Irradiated reactor fuel of the type and quantity subject to the 
requirements of Sec. 73.37 of this chapter.
    (b) Persons generally licensed under this section are exempt from 
the requirements of parts 19 and 20 of this chapter and the requirements 
of this part, except Sec. Sec. 70.32 (a) and (b), 70.52, 70.55, 70.91, 
70.81, and 70.82.
    (c) Persons generally licensed under this section to possess a 
transient shipment of special nuclear material of the

[[Page 303]]

kind and quantity specified in paragraph (a)(1) of this section shall 
provide physical protection for that shipment in accordance with or 
equivalent to Sec. Sec. 73.20(a), 73.20(b), 73.25, and 73.71(b) of this 
chapter from the time a shipment enters a United States port until it 
exits that or another United States port.
    (d) Persons generally licensed under this section to possess a 
transient shipment of special nuclear material of moderate or low 
strategic significance of the kind and quantity specified in paragraph 
(a)(2) of this section shall provide physical protection for that 
shipment in accordance with or equivalent to Sec. 73.67 of this chapter 
and shall comply with the requirements of Sec. 73.71(b) of this 
chapter.
    (e) Persons generally licensed under this section to possess a 
transient shipment of irradiated reactor fuel of the kind and quantity 
specified in paragraph (a)(3) of this section shall provide physical 
protection for that shipment in accordance with or equivalent to Sec. 
73.37 of this chapter and shall comply with the requirements of Sec. 
73.71(b) of this chapter.
    (f)(1) Persons generally licensed under this section, who plan to 
carry transient shipments with scheduled stops at United States ports, 
shall notify in writing the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, using an appropriate 
method listed in Sec. 70.5(a). Classified notifications shall be sent 
to the NRC headquarters classified mailing address listed in appendix A 
to part 73 of this chapter.
    (2) A person generally licensed under this section shall assure 
that:
    (i) The notification will be received at least 10 days before 
transport of the shipment commences at the shipping facility;
    (ii) The NRC Headquarters Operations Center shall be notified by 
telephone at least 2 days before commencement of the shipment at the 
numbers listed in appendix A to part 73 of this chapter. Classified 
notifications shall be made by secure telephone.
    (iii) The NRC Headquarters Operations Center shall be notified by 
telephone of schedule changes greater than 6 hours 
at the numbers listed in appendix A to part 73 of this chapter. 
Classified notifications shall be made by secure telephone.
    (3) Persons who are generally licensed under paragraph (a)(1) of 
this section must include the information listed in paragraphs (f)(3)(i) 
through (ix) of this section. Persons who are generally licensed under 
Sec. 70.20b(a)(2) and Sec. 70.20b(a)(3) must include the information 
listed in paragraphs (f)(3) (i) through (viii) of this section.
    (i) Location of all scheduled stops in United States territory;
    (ii) Arrival and departure times for all scheduled stops in United 
States territory;
    (iii) The type of transport vehicle;
    (iv) A physical description of the shipment (elements, isotopes, and 
enrichments);
    (v) The number and types of containers;
    (vi) The name and telephone number of the carrier's representative 
at each stopover location in United States territory;
    (vii) The estimated time and date that shipment will commence and 
that each country (other than the United States) along the route is 
scheduled to be entered;
    (viii) For shipments between countries that are not party to the 
Convention on the Physical Protection of Nuclear Material, provide 
assurances, as far as is practicable, that this nuclear material will be 
protected during international transport at levels described in Annex I 
to that Convention (see appendices E and F of part 73 of this chapter); 
and
    (ix) A physical protection plan for implementing the requirement of 
Sec. 70.20b(c), which will include the use of armed personnel to 
protect the shipment during the time the shipment is in a United States 
port.
    (g) Persons generally licensed under this section making unscheduled 
stops at United States ports, immediately after the decision to make an 
unscheduled stop, shall:
    (1) Provide to the Director, Division of Security Policy, Office of 
Security Policy and Incident Response, the information required under 
paragraph (f) of this section.

[[Page 304]]

    (2) In the case of persons generally licensed under paragraph (a)(1) 
of this section, arrange for local law enforcement authorities or 
trained and qualified private guards to protect the shipment during the 
stop.
    (3) In the case of persons generally licensed under paragraph (a)(2) 
of this section, arrange for the shipment to be protected as required in 
Sec. 73.67(e) of this chapter.
    (4) In the case of persons generally licensed under paragraph (a)(3) 
of this section, arrange for the shipment to be protected as required in 
Sec. 73.37(e) of this chapter.
    (5) Implement these arrangements within a reasonable time after the 
arrival of the shipment at a United States port to remain in effect 
until the shipment exits that or another United States port.

[52 FR 9652, Mar. 26, 1987, as amended at 60 FR 24552, May 9, 1995; 67 
FR 3585, Jan. 25, 2002; 68 FR 14529, Mar. 26, 2003; 68 FR 23575, May 5, 
2003; 68 FR 58817, Oct. 10, 2003; 72 FR 35145, June 27, 2007; 74 FR 
62683, Dec. 1, 2009]



                     Subpart D_License Applications



Sec. 70.21  Filing.

    (a)(1) A person may apply for a license to possess and use special 
nuclear material in a plutonium processing or fuel fabrication plant, or 
for a uranium enrichment facility license, by filing the application 
with the Director of the NRC's Office of Nuclear Material Safety and 
Safeguards in accordance with the instructions in Sec. 70.5(a). If the 
application is on paper or CD-ROM, only one copy need be provided. If 
the application is to be submitted electronically, see guidance for 
electronic submissions to the Commission.
    (2) A person may apply for any other license issued under this part, 
by filing the application in accordance with the instructions in Sec. 
70.5(a). If the application is on paper, only one copy need be provided. 
If the application is to be submitted electronically, see guidance for 
electronic submissions to the Commission.
    (3) Information contained in previous applications, statements, or 
reports filed with the Commission may be incorporated by reference if 
the references are clear and specific.
    (b) An application for license filed pursuant to the regulations in 
this part will be considered also as an application for licenses 
authorizing other activities for which licenses are required by the Act, 
provided the application specifies the additional activities for which 
licenses are requested and complies with regulations of the Commission 
as to applications for such licenses.
    (c) Any application which contains Restricted Data shall be prepared 
in such manner that all Restricted Data are separated from the 
unclassified information.
    (d) Applications and documents submitted to the Commission in 
connection with applications may be made available for public inspection 
in accordance with the provisions of the regulations contained in part 2 
of this chapter.
    (e) Each application for a special nuclear material license, other 
than a license exempted from part 170 of this chapter, shall be 
accompanied by the fee prescribed in Sec. 170.31 of this chapter. No 
fee will be required to accompany an application for renewal or 
amendment of a license, except as provided in Sec. 170.31 of this 
chapter.
    (f) An application for a license to possess and use special nuclear 
material for processing and fuel fabrication, scrap recovery or 
conversion of uranium hexafluoride, or for the conduct of any other 
activity which the Commission has determined pursuant to subpart A of 
part 51 of this chapter will significantly affect the quality of the 
environment shall be filed at least 9 months prior to commencement of 
construction of the plant or facility in which the activity will be 
conducted, and shall be accompanied by an Environmental Report required 
under subpart A of part 51 of this chapter.
    (g)(1) In response to a written request by the Commission, each 
applicant for a construction authorization or license and each recipient 
of a construction authorization or a license to possess and use special 
nuclear material shall submit facility information, as described in 
Sec. 75.10 of this chapter, on Form N-71 and associated forms and site 
information on DOC/NRC Form AP-A and associated forms;

[[Page 305]]

    (2) As required by the Additional Protocol, applicants and licensees 
specified in paragraph (a) of this section shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms; and
    (3) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA) and take other action as necessary to implement the 
US/IAEA Safeguards Agreement, as described in Part 75 of this chapter.
    (h) A license application for a uranium enrichment facility must be 
accompanied by an Environmental Report required under subpart A of part 
51 of this chapter.

[21 FR 764, Feb. 3, 1956, as amended at 23 FR 1122, Feb. 21, 1958; 31 FR 
4670, Mar. 19, 1966; 34 FR 19546, Dec. 11, 1969; 36 FR 146, Jan. 6, 
1971; 37 FR 5749, Mar. 21, 1972; 49 FR 9406, Mar. 12, 1984; 49 FR 19628, 
19632, May 9, 1984; 49 FR 21699, May 23, 1984; 57 FR 18392, Apr. 30, 
1992; 68 FR 58817, Oct. 10, 2003; 73 FR 78606, Dec. 23, 2008]



Sec. 70.22  Contents of applications.

    (a) Each application for a license shall contain the following 
information:
    (1) The full name, address, age (if an individual), and citizenship 
of the applicant and the names and addresses of three personal 
references. If the applicant is a corporation or other entity, it shall 
indicate the State where it was incorporated or organized, the location 
of the principal office, the names, addresses, and citizenship of its 
principal officers, and shall include information known to the applicant 
concerning the control or ownership, if any, exercised over the 
applicant by any alien, foreign corporation, or foreign government;
    (2) The activity for which the special nuclear material is 
requested, or in which special nuclear material will be produced, the 
place at which the activity is to be performed and the general plan for 
carrying out the activity;
    (3) The period of time for which the license is requested;
    (4) The name, amount, and specifications (including the chemical and 
physical form and, where applicable, isotopic content) of the special 
nuclear material the applicant proposes to use or produce;
    (5) [Reserved]
    (6) The technical qualifications, including training and experience 
of the applicant and members of his staff to engage in the proposed 
activities in accordance with the regulations in this chapter;
    (7) A description of equipment and facilities which will be used by 
the applicant to protect health and minimize danger to life or property 
(such as handling devices, working areas, shields, measuring and 
monitoring instruments, devices for the disposal of radioactive 
effluents and wastes, storage facilities, criticality accident alarm 
systems, etc.);
    (8) Proposed procedures to protect health and minimize danger to 
life or property (such as procedures to avoid accidental criticality, 
procedures for personnel monitoring and waste disposal, post-criticality 
accident emergency procedures, etc.).

    Note: Where the nature of the proposed activities is such as to 
require consideration of the applicant's financial qualifications to 
engage in the proposed activities in accordance with the regulations in 
this chapter, the Commission may request the applicant to submit 
information with respect to his financial qualifications.

    (9) As provided by Sec. 70.25, certain applications for specific 
licenses filed under this part must contain a proposed decommissioning 
funding plan or a certification of financial assurance for 
decommissioning. In the case of renewal applications submitted on or 
before July 27, 1990, this submittal may follow the renewal application 
but must be submitted on or before July 27, 1990.
    (b) Each application for a license to possess special nuclear 
material, to possess equipment capable of enriching uranium, to operate 
an uranium enrichment facility, to possess and use at any one time and 
location special nuclear material in a quantity exceeding one effective 
kilogram, except for applications for use as sealed sources and for 
those uses involved in the operation of a nuclear reactor licensed 
pursuant to part 50 of this chapter and those involved in a waste 
disposal operation, must contain a full description of the

[[Page 306]]

applicant's program for control and accounting of such special nuclear 
material or enrichment equipment that will be in the applicant's 
possession under license to show how compliance with the requirements of 
Sec. Sec. 74.31, 74.33, 74.41, or 74.51 of this chapter, as applicable, 
will be accomplished.
    (c) [Reserved]
    (d) The Commission may at any time after the filing of the original 
application, and before the expiration of the license, require further 
statements in order to enable the Commission to determine whether the 
application should be granted or denied or whether a license should be 
modified or revoked. All applications and statements shall be signed by 
the applicant or licensee or a corporate officer thereof.
    (e) Each application and statement shall contain complete and 
accurate disclosure as to all matters and things required to be 
disclosed.
    (f) Each application for a license to possess and use special 
nuclear material in a plutonium processing and fuel fabrication plant 
shall contain, in addition to the other information required by this 
section, a description of the plantsite, a description and safety 
assessment of the design bases of the principal structure, systems, and 
components of the plant, including provisions for protection against 
natural phenomena, and a description of the quality assurance program to 
be applied to the design, fabrication, construction, testing and 
operation of the structures, systems, and components of the plant. \2\
---------------------------------------------------------------------------

    \2\ The description of the quality assurance program should include 
a discussion of how the criteria in appendix B of part 50 of this 
chapter will be met.
---------------------------------------------------------------------------

    (g)(1) Each application for a license that would authorize the 
transport or delivery to a carrier for transport of special nuclear 
material in an amount specified in Sec. 73.1(b)(2) of this chapter must 
include (i) a description of the plan for physical protection of special 
nuclear material in transit in accordance with Sec. Sec. 73.20, 73.25, 
73.26, 73.27, and 73.67 (a), (e), and (g) for 10 kg or more of special 
nuclear material of low strategic significance, and Sec. 73.70(g) of 
this chapter including, as appropriate, a plan for the selection, 
qualification, and training of armed escorts, or the specification and 
design of a specially designed truck or trailer, and (ii) a licensee 
safeguards contingency plan or response procedures, as appropriate, for 
dealing with threats, thefts, and radiological sabotage relating to the 
special nuclear material in transit.
    (2) Each application for such a license involving formula quantities 
of strategic special nuclear material must include the first four 
categories of information contained in the applicant's safeguards 
contingency plan. (The first four categories of information, as set 
forth in appendix C to part 73 of this chapter, are Background, Generic 
Planning Base, Licensee Planning Base, and Responsibility Matrix. The 
fifth category of information, Procedures, does not have to be submitted 
for approval.)
    (3) The licensee shall retain this discription of the plan for 
physical protection of special nuclear material in transit and the 
safeguards contingency plan or safeguards response procedures and each 
change to the plan or procedures as a record for a period of three years 
following the date on which the licensee last possessed the appropriate 
type and quantity of special nuclear material requiring this record 
under each license.
    (h)(1) Each application for a license to possess or use, at any site 
or contiguous sites subject to licensee control, a formula quantity of 
strategic special nuclear material, as defined in Sec. 70.4, other than 
a license for possession or use of this material in the operation of a 
nuclear reactor licensed pursuant to part 50 of this chapter, must 
include a physical security plan. The plan must describe how the 
applicant will meet the applicable requirements of part 73 of this 
chapter in the conduct of the activity to be licensed, including the 
identification and description of jobs as required by 10 CFR 11.11(a). 
The plan must list tests, inspections, audits, and other means to be 
used to demonstrate compliance with the requirements of 10 CFR parts 11 
and 73, if applicable.
    (2) The licensee shall retain a copy of this physical security plan 
and each change to the plan as a record for a period of three years 
following the date on which the licensee last possessed

[[Page 307]]

the appropriate type and quantity of special nuclear material requiring 
this record under each license.
    (i)(1) Each application to possess enriched uranium or plutonium for 
which a criticality accident alarm system is required, uranium 
hexafluoride in excess of 50 kilograms in a single container or 1000 
kilograms total, or in excess of 2 curies of plutonium in unsealed form 
or on foils or plated sources, must contain either:
    (i) An evaluation showing that the maximum dose to a member of the 
public offsite due to a release of radioactive materials would not 
exceed 1 rem effective dose equivalent or an intake of 2 milligrams of 
soluble uranium, or
    (ii) An emergency plan for responding to the radiological hazards of 
an accidental release of special nuclear material and to any associated 
chemical hazards directly incident thereto.
    (2) One or more of the following factors may be used to support an 
evaluation submitted under paragraph (i)(1)(i) of this section:
    (i) The radioactive material is physically separated so that only a 
portion could be involved in an accident;
    (ii) All or part of the radioactive material is not subject to 
release during an accident or to criticality because of the way it is 
stored or packaged;
    (iii) In the case of fires or explosions, the release fraction would 
be lower than 0.001 due to the chemical or physical form of the 
material;
    (iv) The solubility of the material released would reduce the dose 
received;
    (v) The facility design or engineered safety features in the 
facility would cause the release fraction to be lower than 0.001;
    (vi) Operating restrictions or procedures would prevent a release 
large enough to cause a member of the public offsite to receive a dose 
exceeding 1 rem effective dose equivalent; or
    (vii) Other factors appropriate for the specific facility.
    (3) Emergency plans submitted under paragraph (i)(1)(ii) of this 
section must include the following information:
    (i) Facility description. A brief description of the licensee's 
facility and area near the site.
    (ii) Types of accidents. An identification of each type of 
radioactive materials accident for which protective actions may be 
needed.
    (iii) Classification of accidents. A classification system for 
classifying accidents as alerts or site area emergencies.
    (iv) Detection of accidents. Identification of the means of 
detecting each type of accident in a timely manner.
    (v) Mitigation of consequences. A brief description of the means and 
equipment for mitigating the consequences of each type of accident, 
including those provided to protect workers onsite, and a description of 
the program for maintaining the equipment.
    (vi) Assessment of releases. A brief description of the methods and 
equipment to assess releases of radioactive materials.
    (vii) Responsibilities. A brief description of the responsibilities 
of licensee personnel should an accident occur, including identification 
of personnel responsible for promptly notifying offsite response 
organizations and the NRC; also responsibilities for developing, 
maintaining, and updating the plan.
    (viii) Notification and coordination. A commitment to and a brief 
description of the means to promptly notify offsite response 
organizations and request offsite assistance, including medical 
assistance for the treatment of contaminated injured onsite workers when 
appropriate. A control point must be established. The notification and 
coordination must be planned so that unavailability of some personnel, 
parts of the facility, and some equipment will not prevent the 
notification and coordination. The licensee shall also commit to notify 
the NRC operations center immediately after notification of the 
appropriate offsite response organizations and not later than one hour 
after the licensee declares an emergency. \1\
---------------------------------------------------------------------------

    \1\ These reporting requirements do not superceed or release 
licensees of complying with the requirements under the Emergency 
Planning and Community Right-to-Know Act of 1986, Title III, Pub. L. 99-
499 or other state or federal reporting requirements.

---------------------------------------------------------------------------

[[Page 308]]

    (ix) Information to be communicated. A brief description of the 
types of information on facility status, radioactive releases, and 
recommended protective actions, if necessary, to be given to offsite 
response organizations and to the NRC.
    (x) Training. A brief description of the frequency, performance 
objectives and plans for the training that the licensee will provide 
workers on how to respond to an emergency including any special 
instructions and orientation tours the licensee would offer to fire, 
police, medical and other emergency personnel. The training shall 
familiarize personnel with site-specific emergency procedures. Also, the 
training shall thoroughly prepare site personnel for their 
responsibilities in the event of accident scenarios postulated as most 
probable for the specific site, including the use of team training for 
such scenarios.
    (xi) Safe shutdown. A brief description of the means of restoring 
the facility to a safe condition after an accident.
    (xii) Exercises. Provisions for conducting quarterly communications 
checks with offsite response organizations and biennial onsite exercises 
to test response to simulated emergencies. Quarterly communications 
checks with offsite response organizations must include the check and 
update of all necessary telephone numbers. The licensee shall invite 
offsite response organizations to participate in the biennial exercises. 
Participation of offsite response organizations in biennial exercises 
although recommended is not required. Exercises must use accident 
scenarios postulated as most probable for the specific site and the 
scenarios shall not be known to most exercise participants. The licensee 
shall critique each exercise using individuals not having direct 
implementation responsibility for the plan. Critiques of exercises must 
evaluate the appropriateness of the plan, emergency procedures, 
facilities, equipment, training of personnel, and overall effectiveness 
of the response. Deficiencies found by the critiques must be corrected.
    (xiii) Hazardous chemicals. A certification that the applicant has 
met its responsibilities under the Emergency Planning and Community 
Right-to-Know Act of 1986, Title III, Pub. L. 99-499, if applicable to 
the applicant's activities at the proposed place of use of the special 
nuclear material.
    (4) The licensee shall allow the offsite response organizations 
expected to respond in case of an accident 60 days to comment on the 
licensee's emergency plan before submitting it to NRC. The licensee 
shall provide any comments received within the 60 days to the NRC with 
the emergency plan.
    (j)(1) Each application for a license to possess or use at any site 
or contiguous sites subject to control by the licensee uranium-235 
(contained in uranium enriched to 20 percent or more in the uranium-235 
isotope), uranium-233, or plutonium alone or in any combination in a 
quantity of 5,000 grams or more computed by the formula, grams = (grams 
contained U-235) + 2.5 (grams U-233 + grams plutonium) other than a 
license for possession or use of this material in the operation of a 
nuclear reactor licensed pursuant to part 50 of this chapter, must 
include a licensee safeguards contingency plan for dealing with threats, 
thefts, and radiological sabotage, as defined in part 73 of this 
chapter, relating to nuclear facilities licensed under part 50 of this 
chapter or to the possession of special nuclear material licensed under 
this part.
    (2) Each application for such a license must include the first four 
categories of information contained in the applicant's safeguards 
contingency plan. (The first four categories of information, as set 
forth in appendix C to part 73 of this chapter, are Background, Generic 
Planning Base, Licensee Planning Base, and Responsibility Matrix.) The 
fifth category of information, Procedures, does not have to be submitted 
for approval.
    (3) The licensee shall retain a copy of this safeguards contingency 
plan as a record until the Commission terminates each license obtained 
by this application or any application for renewal of a license and 
retain each change to the plan as a record for three years after the 
date of the change.
    (k) Each application for a license to possess or use at any site or 
contiguous

[[Page 309]]

sites subject to licensee control, special nuclear material of moderate 
strategic significance or 10 kg or more of special nuclear material of 
low strategic significance as defined under Sec. 70.4, other than a 
license for possession or use of this material in the operation of a 
nuclear power reactor licensed pursuant to part 50 of this chapter, must 
include a physical security plan that demonstrates how the applicant 
plans to meet the requirements of paragraphs (d), (e), (f), and (g) of 
Sec. 73.67 of this chapter, as appropriate. The licensee shall retain a 
copy of this physical security plan as a record for the period during 
which the licensee possesses the appropriate type and quantity of 
special nuclear material under each license, and if any portion of the 
plan is superseded, retain that superseded portion of the plan for 3 
years after the effective date of the change.
    (l) Each applicant for a license shall protect Safeguards 
Information against unauthorized disclosure in accordance with the 
requirements in Sec. 73.21 and the requirements of Sec. 73.22, or 
73.23 of this chapter, as applicable, and shall protect classified 
information in accordance with the requirements of parts 25 and 95 of 
this chapter, as applicable.
    (m) Each application for a license to possess equipment capable of 
enriching uranium or operate an enrichment facility, and produce, 
possess, or use more than one effective kilogram of special nuclear 
material at any site or contiguous sites subject to control by the 
applicant, must contain a full description of the applicant's security 
program to protect against theft, and to protect against unauthorized 
viewing of classified enrichment equipment, and unauthorized disclosure 
of classified matter in accordance with the requirements of 10 CFR parts 
25 and 95.
    (n) A license application that involves the use of special nuclear 
material in a uranium enrichment facility must include the applicant's 
provisions for liability insurance.

[21 FR 764, Feb. 3, 1956]

    Editorial Note: For Federal Register citations affecting Sec. 
70.22, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 70.23  Requirements for the approval of applications.

    (a) An application for a license will be approved if the Commission 
determines that:
    (1) The special nuclear material is to be used for the conduct of 
research or development activities of a type specified in section 31 of 
the Act, \1\ in activities licensed by the Commission under section 103 
or 104 of the Act, or for such other uses as the Commission determines 
to be appropriate to carry out the purposes of the Act;
---------------------------------------------------------------------------

    \1\ The types of research and development activities specified in 
section 31 are those relating to:
    (1) Nuclear processes;
    (2) The theory and production of atomic energy, including processes, 
materials, and devices related to such production;
    (3) Utilization of special nuclear material and radioactive material 
for medical, biological, agricultural, health or military purposes;
    (4) Utilization of special nuclear material, atomic energy, and 
radioactive material and processes entailed in the utilization or 
production of atomic energy or such material for all other purposes, 
including industrial use, the generation of usable energy, and the 
demonstration of the practical value of utilization or production 
facilities for industrial or commercial purposes; and
    (5) The protection of health and the promotion of safety during 
research and production activities.
---------------------------------------------------------------------------

    (2) The applicant is qualified by reason of training and experience 
to use the material for the purpose requested in accordance with the 
regulations in this chapter;
    (3) The applicant's proposed equipment and facilities are adequate 
to protect health and minimize danger to life or property;
    (4) The applicant's proposed procedures to protect health and to 
minimize danger to life or property are adequate;
    (5) Where the nature of the proposed activities is such as to 
require consideration by the Commission, that the applicant appears to 
be financially qualified to engage in the proposed activities in 
accordance with the regulations in this part;
    (6) Where the applicant is required to submit a summary description 
of the

[[Page 310]]

fundamental material controls provided in his procedures for the control 
of and accounting for special nuclear material pursuant to Sec. 70.22 
(b), the applicant's proposed controls are adequate;
    (7) Where the proposed activity is processing and fuel fabrication, 
scrap recovery, conversion of uranium hexafluoride, uranium enrichment 
facility construction and operation, or any other activity which the NRC 
determines will significantly affect the quality of the environment, the 
Director of Nuclear Material Safety and Safeguards or his/her designee, 
before commencement of construction of the plant or facility in which 
the activity will be conducted, on the basis of information filed and 
evaluations made pursuant to subpart A of part 51 of this chapter, has 
concluded, after weighing the environmental, economic, technical, and 
other benefits against environmental costs and considering available 
alternatives, that the action called for is the issuance of the proposed 
license, with any appropriate conditions to protect environmental 
values. Commencement of construction prior to this conclusion is grounds 
for denial to possess and use special nuclear material in the plant or 
facility. Commencement of construction as defined in section 70.4 may 
include non-construction activities if the activity has a reasonable 
nexus to radiological safety and security.
    (8) Where the proposed activity is the operation of a plutonium 
processing and fuel fabrication plant, construction of the principal 
structures, systems, and components approved pursuant to paragraph (b) 
of this section has been completed in accordance with the application;
    (9) Where the applicant is required to submit a plan for physical 
protection of special nuclear material in transit pursuant to Sec. 
70.22(g), of this chapter, the applicant's plan is adequate;
    (10) Where the applicant is required to submit a physical security 
plan pursuant to Sec. 70.22(h), the applicant's proposed plan is 
adequate;
    (11) Where the proposed activity is processing and fuel fabrication, 
scrap recovery, conversion of uranium hexafluoride, or involves the use 
of special nuclear material in a uranium enrichment facility, the 
applicant's proposed emergency plan is adequate.
    (12) Where the proposed activity is use of special nuclear material 
in a uranium enrichment facility, the applicable provisions of part 140 
of this chapter have been satisfied.
    (b) The Commission will approve construction of the principal 
structures, systems, and components of a plutonium processing and fuel 
fabrication plant on the basis of information filed pursuant to Sec. 
70.22(f) when the Commission has determined that the design bases of the 
principal structures, systems, and components, and the quality assurance 
program provide reasonable assurance of protection against natural 
phenomena and the consequences of potential accidents. \3\ Failure to 
obtain Commission approval prior to beginning of such construction may 
be grounds for denial of a license to possess and use special nuclear 
material in a plutonium processing and fuel fabrication plant.
---------------------------------------------------------------------------

    \3\ The criteria in appendix B of part 50 of this chapter will be 
used by the Commission in determining the adequacy of the quality 
assurance program.

[36 FR 17574, Sept. 2, 1971, as amended at 37 FR 5749, Mar. 21, 1972; 38 
FR 30534, 30538, Nov. 6, 1973; 39 FR 26286, July 18, 1974; 42 FR 17126, 
Mar. 31, 1977; 43 FR 6924, Feb. 17, 1978; 49 FR 9406, Mar. 12, 1984; 54 
FR 14064, Apr. 7, 1989; 57 FR 18392, Apr. 30, 1992; 67 FR 78142, Dec. 
23, 2002; 76 FR 56966, Sept. 15, 2011]



Sec. 70.23a  Hearing required for uranium enrichment facility.

    The Commission will hold a hearing under 10 CFR part 2, subparts A, 
C, G, and I, on each application for issuance of a license for 
construction and operation of a uranium enrichment facility. The 
Commission will publish public notice of the hearing in the Federal 
Register at least thirty (30) days before the hearing.

[69 FR 2280, Jan. 14, 2004]



Sec. 70.24  Criticality accident requirements.

    (a) Each licensee authorized to possess special nuclear material in 
a quantity exceeding 700 grams of contained uranium-235, 520 grams of 
uranium-233,

[[Page 311]]

450 grams of plutonium, 1,500 grams of contained uranium-235 if no 
uranium enriched to more than 4 percent by weight of uranium-235 is 
present, 450 grams of any combination thereof, or one-half such 
quantities if massive moderators or reflectors made of graphite, heavy 
water or beryllium may be present, shall maintain in each area in which 
such licensed special nuclear material is handled, used, or stored, a 
monitoring system meeting the requirements of either paragraph (a)(1) or 
(a)(2), as appropriate, and using gamma- or neutron-sensitive radiation 
detectors which will energize clearly audible alarm signals if 
accidental criticality occurs. This section is not intended to require 
underwater monitoring when special nuclear material is handled or stored 
beneath water shielding or to require monitoring systems when special 
nuclear material is being transported when packaged in accordance with 
the requirements of part 71 of this chapter.
    (1) The monitoring system shall be capable of detecting a 
criticality that produces an absorbed dose in soft tissue of 20 rads of 
combined neutron and gamma radiation at an unshielded distance of 2 
meters from the reacting material within one minute. Coverage of all 
areas shall be provided by two detectors.
    (2) Persons licensed prior to December 6, 1974, to possess special 
nuclear material subject to this section may maintain a monitoring 
system capable of detecting a criticality which generates radiation 
levels of 300 rems per hour one foot from the source of the radiation. 
The monitoring devices in the system shall have a preset alarm point of 
not less than 5 millirems per hour (in order to avoid false alarms) nor 
more than 20 millirems per hour. In no event may any such device be 
farther than 120 feet from the special nuclear material being handled, 
used, or stored; lesser distances may be necessary to meet the 
requirements of this paragraph (a)(2) on account of intervening 
shielding or other pertinent factors.
    (3) The licensee shall maintain emergency procedures for each area 
in which this licensed special nuclear material is handled, used, or 
stored to ensure that all personnel withdraw to an area of safety upon 
the sounding of the alarm. These procedures must include the conduct of 
drills to familiarize personnel with the evacuation plan, and 
designation of responsible individuals for determining the cause of the 
alarm, and placement of radiation survey instruments in accessible 
locations for use in such an emergency. The licensee shall retain a copy 
of current procedures for each area as a record for as long as licensed 
special nuclear material is handled, used, or stored in the area. The 
licensee shall retain any superseded portion of the procedures for three 
years after the portion is superseded.
    (b) Each licensee authorized to possess special nuclear material in 
quantities in excess of those specified in paragraph (a) shall:
    (1) Provide the means for identifying quickly which individuals have 
received doses of 10 rads or more.
    (2) Maintain facilities and supplies at the site for decontamination 
of personnel, arrangements for the services of a physician and other 
medical personnel qualified to handle radiation emergencies, 
arrangements for transportation of injured or contaminated individuals 
to treatment facilities, and arrangements for treatment of individuals 
at treatment facilities outside the site boundary.
    (c) Holders of licenses for construction or operation of a nuclear 
reactor issued pursuant to part 50 of this chapter, except critical 
assembly reactors, are exempt for the requirements of paragraph (b) of 
this section with respect to special nuclear material used or to be used 
in the reactor.
    (d)(1) The requirements in paragraphs (a) through (c) of this 
section do not apply to a holder of a construction permit or operating 
license for a nuclear power reactor issued under part 50 of this chapter 
or a combined license issued under part 52 of this chapter, if the 
holder complies with the requirements of paragraph (b) of 10 CFR 50.68.
    (2) An exemption from Sec. 70.24 held by a licensee who thereafter 
elects to comply with requirements of paragraph (b) of 10 CFR 50.68 does 
not exempt that licensee from complying with any of the requirements in 
Sec. 50.68, but shall be

[[Page 312]]

ineffective so long as the licensee elects to comply with Sec. 50.68.

[39 FR 39021, Nov. 5, 1974, as amended at 41 FR 31522, July 29, 1976; 53 
FR 19252, May 27, 1988; 62 FR 63828, Dec. 3, 1997; 63 FR 9403, Feb. 25, 
1998; 63 FR 63130, Nov. 12, 1998]



Sec. 70.25  Financial assurance and recordkeeping for decommissioning.

    (a) Each applicant for a specific license of the types described in 
paragraphs (a) (1) and (2) of this section shall submit a 
decommissioning funding plan as described in paragraph (e) of this 
section.
    (1) A specific license for a uranium enrichment facility;
    (2) A specific license authorizing the possession and use of 
unsealed special nuclear material in quantities exceeding 10\5\ times 
the applicable quantities set forth in appendix B to part 30. A 
decommissioning funding plan must also be submitted when a combination 
of isotopes is involved if R divided by 10\5\ is greater than 1 (unity 
rule), where R is the sum of the ratios of the quantity of each isotope 
to the applicable value in appendix B to part 30.
    (b) Each applicant for a specific license authorizing possession and 
use of unsealed special nuclear material in quantities specified in 
paragraph (d) of this section shall either--
    (1) Submit a decommissioning funding plan as described in paragraph 
(e) of this section; or
    (2) Submit a certification that financial assurance for 
decommissioning has been provided in the amount prescribed by paragraph 
(d) of this section using one of the methods described in paragraph (f) 
of this section. For an applicant, this certification may state that the 
appropriate assurance will be obtained after the application has been 
approved and the license issued but before the receipt of licensed 
material. If the applicant defers execution of the financial instrument 
until after the license has been issued, a signed original of the 
financial instrument obtained to satisfy the requirements of paragraph 
(f) of this section must be submitted to NRC before receipt of licensed 
material. If the applicant does not defer execution of the financial 
instrument, the applicant shall submit to NRC, as part of the 
certification, a signed original of the financial instrument obtained to 
satisfy the requirements of paragraph (f) of this section.
    (c)(1) Each holder of a specific license issued on or after July 27, 
1990, which is of a type described in paragraph (a) or (b) of this 
section, shall provide financial assurance for decommissioning in 
accordance with the criteria set forth in this section.
    (2) Each holder of a specific license issued before July 27, 1990, 
and of a type described in paragraph (a) of this section shall submit a 
decommissioning funding plan as described in paragraph (e) of this 
section or a certification of financial assurance for decommissioning in 
an amount at least equal to $1,125,000 in accordance with the criteria 
set forth in this section. If the licensee submits the certification of 
financial assurance rather than a decommissioning funding plan, the 
licensee shall include a decommissioning funding plan in any application 
for license renewal.
    (3) Each holder of a specific license issued before July 27, 1990, 
and of a type described in paragraph (b) of this section shall submit, 
on or before July 27, 1990, a decommissioning funding plan, described in 
paragraph (e) of this section, or a certification of financial assurance 
for decommissioning in accordance with the criteria set forth in this 
section.
    (4) Any licensee who has submitted an application before July 27, 
1990, for renewal of license in accordance with Sec. 70.33 shall 
provide financial assurance for decommissioning in accordance with 
paragraphs (a) and (b) of this section. This assurance must be submitted 
when this rule becomes effective November 24, 1995.
    (5) If, in surveys made under 10 CFR 20.1501(a), residual 
radioactivity in the facility and environment, including the subsurface, 
is detected at levels that would, if left uncorrected, prevent the site 
from meeting the 10 CFR 20.1402 criteria for unrestricted use, the 
licensee must submit a decommissioning funding plan within one year of 
when the survey is completed.
    (d) Table of required amounts of financial assurance for 
decommissioning by quantity of material. Licensees required to submit 
the $1,125,000 amount

[[Page 313]]

must do so by December 2, 2004. Licensees required to submit the 
$225,000 amount must do so by June 2, 2005. Licensees having possession 
limits exceeding the upper bounds of this table must base financial 
assurance on a decommissioning funding plan.

------------------------------------------------------------------------
 
------------------------------------------------------------------------
Greater than 10\4\ but less than or equal to 10\5\ times      $1,125,000
 the applicable quantities of appendix B to part 30. (For a
 combination of isotopes, if R, as defined in Sec.
 70.25(a), divided by 10\4\ is greater than 1 but R divided
 by 10\5\ is less than or equal to 1.).....................
Greater than 10\3\ but less than or equal to 10\4\ times        $225,000
 the applicable quantities of appendix B to part 30. (For a
 combination of isotopes, if R, as defined in Sec.
 70.25(a), divided by 10\3\ is greater than 1 but R divided
 by 10\4\ is less than or equal to 1.).....................
------------------------------------------------------------------------

    (e)(1) Each decommissioning funding plan must be submitted for 
review and approval and must contain--
    (i) A detailed cost estimate for decommissioning, in an amount 
reflecting:
    (A) The cost of an independent contractor to perform all 
decommissioning activities;
    (B) The cost of meeting the 10 CFR 20.1402 criteria for unrestricted 
use, provided that, if the applicant or licensee can demonstrate its 
ability to meet the provisions of 10 CFR 20.1403, the cost estimate may 
be based on meeting the 10 CFR 20.1403 criteria;
    (C) The volume of onsite subsurface material containing residual 
radioactivity that will require remediation; and
    (D) An adequate contingency factor.
    (ii) Identification of and justification for using the key 
assumptions contained in the DCE;
    (iii) A description of the method of assuring funds for 
decommissioning from paragraph (f) of this section, including means for 
adjusting cost estimates and associated funding levels periodically over 
the life of the facility;
    (iv) A certification by the licensee that financial assurance for 
decommissioning has been provided in the amount of the cost estimate for 
decommissioning; and
    (v) A signed original, or, if permitted, a copy, of the financial 
instrument obtained to satisfy the requirements of paragraph (f) of this 
section (unless a previously submitted and accepted financial instrument 
continues to cover the cost estimate for decommissioning).
    (2) At the time of license renewal and at intervals not to exceed 3 
years, the decommissioning funding plan must be resubmitted with 
adjustments as necessary to account for changes in costs and the extent 
of contamination. If the amount of financial assurance will be adjusted 
downward, this can not be done until the updated decommissioning funding 
plan is approved. The decommissioning funding plan must update the 
information submitted with the original or prior approved plan, and must 
specifically consider the effect of the following events on 
decommissioning costs:
    (i) Spills of radioactive material producing additional residual 
radioactivity in onsite subsurface material;
    (ii) Waste inventory increasing above the amount previously 
estimated;
    (iii) Waste disposal costs increasing above the amount previously 
estimated;
    (iv) Facility modifications;
    (v) Changes in authorized possession limits;
    (vi) Actual remediation costs that exceed the previous cost 
estimate;
    (vii) Onsite disposal; and
    (viii) Use of a settling pond.
    (f) The financial instrument must include the licensee's name, 
license number, and docket number; and the name, address, and other 
contact information of the issuer, and, if a trust is used, the trustee. 
When any of the foregoing information changes, the licensee must, within 
30 days, submit financial instruments reflecting such changes. Financial 
assurance for decommissioning must be provided by one or more of the 
following methods:
    (1) Prepayment. Prepayment is the deposit before the start of 
operation into an account segregated from licensee assets and outside 
the licensee's administrative control of cash or liquid

[[Page 314]]

assets such that the amount of funds would be sufficient to pay 
decommissioning costs. Prepayment must be made into a trust account, and 
the trustee and the trust must be acceptable to the Commission.
    (2) A surety method, insurance, or other guarantee method. These 
methods guarantee that decommissioning costs will be paid. A surety 
method may be in the form of a surety bond, or letter of credit. A 
parent company guarantee of funds for decommissioning costs based on a 
financial test may be used if the guarantee and test are as contained in 
appendix A to part 30 of this chapter. For commercial corporations that 
issue bonds, a guarantee of funds by the applicant or licensee for 
decommissioning costs based on a financial test may be used if the 
guarantee and test are as contained in appendix C to part 30 of this 
chapter. For commercial companies that do not issue bonds, a guarantee 
of funds by the applicant or licensee for decommissioning costs may be 
used if the guarantee and test are as contained in appendix D to part 30 
of this chapter. For nonprofit entities, such as colleges, universities, 
and nonprofit hospitals, a guarantee of funds by the applicant or 
licensee may be used if the guarantee and test are as contained in 
appendix E to part 30 of this chapter. Except for an external sinking 
fund, a parent company guarantee or a guarantee by the applicant or 
licensee may not be used in combination with any other financial methods 
used to satisfy the requirements of this section. A guarantee by the 
applicant or licensee may not be used in any situation where the 
applicant or licensee has a parent company holding majority control of 
the voting stock of the company. Any surety method or insurance used to 
provide financial assurance for decommissioning must contain the 
following conditions:
    (i) The surety method or insurance must be open-ended or, if written 
for a specified term, such as five years, must be renewed automatically 
unless 90 days or more prior to the renewal date, the issurer notifies 
the Commission, the beneficiary, and the licensee of its intention not 
to renew. The surety method or insurance must also provide that the full 
face amount be paid to the beneficiary automatically prior to the 
expiration without proof of forfeiture if the licensee fails to provide 
a replacement acceptable to the Commission within 30 days after receipt 
of notification of cancellation.
    (ii) The surety method or insurance must be payable to a trust 
established for decommissioning costs. The trustee and trust must be 
acceptable to the Commission. An acceptable trustee includes an 
appropriate State or Federal government agency or an entity which has 
the authority to act as a trustee and whose trust operations are 
regulated and examined by a Federal or State agency.
    (iii) The surety method or insurance must remain in effect until the 
Commission has terminated the license.
    (3) An external sinking fund in which deposits are made at least 
annually, coupled with a surety method, insurance, or other guarantee 
method, the value of which may decrease by the amount being accumulated 
in the sinking fund. An external sinking fund is a fund established and 
maintained by setting aside funds periodically in an account segregated 
from licensee assets and outside the licensee's administrative control 
in which the total amount of funds would be sufficient to pay 
decommissioning costs at the time termination of operation is expected. 
An external sinking fund must be in the form of a trust. If the other 
guarantee method is used, no surety or insurance may be combined with 
the external sinking fund. The surety, insurance, or other guarantee 
provisions must be as stated in paragraph (f)(2) of this section.
    (4) In the case of Federal, State, or local government licensees, a 
statement of intent containing a cost estimate for decommissioning or an 
amount based on the Table in paragraph (d) of this section, and 
indicating that funds for decommissioning will be obtained when 
necessary.
    (5) When a governmental entity is assuming custody and ownership of 
a site, an arrangement that is deemed acceptable by such governmental 
entity.
    (g) Each person licensed under this part shall keep records of 
information important to the decommissioning of a facility in an 
identified location until

[[Page 315]]

the site is released for unrestricted use. If records important to the 
decommissioning of a facility are kept for other purposes, reference to 
these records and their locations may be used. Information the 
Commission considers important to decommissioning consists of--
    (1) Records of spills or other unusual occurrences involving the 
spread of contamination in and around the facility, equipment, or site. 
These records may be limited to instances when contamination remains 
after any cleanup procedures or when there is reasonable likelihood that 
contaminants may have spread to inaccessible areas as in the case of 
possible seepage into porous materials such as concrete. These records 
must include any known information on identification of involved 
nuclides, quantities, forms, and concentrations.
    (2) As-built drawings and modifications of structures and equipment 
in restricted areas where radioactive materials are used and/or stored 
and of locations of possible inaccessible contamination such as buried 
pipes which may be subject to contamination. If required drawings are 
referenced, each relevant document need not be indexed individually. If 
drawings are not available, the licensee shall substitute appropriate 
records of available information concerning these areas and locations.
    (3) Except for areas containing only sealed sources (provided the 
sources have not leaked or no contamination remains after cleanup of any 
leak), a list contained in a single document and updated every 2 years, 
of the following:
    (i) All areas designated and formerly designated as restricted areas 
as defined under 10 CFR 20.1003 (For requirements prior to January 1, 
1994, see 10 CFR 20.3 as contained in the CFR edition revised as of 
January 1, 1993.);
    (ii) All areas outside of restricted areas that require 
documentation under Sec. 70.25(g)(1);
    (iii) All areas outside of restricted areas where current and 
previous wastes have been buried as documented under 10 CFR 20.2108; and
    (iv) All areas outside of restricted areas that contain material 
such that, if the license expired, the licensee would be required to 
either decontaminate the area to meet the criteria for decommissioning 
in 10 CFR part 20, subpart E, or apply for approval for disposal under 
10 CFR 20.2002.
    (4) Records of the cost estimate performed for the decommissioning 
funding plan or of the amount certified for decommissioning, and records 
of the funding method used for assuring funds if either a funding plan 
or certification is used.
    (h) In providing financial assurance under this section, each 
licensee must use the financial assurance funds only for decommissioning 
activities and each licensee must monitor the balance of funds held to 
account for market variations. The licensee must replenish the funds, 
and report such actions to the NRC, as follows:
    (1) If, at the end of a calendar quarter, the fund balance is below 
the amount necessary to cover the cost of decommissioning, but is not 
below 75 percent of the cost, the licensee must increase the balance to 
cover the cost, and must do so within 30 days after the end of the 
calendar quarter.
    (2) If, at any time, the fund balance falls below 75 percent of the 
amount necessary to cover the cost of decommissioning, the licensee must 
increase the balance to cover the cost, and must do so within 30 days of 
the occurrence.
    (3) Within 30 days of taking the actions required by paragraph 
(h)(1) or (h)(2) of this section, the licensee must provide a written 
report of such actions to the Director, Office of Nuclear Material 
Safety and Safeguards, and state the new balance of the fund.

[53 FR 24053, June 27, 1988, as amended at 56 FR 23474, May 21, 1991; 57 
FR 18393, Apr. 30, 1992; 58 FR 39634, July 26, 1993; 58 FR 67662, Dec. 
22, 1993; 58 FR 68731, Dec. 29, 1993; 59 FR 1618, Jan. 12, 1994; 60 FR 
38239, July 26, 1995; 61 FR 24675, May 16, 1996; 62 FR 39091, July 21, 
1997; 63 FR 29544, June 1, 1998; 68 FR 57337, Oct. 3, 2003; 76 FR 35572, 
June 17, 2011; 78 FR 34250, June 7, 2013; 78 FR 75450, Dec. 12, 2013; 79 
FR 75740, Dec. 19, 2014]



                           Subpart E_Licenses



Sec. 70.31  Issuance of licenses.

    (a) Upon a determination that an application meets the requirements 
of the act and of the regulations of the

[[Page 316]]

Commission, the Commission will issue a license in such form and 
containing such conditions and limitations as it deems appropriate or 
necessary to effectuate the purposes of the act.
    (b) [Reserved]
    (c) Each license issued to a person for use of special nuclear 
material in activities in which special nuclear material will be 
produced shall (subject to the provisions of Sec. 70.41(b)) be deemed 
to authorize such person to receive title to, own, acquire, receive, 
possess, use, and transfer the special nuclear material produced in the 
course of such authorized activities.
    (d) No license will be issued by the Commission to any person within 
the United States if the Commission finds that the issuance of such 
license would be inimical to the common defense and security or would 
constitute an unreasonable risk to the health and safety of the public.
    (e) No license to construct and operate a uranium enrichment 
facility may be issued until a hearing pursuant to 10 CFR part 2, 
subparts G and I, is completed and decision issued on the application.

[21 FR 764, Feb. 3, 1956, as amended at 32 FR 2563, Feb. 7, 1967; 32 FR 
4056, Mar. 15, 1967; 43 FR 6925, Feb. 17, 1978; 57 FR 18393, Apr. 30, 
1992]



Sec. 70.32  Conditions of licenses.

    (a) Each license shall contain and be subject to the following 
conditions:
    (1) [Reserved]
    (2) No right to the special nuclear material shall be conferred by 
the license except as defined by the license;
    (3) Neither the license nor any right under the license shall be 
assigned or otherwise transferred in violation of the provisions of the 
Act;
    (4) All special nuclear material shall be subject to the right of 
recapture or control reserved by section 108 and to all other provisions 
of the Act;
    (5) No special nuclear material may be used in any utilization or 
production facility except in accordance with the provisions of the Act;
    (6) The licensee shall not use the special nuclear material to 
construct an atomic weapon or any component of an atomic weapon;
    (7) Except to the extent that the indemnification and limitation of 
liability provisions of part 140 of this chapter apply, the licensee 
will hold the United States and the Department harmless from any damages 
resulting from the use or possession of special nuclear material leased 
from the Department by the licensee;
    (8) The license shall be subject to and the licensee shall observe, 
all applicable rules, regulations and orders of the Commission.
    (9)(i) Each licensee shall notify the appropriate NRC Regional 
Administrator, in writing, immediately following the filing of a 
voluntary or involuntary petition for bankruptcy under any Chapter of 
Title 11 (Bankruptcy) of the United States Code by or against:
    (A) The licensee;
    (B) An entity (as that term is defined in 11 U.S.C. 101(14)) 
controlling the licensee or listing the license or licensee as property 
of the estate; or
    (C) An affiliate (as that term is defined in 11 U.S.C. 101(a)) of 
the licensee.
    (ii) This notification must indicate:
    (A) The bankruptcy court in which the petition for bankruptcy was 
filed; and
    (B) The date of the filing of the petition.
    (b) The Commission may incorporate in any license such additional 
conditions and requirements with respect to the licensee's ownership, 
receipt, possession, use, and transfer of special nuclear material as it 
deems appropriate or necessary in order to:
    (1) Promote the common defense and security;
    (2) Protect health or to minimize danger to life or property;
    (3) Protect restricted data;
    (4) Guard against the loss or diversion of special nuclear material;
    (5) Require such reports and the keeping of such records, and to 
provide for such inspections, of activities under the license as may be 
necessary or appropriate to effectuate the purposes of the act and 
regulations thereunder.
    (c)(1) Each license authorizing the possession and use at any one 
time and location of uranium source material at

[[Page 317]]

an uranium enrichment facility or special nuclear material in a quantity 
exceeding one effective kilogram, except for use as sealed sources and 
those uses involved in the operation of a nuclear reactor licensed 
pursuant to part 50 of this chapter and those involved in a waste 
disposal operation, shall contain and be subject to a condition 
requiring the licensee to maintain and follow:
    (i) The program for control and accounting of uranium source 
material at an uranium enrichment facility and special nuclear material 
at all applicable facilities as implemented pursuant to Sec. 70.22(b), 
or Sec. Sec. 74.31(b), 74.33(b), 74.41(b), or 74.51(c) of this chapter, 
as appropriate;
    (ii) The measurement control program for uranium source material at 
an uranium enrichment facility and for special nuclear material at all 
applicable facilities as implemented pursuant to Sec. Sec. 74.31(b), 
74.33(b), 74.45(c), or 74.59(e) of this chapter, as appropriate; and
    (iii) Other material control procedures as the Commission determines 
to be essential for the safeguarding of uranium source material at an 
uranium enrichment facility or of special nuclear material and providing 
that the licensee shall make no change that would decrease the 
effectiveness of the material control and accounting program implemented 
pursuant to Sec. 70.22(b), or Sec. Sec. 74.31(b), 74.33(b), 74.41(b), 
or 74.51(c) of this chapter, and the measurement control program 
implemented pursuant to Sec. Sec. 74.31(b), 74.33(b), 74.41(b), or 
74.59(e) of this chapter without the prior approval of the Commission. A 
licensee desiring to make changes that would decrease the effectiveness 
of its material control and accounting program or its measurement 
control program shall submit an application for amendment to its license 
pursuant to Sec. 70.34.
    (2) The licensee shall maintain records of changes to the material 
control and accounting program made without prior Commission approval 
for a period of 5 years from the date of the change. Licensees located 
in all four Regions as indicated in appendix A of part 73 of this 
chapter shall furnish to the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, using an appropriate 
method listed in Sec. 70.5(a), a report containing a description of 
each change within:
    (i) Two months of the change if it pertains to uranium-233, uranium-
235 contained in uranium enriched 20 percent or more in the uranium-235 
isotope, or plutonium, except plutonium containing 80 percent or more by 
weight of the isotope Pu-238, and
    (ii) Six months of the change if it pertains to uranium enriched 
less than 20 percent in the uranium-235 isotope, or plutonium containing 
80 percent or more by weight of the isotope Pu-238.
    (d) The licensee shall make no change which would decrease the 
effectiveness of the plan for physical protection of special nuclear 
material in transit prepared pursuant to Sec. 70.22(g) or Sec. 
73.20(c) of this chapter without the prior approval of the Commission. A 
licensee desiring to make such changes shall submit an application for a 
change in the technical specifications incorporated in his or her 
license, if any, or for an amendment to the license pursuant to Sec. 
50.90 or Sec. 70.34 of this chapter, as appropriate. The licensee may 
make changes to the plan for physical protection of special nuclear 
material without prior Commission approval if these changes do not 
decrease the effectiveness of the plan. The licensee shall retain a copy 
of the plan as a record for the period during which the licensee 
possesses a formula quantity of special nuclear material requiring this 
record under each license and each change to the plan for three years 
from the effective date of the change. Within two months after each 
change, a report containing a description of the change must be 
furnished to the Director of the NRC's Office of Nuclear Material Safety 
and Safeguards, using an appropriate method listed in Sec. 70.5(a); and 
a copy must be sent to the appropriate NRC Regional Office shown in 
appendix A to part 73 of this chapter.
    (e) The licensee shall make no change which would decrease the 
effectiveness of a security plan prepared pursuant to Sec. Sec. 
70.22(h), 70.22(k), or 73.20(c) without the prior approval of the 
Commission. A licensee desiring to make such a change shall submit an

[[Page 318]]

application for an amendment to its license pursuant to Sec. 70.34. The 
licensee shall maintain records of changes to the plan made without 
prior Commission approval, for three years from the effective date of 
the change, and shall, within two months after the change is made, 
furnish a report containing a description of each change to the 
Director, Division of Security Policy, Office of Nuclear Security and 
Incident Response; the report may be sent using an appropriate method 
listed in Sec. 70.5(a), and a copy of the report must be sent to the 
appropriate NRC Regional Office shown in appendix A to part 73 of this 
chapter.
    (f) [Reserved]
    (g) The licensee shall prepare and maintain safeguards contingency 
plan procedures in accordance with appendix C to part 73 of this chapter 
for bringing about the actions and decisions contained in the 
Responsibility Matrix of its safeguards contingency plan. The licensee 
shall retain the current safeguards contingency plan procedures as a 
record for the entire period during which the licensee possesses the 
appropriate type and quantity of special nuclear material under each 
license for which the procedures were developed and, if any portion of 
the plan is superseded, retain that superseded portion for 3 years after 
the effective date of the change. The licensee shall not make a change 
that would decrease the safeguards effectiveness of the first four 
categories of information (i.e., Background, Generic Planning Base, 
Licensee Planning Base, and Responsibility Matrix) contained in any 
licensee safeguards contingency plan prepared pursuant to Sec. Sec. 
70.22(g), 70.22(j), 72.184, 73.20(c), 73.26(e)(1), 73.46(h)(1), or 
73.50(g)(1) of this chapter without the prior approval of the NRC. A 
licensee desiring to make such a change shall submit an application for 
an amendment to its license pursuant to Sec. 70.34. The licensee may 
make changes to the licensee safeguards contingency plan without prior 
NRC approval if the changes do not decrease the safeguards effectiveness 
of the plan. The licensee shall maintain each change to the plan made 
without prior approval as a record during the period for which 
possession of a formula quantity of special nuclear material is 
authorized under a license and retain the superseded portion for 3 years 
after the effective date of the change, and shall, within 60 days after 
the change is made, furnish a report containing a description of each 
change to the Director of Nuclear Material Safety and Safeguards; the 
report may be sent using an appropriate method listed in Sec. 70.5(a), 
and a copy of the report must be sent to the Regional Administrator of 
the appropriate NRC Regional Office as specified in appendix A to part 
73 of this chapter.
    (h) [Reserved]
    (i) Licensees required to submit emergency plans in accordance with 
Sec. 70.22(i) shall follow the emergency plan approved by the 
Commission. The licensee may change the approved plan without Commission 
approval if the changes do not decrease the effectiveness of the plan. 
Within six months after each change is made, the licensee shall, using 
an appropriate method listed in Sec. 70.5(a), furnish the Director, 
Division of Security Policy, Office of Nuclear Security and Incident 
Response, a copy of each change, with copies to the appropriate NRC 
Regional Office specified in appendix D to part 20 of this chapter and 
to affected offsite response organizations. Proposed changes that 
decrease the effectiveness of the approved emergency plan may not be 
implemented without prior application to and prior approval by the 
Commission.
    (j) Each licensee who possesses special nuclear material, or who 
transports, or delivers to a carrier for transport, a formula quantity 
of strategic special nuclear material, special nuclear material of 
moderate strategic significance, or special nuclear material of low 
strategic significance, or more than 100 grams of irradiated reactor 
fuel shall ensure that Safeguards Information is protected against 
unauthorized disclosure in accordance with the requirements in Sec. 
73.21 and the requirements of Sec. 73.22 or Sec. 73.23 of this 
chapter, as applicable, and shall protect classified information in 
accordance with the requirements of parts 25 and 95 of this chapter, as 
applicable.
    (k) No person may commence operation of a uranium enrichment 
facility until the Commission verifies through

[[Page 319]]

inspection that the facility has been constructed in accordance with the 
requirements of the license. The Commission shall publish notice of the 
inspection results in the Federal Register.

[21 FR 764, Feb. 3, 1956]

    Editorial Note: For Federal Register citations affecting Sec. 
70.32, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 70.33  Applications for renewal of licenses.

    Applications for renewal of a license should be filed in accordance 
with Sec. Sec. 70.21 and 70.22. Information contained in previous 
applications, statements or reports filed with the Commission under the 
license may be incorporated by reference, provided that such references 
are clear and specific.

[75 FR 73944, Nov. 30, 2010]



Sec. 70.34  Amendment of licenses.

    Applications for amendment of a license shall be filed in accordance 
with Sec. 70.21(a) and shall specify the respects in which the licensee 
desires his license to be amended and the grounds for such amendment.



Sec. 70.35  Commission action on applications to renew or amend.

    In considering an application by a licensee to renew or amend his 
license, the Commission will apply the criteria set forth in Sec. 
70.23.



Sec. 70.36  Inalienability of licenses.

    (a) No license granted under the regulations in this part and no 
right to possess or utilize special nuclear material granted by any 
license issued pursuant to the regulations in this part shall be 
transferred, assigned or in any manner disposed of, either voluntarily 
or involuntarily, directly or indirectly, through transfer of control of 
any license to any person unless the Commission shall after securing 
full information, find that the transfer is in accordance with the 
provisions of the Act, and shall give its consent in writing.
    (b) An application for transfer of license must include:
    (1) The identity, technical and financial qualifications of the 
proposed transferee; and
    (2) Financial assurance for decommissioning information required by 
Sec. 70.25.

[21 FR 764, Feb. 3, 1956, as amended at 35 FR 11461, July 17, 1970; 76 
FR 35573, June 17, 2011]



Sec. 70.37  Disclaimer of warranties.

    Neither the Government nor the Commission makes any warranty or 
other representation that special nuclear material (a) will not result 
in injury or damage when used for purposes approved by the Commission, 
(b) will accomplish the results for which it is requested and approved 
by the Commission, or (c) is safe for any other use.



Sec. 70.38  Expiration and termination of licenses and decommissioning
of sites and separate buildings or outdoor areas.

    (a) Each specific license expires at the end of the day on the 
expiration date stated in the license unless the licensee has filed an 
application for renewal under Sec. 70.33 not less than 30 days before 
the expiration date stated in the existing license. If an application 
for renewal has been filed at least 30 days before the expiration date 
stated in the existing license, the existing license expires at the end 
of the day on which the Commission makes a final determination to deny 
the renewal application or, if the determination states an expiration 
date, the expiration date stated in the determination.
    (b) Each specific license revoked by the Commission expires at the 
end of the day on the date of the Commission's final determination to 
revoke the license, or on the expiration date stated in the 
determination, or as otherwise provided by Commission Order.
    (c) Each specific license continues in effect, beyond the expiration 
date if necessary, with respect to possession of special nuclear 
material until the Commission notifies the licensee in writing that the 
license is terminated. During this time, the licensee shall--
    (1) Limit actions involving special nuclear material to those 
related to decommissioning; and
    (2) Continue to control entry to restricted areas until they are 
suitable

[[Page 320]]

for release in accordance with NRC requirements.
    (d) Within 60 days of the occurrence of any of the following, 
consistent with the administrative directions in Sec. 70.5, each 
licensee shall provide notification to the NRC in writing and either 
begin decommissioning its site, or any separate building or outdoor area 
that contains residual radioactivity, so that the building or outdoor 
area is suitable for release in accordance with NRC requirements, or 
submit within 12 months of notification a decommissioning plan, if 
required by paragraph (g)(1) of this section, and begin decommissioning 
upon approval of that plan if--
    (1) The license has expired pursuant to paragraph (a) or (b) of this 
section; or
    (2) The licensee has decided to permanently cease principal 
activities, as defined in this part, at the entire site or in any 
separate building or outdoor area; or
    (3) No principal activities under the license have been conducted 
for a period of 24 months; or
    (4) No principal activities have been conducted for a period of 24 
months in any separate building or outdoor area that contains residual 
radioactivity such that the building or outdoor area is unsuitable for 
release in accordance with NRC requirements.
    (e) Coincident with the notification required by paragraph (d) of 
this section, the licensee shall maintain in effect all decommissioning 
financial assurances established by the licensee pursuant to Sec. 70.25 
in conjunction with a license issuance or renewal or as required by this 
section. The amount of the financial assurance must be increased, or may 
be decreased, as appropriate, to cover the detailed cost estimate for 
decommissioning established pursuant to paragraph (g)(4)(v) of this 
section.
    (1) Any licensee who has not provided financial assurance to cover 
the detailed cost estimate submitted with the decommissioning plan shall 
do so when this rule becomes effective November 24, 1995.
    (2) Following approval of the decommissioning plan, a licensee may 
reduce the amount of the financial assurance as decommissioning proceeds 
and radiological contamination is reduced at the site with the approval 
of the Commission.
    (f) The Commission may grant a request to delay or postpone 
initiation of the decommissioning process if the Commission determines 
that this relief is not detrimental to the public health and safety and 
is otherwise in the public interest. The request must be submitted no 
later than 30 days before notification pursuant to paragraph (d) of this 
section. The schedule for decommissioning set forth in paragraph (d) of 
this section may not commence until the Commission has made a 
determination on the request.
    (g)(1) A decommissioning plan must be submitted if required by 
license condition or if the procedures and activities necessary to carry 
out decommissioning of the site or separate building or outdoor area 
have not been previously approved by the Commission and these procedures 
could increase potential health and safety impacts to workers or to the 
public, such as in any of the following cases:
    (i) Procedures would involve techniques not applied routinely during 
cleanup or maintenance operations;
    (ii) Workers would be entering areas not normally occupied where 
surface contamination and radiation levels are significantly higher than 
routinely encountered during operation;
    (iii) Procedures could result in significantly greater airborne 
concentrations of radioactive materials than are present during 
operation; or
    (iv) Procedures could result in significantly greater releases of 
radioactive material to the environment than those associated with 
operation.
    (2) The Commission may approve an alternate schedule for submittal 
of a decommissioning plan required pursuant to paragraph (d) of this 
section if the Commission determines that the alternative schedule is 
necessary to the effective conduct of decommissioning operations and 
presents no undue risk from radiation to the public health and safety 
and is otherwise in the public interest.
    (3) The procedures listed in paragraph (g)(1) of this section may 
not be

[[Page 321]]

carried out prior to approval of the decommissioning plan.
    (4) The proposed decommissioning plan for the site or separate 
building or outdoor area must include:
    (i) A description of the conditions of the site or separate building 
or outdoor area sufficient to evaluate the acceptability of the plan;
    (ii) A description of planned decommissioning activities;
    (iii) A description of methods used to ensure protection of workers 
and the environment against radiation hazards during decommissioning;
    (iv) A description of the planned final radiation survey; and
    (v) An updated detailed cost estimate for decommissioning, 
comparison of that estimate with present funds set aside for 
decommissioning, and a plan for assuring the availability of adequate 
funds for completion of decommissioning.
    (vi) A description of the physical security plan and material 
control and accounting plan provisions in place during decommissioning.
    (vii) For decommissioning plans calling for completion of 
decommissioning later than 24 months after plan approval, a 
justification for the delay based on the criteria in paragraph (i) of 
this section.
    (5) The proposed decommissioning plan will be approved by the 
Commission if the information therein demonstrates that the 
decommissioning will be completed as soon as practical and that the 
health and safety of workers and the public will be adequately 
protected.
    (h)(1) Except as provided in paragraph (i) of this section, 
licensees shall complete decommissioning of the site or separate 
building or outdoor area as soon as practicable but no later than 24 
months following the initiation of decommissioning.
    (2) Except as provided in paragraph (i) of this section, when 
decommissioning involves the entire site, the licensee shall request 
license termination as soon as practicable but no later than 24 months 
following the initiation of decommissioning.
    (i) The Commission may approve a request for an alternate schedule 
for completion of decommissioning of the site or separate building or 
outdoor area, and license termination if appropriate, if the Commission 
determines that the alternative is warranted by consideration of the 
following:
    (1) Whether it is technically feasible to complete decommissioning 
within the allotted 24-month period;
    (2) Whether sufficient waste disposal capacity is available to allow 
completion of decommissioning within the allotted 24-month period;
    (3) Whether a significant volume reduction in wastes requiring 
disposal will be achieved by allowing short-lived radionuclides to 
decay;
    (4) Whether a significant reduction in radiation exposure to workers 
can be achieved by allowing short-lived radionuclides to decay; and
    (5) Other site-specific factors which the Commission may consider 
appropriate on a case-by-case basis, such as regulatory requirements of 
other government agencies, lawsuits, groundwater treatment activities, 
monitored natural groundwater restoration, actions that could result in 
more environmental harm than deferred cleanup, and other factors beyond 
the control of the licensee.
    (j) As the final step in decommissioning, the licensee shall--
    (1) Certify the disposition of all licensed material, including 
accumulated wastes, by submitting a completed NRC Form 314 or equivalent 
information; and
    (2) Conduct a radiation survey of the premises where the licensed 
activities were carried out and submit a report of the results of this 
survey, unless the licensee demonstrates in some other manner that the 
premises are suitable for release in accordance with the criteria for 
decommissioning in 10 CFR part 20, subpart E. The licensee shall, as 
appropriate--
    (i) Report levels of gamma radiation in units of millisieverts 
(microroentgen) per hour at one meter from surfaces, and report levels 
of radioactivity, including alpha and beta, in units of megabecquerels 
(disintegrations per minute or microcuries) per 100 square centimeters 
removable and fixed for surfaces, megabecquerels (microcuries) per 
milliliter for water,

[[Page 322]]

and becquerels (picocuries) per gram for solids such as soils or 
concrete; and
    (ii) Specify the survey instrument(s) used and certify that each 
instrument is properly calibrated and tested.
    (k) Specific licenses, including expired licenses, will be 
terminated by written notice to the licensee when the Commission 
determines that:
    (1) Special nuclear material has been properly disposed;
    (2) Reasonable effort has been made to eliminate residual 
radioactive contamination, if present; and
    (3)(i) A radiation survey has been performed which demonstrates that 
the premises are suitable for release in accordance with the criteria 
for decommissioning in 10 CFR part 20, subpart E; or
    (ii) Other information submitted by the licensee is sufficient to 
demonstrate that the premises are suitable for release in accordance 
with the criteria for decommissioning in 10 CFR part 20, subpart E.
    (4) Records required by Sec. 70.51(b)(6) have been received.

[59 FR 36037, July 15, 1994, as amended at 60 FR 38240, July 26, 1995; 
61 FR 1115, Jan. 16, 1996; 61 FR 24675, May 16, 1996; 61 FR 29637, 
29638, June 12, 1996; 62 FR 39091, July 21, 1997; 66 FR 24049, May 11, 
2001; 73 FR 42675, July 23, 2008]



Sec. 70.39  Specific licenses for the manufacture or initial transfer
of calibration or reference sources.

    (a) An application for a specific license to manufacture or 
initially transfer calibration or reference sources containing 
plutonium, for distribution to persons generally licensed under Sec. 
70.19, will be approved if:
    (1) The applicant satisfies the general requirements of Sec. 70.23.
    (2) The applicant submits sufficient information regarding each type 
of calibration or reference source pertinent to evaluation of the 
potential radiation exposure, including:
    (i) Chemical and physical form and maximum quantity of plutonium in 
the source;
    (ii) Details of construction and design;
    (iii) Details of the method of incorporation and binding of the 
plutonium in the source;
    (iv) Procedures for and results of prototype testing of sources, 
which are designed to contain more than 0.005 microcurie of plutonium, 
to demonstrate that the plutonium contained in each source will not be 
released or be removed from the source under normal conditions of use;
    (v) Details of quality control procedures to be followed in 
manufacture of the source;
    (vi) Description of labeling to be affixed to the source or the 
storage container for the source;
    (vii) Any additional information, including experimental studies and 
tests, required by the Commission to facilitate a determination of the 
safety of the source.
    (3) Each source will contain no more than 5 microcuries of 
plutonium.
    (4) The Commission determines, with respect to any type of source 
containing more than 0.005 microcurie of plutonium, that:
    (i) The method of incorporation and binding of the plutonium in the 
source is such that the plutonium will not be released or be removed 
from the source under normal conditions of use and handling of the 
source; and
    (ii) The source has been subjected to and has satisfactorily passed 
the prototype tests prescribed by paragraph (a)(5) of this section.
    (5) For any type of source which is designed to contain more than 
0.005 microcurie of plutonium, the applicant has conducted prototype 
tests, in the order listed, on each of five prototypes of such source, 
which contains more than 0.005 microcurie of plutonium, as follows:
    (i) Initial measurement. The quantity of radioactive material 
deposited on the source shall be measured by direct counting of the 
source.
    (ii) Dry wipe test. The entire radioactive surface of the source 
shall be wiped with filter paper with the application of moderate finger 
pressure. Removal of radioactive material from the source shall be 
determined by measuring the radioactivity on the filter paper or by 
direct measurement of the radioactivity on the source following the dry 
wipe.
    (iii) Wet wipe test. The entire radioactive surface of the source 
shall be

[[Page 323]]

wiped with filter paper, moistened with water, with the application of 
moderate finger pressure. Removal of radioactive material from the 
source shall be determined by measuring the radioactivity on the filter 
paper after it has dried or by direct measurement of the radioactivity 
on the source following the wet wipe.
    (iv) Water soak test. The source shall be immersed in water at room 
temperature for a period of 24 consecutive hours. The source shall then 
be removed from the water. Removal of radioactive material from the 
source shall be determined by direct measurement of the radioactivity on 
the source after it has dried or by measuring the radioactivity in the 
residue obtained by evaporation of the water in which the source was 
immersed.
    (v) Dry wipe test. On completion of the preceding tests in 
paragraphs (a)(5)(i) through (iv) of this section, the dry wipe test 
described in paragraph (a)(5)(ii) of this section shall be repeated.
    (vi) Observations. Removal of more than 0.005 microcurie of 
radioactivity in any test prescribed by this paragraph shall be cause 
for rejection of the source design. Results of prototype tests submitted 
to the Commission shall be given in terms of radioactivity in 
microcuries and percent of removal from the total amount of radioactive 
material deposited on the source.
    (b) Each person licensed under this section shall affix to each 
source, or storage container for the source, a label which shall contain 
sufficient information relative to safe use and storage of the source 
and shall include the following statement or a substantially similar 
statement which contains the information called for in the following 
statement. \1\
---------------------------------------------------------------------------

    \1\ Sources generally licensed under this section prior to January 
19, 1975 may bear labels authorized by the regulations in effect on 
January 1, 1975.

    The receipt, possession, use and transfer of this source, Model ___, 
Serial No. ___, are subject to a general license and the regulations of 
the United States Nuclear Regulatory Commission or of a State with which 
the Commission has entered into an agreement for the exercise of 
regulatory authority. Do not remove this label.
 caution--radioactive material--this source contains plutonium. do not 
          touch radioactive portion of this source.

              (Name of Manufacturer or Initial Transferor)

    (c) Each person licensed under this section shall perform a dry wipe 
test upon each source containing more than 0.1 microcurie of plutonium 
prior to transferring the source to a general licensee under Sec. 
70.19. This test shall be performed by wiping the entire radioactive 
surface of the source with a filter paper with the application of 
moderate finger pressure. The radioactivity on the paper shall be 
measured by using radiation detection instrumentation capable of 
detecting 0.005 microcurie of plutonium. If any such test discloses more 
than 0.005 microcurie of radioactive material, the source shall be 
deemed to be leaking or losing plutonium and shall not be transferred to 
a general licensee under Sec. 70.19.

[29 FR 5884, May 5, 1964, as amended at 32 FR 2563, Feb. 7, 1967; 38 FR 
1272, Jan. 11, 1973; 40 FR 8792, Mar. 3, 1975; 42 FR 43966, Sept. 1, 
1977; 43 FR 6925, Feb. 17, 1978]



Sec. 70.40  Ineligibility of certain applicants.

    A license may not be issued to the Corporation if the Commission 
determines that:
    (a) The Corporation is owned, controlled, or dominated by an alien, 
a foreign corporation, or a foreign government; or
    (b) The issuance of such a license would be inimical to--
    (1) The common defense and security of the United States; or
    (2) The maintenance of a reliable and economical domestic source of 
enrichment services.

[62 FR 6669, Feb. 12, 1997]



  Subpart F_Acquisition, Use and Transfer of Special Nuclear Material, 
                            Creditors' Rights



Sec. 70.41  Authorized use of special nuclear material.

    (a) Each licensee shall confine his possession and use of special 
nuclear material to the locations and purposes

[[Page 324]]

authorized in his license. Except as otherwise provided in the license, 
each license issued pursuant to the regulations in this part shall carry 
with it the right to receive title to, own, acquire, receive, possess 
and use special nuclear material. Preparation for shipment and transport 
of special nuclear material shall be in accordance with the provisions 
of part 71 of this chapter.
    (b) The possession, use and transfer of any special nuclear material 
produced by a licensee, in connection with or as a result of use of 
special nuclear material received under his license, shall be subject to 
the provisions of the license and the regulations in this part.

[21 FR 764, Feb. 3, 1956, as amended at 38 FR 33970, Dec. 10, 1973; 43 
FR 6925, Feb. 17, 1978]



Sec. 70.42  Transfer of special nuclear material.

    (a) No licensee shall transfer special nuclear material except as 
authorized pursuant to this section.
    (b) Except as otherwise provided in his license and subject to the 
provisions of paragraphs (c) and (d) of this section, any licensee may 
transfer special nuclear material:
    (1) To the Department;
    (2) To the agency in any Agreement State which regulates radioactive 
materials pursuant to an agreement with the Commission or the Atomic 
Energy Commission under section 274 of the Act, if the quantity 
transferred is not sufficient to form a critical mass;
    (3) To any person exempt from the licensing requirements of the Act 
and regulations in this part, to the extent permitted under such 
exemption;
    (4) To any person in an Agreement State, subject to the jurisdiction 
of that State, who has been exempted from the licensing requirements and 
regulations of that State, to the extent permitted under such exemption;
    (5) To any person authorized to receive such special nuclear 
material under terms of a specific license or a general license or their 
equivalents issued by the Commission or an Agreement State;
    (6) To any person abroad pursuant to an export license issued under 
part 110 of this chapter; or
    (7) As otherwise authorized by the Commission in writing.
    (c) Before transferring special nuclear material to a specific 
licensee of the Commission or an Agreement State or to a general 
licensee who is required to register with the Commission or with an 
Agreement State prior to receipt of the special nuclear material, the 
licensee transferring the material shall verify that the transferee's 
license authorizes receipt of the type, form, and quantity of special 
nuclear material to be transferred.
    (d) The following methods for the verification required by paragraph 
(c) of this section are acceptable:
    (1) The transferor may have in his or her possession, and read, a 
current copy of the transferee's specific license or registration 
certificate. The transferor shall retain a copy of each license or 
certificate for three years from the date that it was obtained.
    (2) The transferor may have in its possession a written 
certification by the transferee that the transferee is authorized by 
license or registration certificate to receive the type, form, and 
quantity of special nuclear material to be transferred, specifying the 
license or registration certificate number, issuing agency, and 
expiration date. The transferor shall retain the written certification 
as a record for three years from the date of receipt of the 
certification;
    (3) For emergency shipments the transferor may accept oral 
certification by the transferee that he or she is authorized by license 
or registration certification to receive the type, form, and quantity of 
special nuclear material to be transferred, specifying the license or 
registration certificate number, issuing agency, and expiration date, 
provided that the oral certification is confirmed in writing within ten 
days. The transferor shall retain the written confirmation of the oral 
certification for three years from the date of receipt of the 
confirmation;
    (4) The transferor may obtain other sources of information compiled 
by a reporting service from official records of the Commission or the 
licensing agency of an Agreement State as to the identity of licensees 
and the scope and

[[Page 325]]

expiration dates of licenses and registrations. The transferor shall 
retain the compilation of information as a record for three years from 
the date that it was obtained; or
    (5) When none of the methods of verification described in paragraphs 
(d) (1) to (4) of this section are readily available or when a 
transferor desires to verify that information received by one of these 
methods is correct or up-to-date, the transferor may obtain and record 
confirmation from the Commission or the licensing agency of an Agreement 
State that the transferee is licensed to receive the special nuclear 
material. The transferor shall retain the record of confirmation for 
three years from the date the record is made.

[38 FR 33970, Dec. 10, 1973, as amended at 40 FR 8792, Mar. 3, 1975; 43 
FR 6925, Feb. 21, 1978; 53 FR 19253, May 27, 1988]



Sec. 70.44  Creditor regulations.

    (a) Pursuant to section 184 of the Act, the Commission consents, 
without individual application, to the creation of any mortgage, pledge, 
or other lien upon any special nuclear material, not owned by the United 
States, which is subject to licensing: Provided:
    (1) That the rights of any creditor so secured may be exercised only 
in compliance with and subject to the same requirements and restrictions 
as would apply to the licensee pursuant to the provisions of the 
license, the Atomic Energy Act of 1954, as amended, and regulations 
issued by the Commission pursuant to said Act; and
    (2) That no creditor so secured may take possession of the special 
nuclear material pursuant to the provisions of this section prior to 
either the issuance of a license by the Commission authorizing such 
possession or the transfer of a license pursuant to Sec. 70.36.
    (b) Nothing contained in this section shall be deemed to affect the 
means of acquiring, or the priority of, any tax lien or other lien 
provided by law.
    (c) As used in this section, creditor includes, without implied 
limitation, the trustee under any mortgage, pledge, or lien on special 
nuclear material made to secure any creditor, any trustee or receiver of 
the special nuclear material appointed by a court of competent 
jurisdiction in any action brought for the benefit of any creditor 
secured by such mortgage, pledge, or lien, any purchaser of such special 
nuclear material at the sale thereof upon foreclosure of such mortgage, 
pledge, or lien or upon exercise of any power of sale contained therein, 
or any assignee of any such purchaser.

[32 FR 2563, Feb. 7, 1967, as amended at 35 FR 11461, July 17, 1970]



    Subpart G_Special Nuclear Material Control, Records, Reports and 
                               Inspections



Sec. 70.50  Reporting requirements.

    (a) Immediate report. Each licensee shall notify the NRC as soon as 
possible but not later than 4 hours after the discovery of an event that 
prevents immediate protective actions necessary to avoid exposures to 
radiation or radioactive materials that could exceed regulatory limits 
or releases of licensed material that could exceed regulatory limits 
(events may include fires, explosions, toxic gas releases, etc.).
    (b) Twenty-four hour report. Each licensee shall notify the NRC 
within 24 hours after the discovery of any of the following events 
involving licensed material:
    (1) An unplanned contamination event that:
    (i) Requires access to the contaminated area, by workers or the 
public, to be restricted for more than 24 hours by imposing additional 
radiological controls or by prohibiting entry into the area;
    (ii) Involves a quantity of material greater than five times the 
lowest annual limit on intake specified in Appendix B of Sec. Sec. 
20.1001-20.2401 of 10 CFR part 20 for the material; and
    (iii) Has access to the area restricted for a reason other than to 
allow isotopes with a half-life of less than 24 hours to decay prior to 
decontamination.
    (2) An event in which equipment is disabled or fails to function as 
designed when:
    (i) The equipment is required by regulation or licensee condition to 
prevent releases exceeding regulatory limits, to

[[Page 326]]

prevent exposures to radiation and radioactive materials exceeding 
regulatory limits, or to mitigate the consequences of an accident;
    (ii) The equipment is required to be available and operable when it 
is disabled or fails to function; and
    (iii) No redundant equipment is available and operable to perform 
the required safety function.
    (3) An event that requires unplanned medical treatment at a medical 
facility of an individual with spreadable radioactive contamination on 
the individual's clothing or body.
    (4) An unplanned fire or explosion damaging any licensed material or 
any device, container, or equipment containing licensed material when:
    (i) The quantity of material involved is greater than five times the 
lowest annual limit on intake specified in appendix B of Sec. Sec. 
20.1001-20.2401 of 10 CFR part 20 for the material; and
    (ii) The damage affects the integrity of the licensed material or 
its container.
    (c) Preparation and submission of reports. Reports made by licensees 
in response to the requirements of this section must be made as follows:
    (1) Licensees shall make reports required by paragraphs (a) and (b) 
of this section, and by Sec. 70.74 and Appendix A of this part, if 
applicable, by telephone to the NRC Operations Center. \1\ To the extent 
that the information is available at the time of notification, the 
information provided in these reports must include:
---------------------------------------------------------------------------

    \1\ The commercial telephone number for the NRC Operations Center is 
(301) 816-5100.
---------------------------------------------------------------------------

    (i) Caller's name, position title, and call-back telephone number;
    (ii) Date, time, and exact location of the event;
    (iii) Description of the event, including:
    (A) Radiological or chemical hazards involved, including isotopes, 
quantities, and chemical and physical form of any material released;
    (B) Actual or potential health and safety consequences to the 
workers, the public, and the environment, including relevant chemical 
and radiation data for actual personnel exposures to radiation or 
radioactive materials or hazardous chemicals produced from licensed 
materials (e.g., level of radiation exposure, concentration of 
chemicals, and duration of exposure);
    (C) The sequence of occurrences leading to the event, including 
degradation or failure of structures, systems, equipment, components, 
and activities of personnel relied on to prevent potential accidents or 
mitigate their consequences; and
    (D) Whether the remaining structures, systems, equipment, 
components, and activities of personnel relied on to prevent potential 
accidents or mitigate their consequences are available and reliable to 
perform their function;
    (iv) External conditions affecting the event;
    (v) Additional actions taken by the licensee in response to the 
event;
    (vi) Status of the event (e.g., whether the event is on-going or was 
terminated);
    (vii) Current and planned site status, including any declared 
emergency class;
    (viii) Notifications, related to the event, that were made or are 
planned to any local, State, or other Federal agencies;
    (ix) Status of any press releases, related to the event, that were 
made or are planned.
    (2) Written report. Each licensee that makes a report required by 
paragraph (a) or (b) of this section shall submit a written follow-up 
report within 30 days of the initial report. Written reports prepared 
pursuant to other regulations may be submitted to fulfill this 
requirement if the report contains all the necessary information, and 
the appropriate distribution is made. These written reports must be sent 
to the NRC's Document Control Desk, using an appropriate method listed 
in Sec. 70.5(a), with a copy to the appropriate NRC regional office 
listed in appendix D to part 20 of this chapter. The reports must 
include the following:
    (i) Complete applicable information required by Sec. 70.50(c)(1);
    (ii) The probable cause of the event, including all factors that 
contributed to the event and the manufacturer and model number (if 
applicable) of any

[[Page 327]]

equipment that failed or malfunctioned;
    (iii) Corrective actions taken or planned to prevent occurrence of 
similar or identical events in the future and the results of any 
evaluations or assessments; and
    (iv) For licensees subject to Subpart H of this part, whether the 
event was identified and evaluated in the Integrated Safety Analysis.
    (d) The provisions of Sec. 70.50 do not apply to licensees subject 
to Sec. 50.72. They do apply to those Part 50 licensees possessing 
material licensed under Part 70 that are not subject to the notification 
requirements in Sec. 50.72.

[56 FR 40769, Aug. 16, 1991; 56 FR 64980, Dec. 13, 1991, as amended at 
59 FR 14087, Mar. 25, 1994; 65 FR 56226, Sept. 18, 2000; 68 FR 58817, 
Oct. 10, 2003; 79 FR 57725, Sept. 26, 2014]



Sec. 70.51  Records requirements.

    (a) Before license termination, licensees shall forward the 
following records to the appropriate NRC Regional Office:
    (1) Records of disposal of licensed material made under 10 CFR 
20.2002 (including burials authorized before January 28, 1981 \1\), 
20.2003, 20.2004, 20.2005;
---------------------------------------------------------------------------

    \1\ A previous Sec. 20.304 permitted burial of small quantities of 
licensed materials in soil before January 28, 1981, without specific 
Commission authorization. See Sec. 20.304 contained in the 10 CFR, 
parts 0 to 199, edition revised as of January 1, 1981.
---------------------------------------------------------------------------

    (2) Records required by 10 CFR 20.2103(b)(4); and
    (3) Records required by Sec. 70.25(g).
    (b) If licensed activities are transferred or assigned in accordance 
with Sec. 70.32(a)(3), the licensee shall transfer the following 
records to the new licensee and the new licensee will be responsible for 
maintaining these records until the license is terminated:
    (1) Records of disposal of licensed material made under 10 CFR 
20.2002 (including burials authorized before January 28, 1981 \1\), 
20.2003, 20.2004, 20.2005;
    (2) Records required by 10 CFR 20.2103(b)(4); and
    (3) Records required by Sec. 70.25(g).
    (c)(1) Records which must be maintained pursuant to this part may be 
the original or a reproduced copy, or microform if the reproduced copy 
or microform is duly authenticated by authorized personnel, and the 
microform is capable of producing a clear and legible copy after storage 
for the period specified by Commission regulations. The record may also 
be stored in electronic media with the capability for producing legible, 
accurate, and complete records during the required retention period. 
Records such as letters, drawings, and specifications, must include all 
pertinent information such as stamps, initials, and signatures. The 
licensee shall maintain adequate safeguards against tampering with and 
loss of records.
    (2) If there is a conflict between the Commission's regulations in 
this part, license condition, or other written Commission approval or 
authorization pertaining to the retention period for the same type of 
record, the retention period specified in the regulations in this part 
for these records shall apply unless the Commission, under Sec. 70.17 
has granted a specific exemption from the record retention requirements 
specified in the regulations in this part.

[67 FR 78142, Dec. 23, 2002, as amended at 72 FR 35145, June 27, 2007]



Sec. 70.52  Reports of accidental criticality.

    (a) Each licensee shall notify the NRC Operations Center \1\ within 
one hour after discovery of any case of accidental criticality.
---------------------------------------------------------------------------

    \1\ Commercial telephone number of the NRC Operations Center is 
(301) 816-5100.
---------------------------------------------------------------------------

    (b) This notification must be made to the NRC Operations Center via 
the Emergency Notification System if the licensee is party to that 
system. If the Emergency Notification System is inoperative or 
unavailable, the licensee shall make the required notification via 
commercial telephonic service or other dedicated telephonic system or 
any other method that will ensure that a report is received by the NRC 
Operations Center within one hour.

[67 FR 78143, Dec. 23, 2002]



Sec. 70.55  Inspections.

    (a) Each licensee shall afford to the Commission at all reasonable 
times opportunity to inspect special nuclear

[[Page 328]]

material and the premises and facilities wherein special nuclear 
material is used, produced, or stored.
    (b) Each licensee shall make available to the Commission for 
inspection, upon reasonable notice, records kept by the licensee 
pertaining to his receipt, possession, use, acquisition, import, export, 
or transfer of special nuclear material.
    (c)(1) In the case of fuel cycle facilities where nuclear reactor 
fuel is fabricated or processed each licensee shall upon request by the 
Director, Office of Nuclear Material Safety and Safeguards or the 
appropriate NRC Regional Administrator, provide rent-free office space 
for the exclusive use of Commission inspection personnel. Heat, air 
conditioning, light, electrical outlets and janitorial services shall be 
furnished by each licensee. The office shall be convenient to and have 
full access to the facility and, shall provide the inspector both visual 
and acoustic privacy.
    (2) For a site with a single fuel facility licensed pursuant to part 
70, the space provided shall be adequate to accommodate a full-time 
inspector, a part-time secretary and transient NRC personnel and will be 
generally commensurate with other office facilities at the site. A space 
of 250 square feet either within the site's office complex or in an 
office trailer or other on site space is suggested as a guide. For sites 
containing multiple fuel facilities, additional space may be requested 
to accommodate additional full-time inspector(s). The office space that 
is provided shall be subject to the approval of the Director, Office of 
Nuclear Material Safety and Safeguards or the appropriate NRC Regional 
Administrator. All furniture, supplies and communication equipment will 
be furnished by the Commission.
    (3) The licensee shall afford any NRC resident inspector assigned to 
that site or other NRC inspectors identified by the Director, Office of 
Nuclear Material Safety and Safeguards, as likely to inspect the 
facility, immediate unfettered access, equivalent to access provided 
regular plant employees, following proper identification and compliance 
with applicable access control measures for security, radiological 
protection, and personal safety.

[21 FR 764, Feb. 3, 1956. Redesignated at 25 FR 1607, Feb. 25, 1960, and 
25 FR 12730, Dec. 13, 1960, and amended at 32 FR 2563, Feb. 7, 1967; 44 
FR 47919, Aug. 16, 1979; 52 FR 31612, Aug. 21, 1987; 54 FR 6877, Feb. 
15, 1989; 55 FR 5979, Feb. 21, 1990]



Sec. 70.56  Tests.

    Each licensee shall perform, or permit the Commission to perform, 
such tests as the Commission deems appropriate or necessary for the 
administration of the regulations in this part, including tests of (a) 
special nuclear material, (b) facilities wherein special nuclear 
material is utilized, produced or stored, (c) radiation detection and 
monitoring instruments, and (d) other equipment and devices used in 
connection with the production, utilization or storage of special 
nuclear material.

[21 FR 764, Feb. 3, 1956. Redesignated at 25 FR 1607, Feb. 25, 1960, and 
25 FR 12730, Dec. 13, 1960]



Sec. 70.59  Effluent monitoring reporting requirements.

    Within 60 days after January 1 and July 1 of each year, and using an 
appropriate method listed in Sec. 70.5(a), each licensee authorized to 
possess and use special nuclear material for processing and fuel 
fabrication, scrap recovery, conversion of uranium hexafluoride, or in a 
uranium enrichment facility shall submit a report addressed: ATTN: 
Document Control Desk, Director, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, with a copy to the appropriate NRC Regional Office shown in 
appendix D to part 20 of this chapter. The report must specify the 
quantity of each of the principal radionuclides released to unrestricted 
areas in liquid and gaseous effluents during the previous six months of 
operation, and such other information as the Commission may require to 
estimate maximum potential annual radiation doses to the public 
resulting from effluent releases. If quantities of radioactive materials 
released during the reporting periods are significantly above

[[Page 329]]

the licensee's design objectives previously reviewed as part of the 
licensing action, the report must cover this specifically. On the basis 
of these reports and any additional information the Commission may 
obtain from the licensee or others, the Commission may from time to time 
require the licensee to take such action as the Commission deems 
appropriate.

[68 FR 58817, Oct. 10, 2003]



 Subpart H_Additional Requirements for Certain Licensees Authorized To 
           Possess a Critical Mass of Special Nuclear Material

    Source: 65 FR 56226, Sept. 18, 2000, unless otherwise noted.



Sec. 70.60  Applicability.

    The regulations in Sec. 70.61 through Sec. 70.76 apply, in 
addition to other applicable Commission regulations, to each applicant 
or licensee that is or plans to be authorized to possess greater than a 
critical mass of special nuclear material, and engaged in enriched 
uranium processing, fabrication of uranium fuel or fuel assemblies, 
uranium enrichment, enriched uranium hexafluoride conversion, plutonium 
processing, fabrication of mixed-oxide fuel or fuel assemblies, scrap 
recovery of special nuclear material, or any other activity that the 
Commission determines could significantly affect public health and 
safety. The regulations in Sec. 70.61 through Sec. 70.76 do not apply 
to decommissioning activities performed pursuant to other applicable 
Commission regulations including Sec. 70.25 and Sec. 70.38 of this 
part. Also, the regulations in Sec. 70.61 through Sec. 70.76 do not 
apply to activities that are certified by the Commission pursuant to 
part 76 of this chapter or licensed by the Commission pursuant to other 
parts of this chapter. Unless specifically addressed in Sec. 70.61 
through Sec. 70.76, implementation by current licensees of the Subpart 
H requirements shall be completed no later than the time of the ISA 
Summary submittal required in Sec. 70.62(c)(3)(ii).



Sec. 70.61  Performance requirements.

    (a) Each applicant or licensee shall evaluate, in the integrated 
safety analysis performed in accordance with Sec. 70.62, its compliance 
with the performance requirements in paragraphs (b), (c), and (d) of 
this section.
    (b) The risk of each credible high-consequence event must be 
limited. Engineered controls, administrative controls, or both, shall be 
applied to the extent needed to reduce the likelihood of occurrence of 
the event so that, upon implementation of such controls, the event is 
highly unlikely or its consequences are less severe than those in 
paragrahs (b)(1)-(4) of this section. High consequence events are those 
internally or externally initiated events that result in:
    (1) An acute worker dose of 1 Sv (100 rem) or greater total 
effective dose equivalent;
    (2) An acute dose of 0.25 Sv (25 rem) or greater total effective 
dose equivalent to any individual located outside the controlled area 
identified pursuant to paragraph (f) of this section;
    (3) An intake of 30 mg or greater of uranium in soluble form by any 
individual located outside the controlled area identified pursuant to 
paragraph (f) of this section; or
    (4) An acute chemical exposure to an individual from licensed 
material or hazardous chemicals produced from licensed material that:
    (i) Could endanger the life of a worker, or
    (ii) Could lead to irreversible or other serious, long-lasting 
health effects to any individual located outside the controlled area 
identified pursuant to paragraph (f) of this section. If an applicant 
possesses or plans to possess quantities of material capable of such 
chemical exposures, then the applicant shall propose appropriate 
quantitative standards for these health effects, as part of the 
information submitted pursuant to Sec. 70.65 of this subpart.
    (c) The risk of each credible intermediate-consequence event must be 
limited. Engineered controls, administrative controls, or both shall be 
applied to the extent needed so that, upon implementation of such 
controls,

[[Page 330]]

the event is unlikely or its consequences are less than those in 
paragraphs (c)(1)-(4) of this section. Intermediate consequence events 
are those internally or externally initiated events that are not high 
consequence events, that result in:
    (1) An acute worker dose of 0.25 Sv (25 rem) or greater total 
effective dose equivalent;
    (2) An acute dose of 0.05 Sv (5 rem) or greater total effective dose 
equivalent to any individual located outside the controlled area 
identified pursuant to paragraph (f) of this section;
    (3) A 24-hour averaged release of radioactive material outside the 
restricted area in concentrations exceeding 5000 times the values in 
Table 2 of Appendix B to Part 20; or
    (4) An acute chemical exposure to an individual from licensed 
material or hazardous chemicals produced from licensed material that:
    (i) Could lead to irreversible or other serious, long-lasting health 
effects to a worker, or
    (ii) Could cause mild transient health effects to any individual 
located outside the controlled area as specified in paragraph (f) of 
this section. If an applicant possesses or plans to possess quantities 
of material capable of such chemical exposures, then the applicant shall 
propose appropriate quantitative standards for these health effects, as 
part of the information submitted pursuant to Sec. 70.65 of this 
subpart.
    (d) In addition to complying with paragraphs (b) and (c) of this 
section, the risk of nuclear criticality accidents must be limited by 
assuring that under normal and credible abnormal conditions, all nuclear 
processes are subcritical, including use of an approved margin of 
subcriticality for safety. Preventive controls and measures must be the 
primary means of protection against nuclear criticality accidents.
    (e) Each engineered or administrative control or control system 
necessary to comply with paragraphs (b), (c), or (d) of this section 
shall be designated as an item relied on for safety. The safety program, 
established and maintained pursuant to Sec. 70.62 of this subpart, 
shall ensure that each item relied on for safety will be available and 
reliable to perform its intended function when needed and in the context 
of the performance requirements of this section.
    (f) Each licensee must establish a controlled area, as defined in 
Sec. 20.1003. In addition, the licensee must retain the authority to 
exclude or remove personnel and property from the area. For the purpose 
of complying with the performance requirements of this section, 
individuals who are not workers, as defined in Sec. 70.4, may be 
permitted to perform ongoing activities (e.g., at a facility not related 
to the licensed activities) in the controlled area, if the licensee:
    (1) Demonstrates and documents, in the integrated safety analysis, 
that the risk for those individuals at the location of their activities 
does not exceed the performance requirements of paragraphs (b)(2), 
(b)(3), (b)(4)(ii), (c)(2), and (c)(4)(ii) of this section; or
    (2) Provides training that satisfies 10 CFR 19.12(a)(1)-(5) to these 
individuals and ensures that they are aware of the risks associated with 
accidents involving the licensed activities as determined by the 
integrated safety analysis, and conspicuously posts and maintains 
notices stating where the information in 10 CFR 19.11(a) may be examined 
by these individuals. Under these conditions, the performance 
requirements for workers specified in paragraphs (b) and (c) of this 
section may be applied to these individuals.



Sec. 70.62  Safety program and integrated safety analysis.

    (a) Safety program. (1) Each licensee or applicant shall establish 
and maintain a safety program that demonstrates compliance with the 
performance requirements of Sec. 70.61. The safety program may be 
graded such that management measures applied are graded commensurate 
with the reduction of the risk attributable to that item. Three elements 
of this safety program; namely, process safety information, integrated 
safety analysis, and management measures, are described in paragraphs 
(b) through (d) of this section.
    (2) Each licensee or applicant shall establish and maintain records 
that demonstrate compliance with the requirements of paragraphs (b) 
through (d) of this section.

[[Page 331]]

    (3) Each licensee or applicant shall maintain records of failures 
readily retrievable and available for NRC inspection, documenting each 
discovery that an item relied on for safety or management measure has 
failed to perform its function upon demand or has degraded such that the 
performance requirements of Sec. 70.61 are not satisfied. These records 
must identify the item relied on for safety or management measure that 
has failed and the safety function affected, the date of discovery, date 
(or estimated date) of the failure, duration (or estimated duration) of 
the time that the item was unable to perform its function, any other 
affected items relied on for safety or management measures and their 
safety function, affected processes, cause of the failure, whether the 
failure was in the context of the performance requirements or upon 
demand or both, and any corrective or compensatory action that was 
taken. A failure must be recorded at the time of discovery and the 
record of that failure updated promptly upon the conclusion of each 
failure investigation of an item relied on for safety or management 
measure.
    (b) Process safety information. Each licensee or applicant shall 
maintain process safety information to enable the performance and 
maintenance of an integrated safety analysis. This process safety 
information must include information pertaining to the hazards of the 
materials used or produced in the process, information pertaining to the 
technology of the process, and information pertaining to the equipment 
in the process.
    (c) Integrated safety analysis. (1) Each licensee or applicant shall 
conduct and maintain an integrated safety analysis, that is of 
appropriate detail for the complexity of the process, that identifies:
    (i) Radiological hazards related to possessing or processing 
licensed material at its facility;
    (ii) Chemical hazards of licensed material and hazardous chemicals 
produced from licensed material;
    (iii) Facility hazards that could affect the safety of licensed 
materials and thus present an increased radiological risk;
    (iv) Potential accident sequences caused by process deviations or 
other events internal to the facility and credible external events, 
including natural phenomena;
    (v) The consequence and the likelihood of occurrence of each 
potential accident sequence identified pursuant to paragraph (c)(1)(iv) 
of this section, and the methods used to determine the consequences and 
likelihoods; and
    (vi) Each item relied on for safety identified pursuant to Sec. 
70.61(e) of this subpart, the characteristics of its preventive, 
mitigative, or other safety function, and the assumptions and conditions 
under which the item is relied upon to support compliance with the 
performance requirements of Sec. 70.61.
    (2) Integrated safety analysis team qualifications. To assure the 
adequacy of the integrated safety analysis, the analysis must be 
performed by a team with expertise in engineering and process 
operations. The team shall include at least one person who has 
experience and knowledge specific to each process being evaluated, and 
persons who have experience in nuclear criticality safety, radiation 
safety, fire safety, and chemical process safety. One member of the team 
must be knowledgeable in the specific integrated safety analysis 
methodology being used.
    (3) Requirements for existing licensees. Individuals holding an NRC 
license on September 18, 2000 shall, with regard to existing licensed 
activities:
    (i) By April 18, 2001, submit for NRC approval, a plan that 
describes the integrated safety analysis approach that will be used, the 
processes that will be analyzed, and the schedule for completing the 
analysis of each process.
    (ii) By October 18, 2004, or in accordance with the approved plan 
submitted under Sec. 70.62(c)(3)(i), complete an integrated safety 
analysis, correct all unacceptable performance deficiencies, and submit, 
for NRC approval, an integrated safety analysis summary, including a 
description of the management measures, in accordance with Sec. 70.65. 
The Commission may approve a request for an alternative schedule for 
completing the correction of unacceptable performance deficiencies if 
the

[[Page 332]]

Commission determines that the alternative is warranted by consideration 
of the following:
    (A) Adequate compensatory measures have been established;
    (B) Whether it is technically feasible to complete the correction of 
the unacceptable performance deficiency within the allotted 4-year 
period;
    (C) Other site-specific factors which the Commission may consider 
appropriate on a case-by-case basis and that are beyond the control of 
the licensee.
    (iii) Pending the correction of unacceptable performance 
deficiencies identified during the conduct of the integrated safety 
analysis, the licensee shall implement appropriate compensatory measures 
to ensure adequate protection.
    (d) Management measures. Each applicant or licensee shall establish 
management measures to ensure compliance with the performance 
requirements of Sec. 70.61. The measures applied to a particular 
engineered or administrative control or control system may be graded 
commensurate with the reduction of the risk attributable to that control 
or control system. The management measures shall ensure that engineered 
and administrative controls and control systems that are identified as 
items relied on for safety pursuant to Sec. 70.61(e) of this subpart 
are designed, implemented, and maintained, as necessary, to ensure they 
are available and reliable to perform their function when needed, to 
comply with the performance requirements of Sec. 70.61 of this subpart.



Sec. 70.64  Requirements for new facilities or new processes 
at existing facilities.

    (a) Baseline design criteria. Each prospective applicant or licensee 
shall address the following baseline design criteria in the design of 
new facilities. Each existing licensee shall address the following 
baseline design criteria in the design of new processes at existing 
facilities that require a license amendment under Sec. 70.72. The 
baseline design criteria must be applied to the design of new facilities 
and new processes, but do not require retrofits to existing facilities 
or existing processes (e.g., those housing or adjacent to the new 
process); however, all facilities and processes must comply with the 
performance requirements in Sec. 70.61. Licensees shall maintain the 
application of these criteria unless the analysis performed pursuant to 
Sec. 70.62(c) demonstrates that a given item is not relied on for 
safety or does not require adherence to the specified criteria.
    (1) Quality standards and records. The design must be developed and 
implemented in accordance with management measures, to provide adequate 
assurance that items relied on for safety will be available and reliable 
to perform their function when needed. Appropriate records of these 
items must be maintained by or under the control of the licensee 
throughout the life of the facility.
    (2) Natural phenomena hazards. The design must provide for adequate 
protection against natural phenomena with consideration of the most 
severe documented historical events for the site.
    (3) Fire protection. The design must provide for adequate protection 
against fires and explosions.
    (4) Environmental and dynamic effects. The design must provide for 
adequate protection from environmental conditions and dynamic effects 
associated with normal operations, maintenance, testing, and postulated 
accidents that could lead to loss of safety functions.
    (5) Chemical protection. The design must provide for adequate 
protection against chemical risks produced from licensed material, 
facility conditions which affect the safety of licensed material, and 
hazardous chemicals produced from licensed material.
    (6) Emergency capability. The design must provide for emergency 
capability to maintain control of:
    (i) Licensed material and hazardous chemicals produced from licensed 
material;
    (ii) Evacuation of on-site personnel; and
    (iii) Onsite emergency facilities and services that facilitate the 
use of available offsite services.
    (7) Utility services. The design must provide for continued 
operation of essential utility services.
    (8) Inspection, testing, and maintenance. The design of items relied 
on for

[[Page 333]]

safety must provide for adequate inspection, testing, and maintenance, 
to ensure their availability and reliability to perform their function 
when needed.
    (9) Criticality control. The design must provide for criticality 
control including adherence to the double contingency principle.
    (10) Instrumentation and controls. The design must provide for 
inclusion of instrumentation and control systems to monitor and control 
the behavior of items relied on for safety.
    (b) Facility and system design and facility layout must be based on 
defense-in-depth practices. \1\ The design must incorporate, to the 
extent practicable:
---------------------------------------------------------------------------

    \1\ As used in Sec. 70.64, Requirements for new facilities or new 
processes at existing facilities, defense-in-depth practices means a 
design philosophy, applied from the outset and through completion of the 
design, that is based on providing successive levels of protection such 
that health and safety will not be wholly dependent upon any single 
element of the design, construction, maintenance, or operation of the 
facility. The net effect of incorporating defense-in-depth practices is 
a conservatively designed facility and system that will exhibit greater 
tolerance to failures and external challenges. The risk insights 
obtained through performance of the integrated safety analysis can be 
then used to supplement the final design by focusing attention on the 
prevention and mitigation of the higher-risk potential accidents.
---------------------------------------------------------------------------

    (1) Preference for the selection of engineered controls over 
administrative controls to increase overall system reliability; and
    (2) Features that enhance safety by reducing challenges to items 
relied on for safety.



Sec. 70.65  Additional content of applications.

    (a) In addition to the contents required by Sec. 70.22, each 
application must include a description of the applicant's safety program 
established under Sec. 70.62.
    (b) The integrated safety analysis summary must be submitted with 
the license or renewal application (and amendment application as 
necessary), but shall not be incorporated in the license. However, 
changes to the integrated safety analysis summary shall meet the 
conditions of Sec. 70.72. The integrated safety analysis summary must 
contain:
    (1) A general description of the site with emphasis on those factors 
that could affect safety (i.e., meteorology, seismology);
    (2) A general description of the facility with emphasis on those 
areas that could affect safety, including an identification of the 
controlled area boundaries;
    (3) A description of each process (defined as a single reasonably 
simple integrated unit operation within an overall production line) 
analyzed in the integrated safety analysis in sufficient detail to 
understand the theory of operation; and, for each process, the hazards 
that were identified in the integrated safety analysis pursuant to Sec. 
70.62(c)(1)(i)-(iii) and a general description of the types of accident 
sequences;
    (4) Information that demonstrates the licensee's compliance with the 
performance requirements of Sec. 70.61, including a description of the 
management measures; the requirements for criticality monitoring and 
alarms in Sec. 70.24; and, if applicable, the requirements of Sec. 
70.64;
    (5) A description of the team, qualifications, and the methods used 
to perform the integrated safety analysis;
    (6) A list briefly describing each item relied on for safety which 
is identified pursuant to Sec. 70.61(e) in sufficient detail to 
understand their functions in relation to the performance requirements 
of Sec. 70.61;
    (7) A description of the proposed quantitative standards used to 
assess the consequences to an individual from acute chemical exposure to 
licensed material or chemicals produced from licensed materials which 
are on-site, or expected to be on-site as described in Sec. 70.61(b)(4) 
and (c)(4);
    (8) A descriptive list that identifies all items relied on for 
safety that are the sole item preventing or mitigating an accident 
sequence that exceeds the performance requirements of Sec. 70.61; and
    (9) A description of the definitions of unlikely, highly unlikely, 
and credible as used in the evaluations in the integrated safety 
analysis.

[[Page 334]]



Sec. 70.66  Additional requirements for approval of license 
application.

    (a) An application for a license from an applicant subject to 
subpart H will be approved if the Commission determines that the 
applicant has complied with the requirements of Sec. Sec. 70.21, 70.22, 
70.23, and 70.60 through 70.65.
    (b) Submittals by existing licensees in accordance with Sec. 
70.62(c)(3)(i) will be approved if the Commission determines that:
    (1) The integrated safety analysis approach is in accordance with 
the requirements of Sec. Sec. 70.61, 70.62(c)(1), and 70.62(c)(2); and
    (2) The schedule is in compliance with Sec. 70.62(c)(3)(ii).
    (c) Submittals by existing licensees in accordance with Sec. 
70.62(c)(3)(ii) will be approved if the Commission determines that:
    (1) The requirements of Sec. 70.65(b) are satisfied; and
    (2) The performance requirements in Sec. 70.61 (b), (c) and (d) are 
satisfied, based on the information in the ISA Summary, together with 
other information submitted to NRC or available to NRC at the licensee's 
site.



Sec. 70.72  Facility changes and change process.

    (a) The licensee shall establish a configuration management system 
to evaluate, implement, and track each change to the site, structures, 
processes, systems, equipment, components, computer programs, and 
activities of personnel. This system must be documented in written 
procedures and must assure that the following are addressed prior to 
implementing any change:
    (1) The technical basis for the change;
    (2) Impact of the change on safety and health or control of licensed 
material;
    (3) Modifications to existing operating procedures including any 
necessary training or retraining before operation;
    (4) Authorization requirements for the change;
    (5) For temporary changes, the approved duration (e.g., expiration 
date) of the change; and
    (6) The impacts or modifications to the integrated safety analysis, 
integrated safety analysis summary, or other safety program information, 
developed in accordance with Sec. 70.62.
    (b) Any change to site, structures, processes, systems, equipment, 
components, computer programs, and activities of personnel must be 
evaluated by the licensee as specified in paragraph (a) of this section, 
before the change is implemented. The evaluation of the change must 
determine, before the change is implemented, if an amendment to the 
license is required to be submitted in accordance with Sec. 70.34.
    (c) The licensee may make changes to the site, structures, 
processes, systems, equipment, components, computer programs, and 
activities of personnel, without prior Commission approval, if the 
change:
    (1) Does not:
    (i) Create new types of accident sequences that, unless mitigated or 
prevented, would exceed the performance requirements of Sec. 70.61 and 
that have not previously been described in the integrated safety 
analysis summary; or
    (ii) Use new processes, technologies, or control systems for which 
the licensee has no prior experience;
    (2) Does not remove, without at least an equivalent replacement of 
the safety function, an item relied on for safety that is listed in the 
integrated safety analysis summary and is necessary for compliance with 
the performance requirements of Sec. 70.61;
    (3) Does not alter any item relied on for safety, listed in the 
integrated safety analysis summary, that is the sole item preventing or 
mitigating an accident sequence that exceeds the performance 
requirements of Sec. 70.61; and
    (4) Is not otherwise prohibited by this section, license condition, 
or order.
    (d)(1) For changes that require pre-approval under Sec. 70.72, the 
licensee shall submit an amendment request to the NRC in accordance with 
Sec. 70.34 and Sec. 70.65 of this chapter.
    (2) For changes that do not require pre-approval under Sec. 70.72, 
the licensee shall submit to NRC annually, within 30 days after the end 
of the calendar year during which the changes occurred, a brief summary 
of all changes

[[Page 335]]

to the records required by Sec. 70.62(a)(2) of this subpart.
    (3) For all changes that affect the integrated safety analysis 
summary, the licensee shall submit to NRC annually, within 30 days after 
the end of the calendar year during which the changes occurred, revised 
integrated safety analysis summary pages.
    (e) If a change covered by Sec. 70.72 is made, the affected on-site 
documentation must be updated promptly.
    (f) The licensee shall maintain records of changes to its facility 
carried out under this section. These records must include a written 
evaluation that provides the bases for the determination that the 
changes do not require prior Commission approval under paragraph (c) or 
(d) of this section. These records must be maintained until termination 
of the license.

[65 FR 56226, Sept. 18, 2000, as amended at 71 FR 56346, Sept. 27, 2006]



Sec. 70.73  Renewal of licenses.

    Applications for renewal of a license must be filed in accordance 
with Sec. Sec. 2.109, 70.21, 70.22, 70.33, 70.38, and 70.65 of this 
chapter. Information contained in previous applications, statements, or 
reports filed with the Commission under the license may be incorporated 
by reference, provided that these references are clear and specific.



Sec. 70.74  Additional reporting requirements.

    (a) Reports to NRC Operations Center. (1) Each licensee shall report 
to the NRC Operations Center the events described in Appendix A to Part 
70.
    (2) Reports must be made by a knowledgeable licensee representative 
and by any method that will ensure compliance with the required time 
period for reporting.
    (3) The information provided must include a description of the event 
and other related information as described in Sec. 70.50(c)(1).
    (4) Follow-up information to the reports must be provided until all 
information required to be reported in Sec. 70.50(c)(1) of this subpart 
is complete.
    (5) Each licensee shall provide reasonable assurance that reliable 
communication with the NRC Operations Center is available during each 
event.
    (b) Written reports. Each licensee that makes a report required by 
paragraph (a)(1) of this section shall submit a written follow-up report 
within 60 days of the initial report. The written report must be sent to 
the NRC's Document Control Desk, using an appropriate method listed in 
Sec. 70.5(a), with a copy to the appropriate NRC regional office listed 
in appendix D to part 20 of this chapter. The reports must include the 
information as described in Sec. 70.50(c)(2)(i) through (iv).

[65 FR 56226, Sept. 18, 2000, as amended at 79 FR 57725, Sept. 26, 2014]



Sec. 70.76  Backfitting.

    (a) For each licensee, this provision shall apply to Subpart H 
requirements as soon as the NRC approves that licensee's ISA Summary 
pursuant to Sec. 70.66. For requirements other than Subpart H, this 
provision applies regardless of the status of the approval of a 
licensee's ISA Summary.
    (1) Backfitting is defined as the modification of, or addition to, 
systems, structures, or components of a facility; or to the procedures 
or organization required to operate a facility; any of which may result 
from a new or amended provision in the Commission rules or the 
imposition of a regulatory staff position interpreting the Commission 
rules that is either new or different from a previous NRC staff 
position.
    (2) Except as provided in paragraph (a)(4) of this section, the 
Commission shall require a systematic and documented analysis pursuant 
to paragraph (b) of this section for backfits which it seeks to impose.
    (3) Except as provided in paragraph (a)(4) of this section, the 
Commission shall require the backfitting of a facility only when it 
determines, based on the analysis described in paragraph (b) of this 
section, that there is a substantial increase in the overall protection 
of the public health and safety or the common defense and security to be 
derived from the backfit and that the direct and indirect costs of 
implementation for that facility are justified in view of this increased 
protection.
    (4) The provisions of paragraphs (a)(2) and (a)(3) of this section 
are inapplicable and, therefore, backfit analysis is

[[Page 336]]

not required and the standards in paragraph (a)(3) of this section do 
not apply where the Commission finds and declares, with appropriately 
documented evaluation for its finding, any of the following:
    (i) That a modification is necessary to bring a facility into 
compliance with Subpart H of this part;
    (ii) That a modification is necessary to bring a facility into 
compliance with a license or the rules or orders of the Commission, or 
into conformance with written commitments by the licensee;
    (iii) That regulatory action is necessary to ensure that the 
facility provides adequate protection to the health and safety of the 
public and is in accord with the common defense and security; or
    (iv) That the regulatory action involves defining or redefining what 
level of protection to the public health and safety or common defense 
and security should be regarded as adequate.
    (5) The Commission shall always require the backfitting of a 
facility if it determines that the regulatory action is necessary to 
ensure that the facility provides adequate protection to the health and 
safety of the public and is in accord with the common defense and 
security.
    (6) The documented evaluation required by paragraph (a)(4) of this 
section must include a statement of the objectives of and reasons for 
the modification and the basis for invoking the exception. If immediate 
effective regulatory action is required, then the documented evaluation 
may follow, rather than precede, the regulatory action.
    (7) If there are two or more ways to achieve compliance with a 
license or the rules or orders of the Commission, or with written 
license commitments, or there are two or more ways to reach an adequate 
level of protection, then ordinarily the licensee is free to choose the 
way that best suits its purposes. However, should it be necessary or 
appropriate for the Commission to prescribe a specific way to comply 
with its requirements or to achieve adequate protection, then cost may 
be a factor in selecting the way, provided that the objective of 
compliance or adequate protection is met.
    (b) In reaching the determination required by paragraph (a)(3) of 
this section, the Commission will consider how the backfit should be 
scheduled in light of other ongoing regulatory activities at the 
facility and, in addition, will consider information available 
concerning any of the following factors as may be appropriate and any 
other information relevant and material to the proposed backfit:
    (1) Statement of the specific objectives that the proposed backfit 
is designed to achieve;
    (2) General description of the activity that would be required by 
the licensee in order to complete the backfit;
    (3) Potential change in the risk to the public from the accidental 
release of radioactive material and hazardous chemicals produced from 
licensed material;
    (4) Potential impact on radiological exposure or exposure to 
hazardous chemicals produced from licensed material of facility 
employees;
    (5) Installation and continuing costs associated with the backfit, 
including the cost of facility downtime;
    (6) The potential safety impact of changes in facility or 
operational complexity, including the relationship to proposed and 
existing regulatory requirements;
    (7) The estimated resource burden on the NRC associated with the 
proposed backfit and the availability of such resources;
    (8) The potential impact of differences in facility type, design, or 
age on the relevancy and practicality of the proposed backfit; and
    (9) Whether the proposed backfit is interim or final and, if 
interim, the justification for imposing the proposed backfit on an 
interim basis.
    (c) No license will be withheld during the pendency of backfit 
analyses required by the Commission's rules.
    (d) The Executive Director for Operations shall be responsible for 
implementation of this section, and all analyses required by this 
section shall be approved by the Executive Director for Operations or 
his or her designee.

[65 FR 56226, Sept. 18, 2000]

[[Page 337]]



            Subpart I_Modification and Revocation of Licenses



Sec. 70.81  Modification and revocation of licenses.

    (a) The terms and conditions of all licenses shall be subject to 
amendment, revision, or modification by reason of amendments to the 
Atomic Energy Act of 1954, or by reason of rules, regulations or orders 
issued in accordance with the Act or any amendments thereto;
    (b) Any license may be revoked, suspended or modified for any 
material false statements in the application or any statement of fact 
required under section 182 of the Act or because of conditions revealed 
by such application or statement of fact or any report, record, or 
inspection or other means which would warrant the Commission to refuse 
to grant a license on an original application, or for failure to 
construct or operate a facility in accordance with the terms of the 
construction permit or license, the technical specifications in the 
application, or for violation of, or failure to observe any of the terms 
and conditions of the Act, or of any regulation of the Commission.
    (c) Upon revocation, suspension or modification of a license, the 
Commission may immediately retake possession of all special nuclear 
material held by the licensee. In cases found by the Commission to be of 
extreme importance to the national defense or security, or to the health 
and safety of the public, the Commission may recapture any special 
nuclear material held by the licensee prior to any of the procedures 
provided under section 551-558 of title 5 of the United States Code.
    (d) Except in cases of willfulness or those in which the public 
health, interest or safety requires otherwise, no license shall be 
modified, suspended or revoked unless, prior to the institution of 
proceedings therefor, facts or conduct which may warrant such action 
shall have been called to the attention of the licensee in writing and 
the licensee shall have been accorded opportunity to demonstrate or 
achieve compliance with all lawful requirements.

[21 FR 764, Feb. 3, 1956, as amended at 35 FR 11461, July 17, 1970. 
Redesignated at 65 FR 56226, Sept. 18, 2000]



Sec. 70.82  Suspension and operation in war or national emergency.

    Whenever Congress declares that a state of war or national emergency 
exists, the Commission, if it finds it necessary to the common defense 
and security may,
    (a) Suspend any license it has issued.
    (b) Order the recapture of special nuclear material.
    (c) Order the operation of any licensed facility.
    (d) Order entry into any plant or facility in order to recapture 
special nuclear material or to operate the facility. Just compensation 
shall be paid for any damages caused by recapture of special nuclear 
material or by operation of any facility, pursuant to this section.

[21 FR 764, Feb. 3, 1956, as amended at 32 FR 4056, Mar. 15, 1967; 35 FR 
11461, July 17, 1970. Redesignated at 65 FR 56226, Sept. 18, 2000]



                          Subpart J_Enforcement



Sec. 70.91  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the

[[Page 338]]

sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55077, Nov. 24, 1992. Redesignated at 65 FR 56226, Sept. 18, 
2000]



Sec. 70.92  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 70 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 70 that are not issued under sections 
161b, 161i, or 161o, for the purposes of section 223 are as follows: 
Sec. Sec. 70.1, 70.2, 70.4, 70.5, 70.6, 70.8, 70.11, 70.12, 70.13, 
70.14, 70.17, 70.18, 70.23, 70.31, 70.33, 70.34, 70.35, 70.37, 70.66, 
70.73, 70.76, 70.81, 70.82, 70.63, 70.91, and 70.92.

[57 FR 55077, Nov. 24, 1992. Redesignated and amended at 65 FR 56226, 
Sept. 18, 2000]



          Sec. Appendix A to Part 70--Reportable Safety Events

    Licensees must comply with reporting requirements in this appendix. 
As required by 10 CFR 70.74, licensees subject to the requirements in 
subpart H of part 70, shall report:
    (a) One hour reports. Events to be reported to the NRC Operations 
Center within 1 hour of discovery, supplemented with the information in 
10 CFR 70.50(c)(1) as it becomes available, followed by a written report 
within 60 days:
    (1) An inadvertent nuclear criticality.
    (2) An acute intake by an individual of 30 mg or greater of uranium 
in a soluble form.
    (3) An acute chemical exposure to an individual from licensed 
material or hazardous chemicals produced from licensed material that 
exceeds the quantitative standards established to satisfy the 
requirements in Sec. 70.61(b)(4).
    (4) An event or condition such that no items relied on for safety, 
as documented in the Integrated Safety Analysis summary, remain 
available and reliable, in an accident sequence evaluated in the 
Integrated Safety Analysis, to perform their function:
    (i) In the context of the performance requirements in Sec. 70.61(b) 
and Sec. 70.61(c), or
    (ii) Prevent a nuclear criticality accident (i.e., loss of all 
controls in a particular sequence).
    (b) Twenty-four hour reports. Events to be reported to the NRC 
Operations Center within 24 hours of discovery, supplemented with the 
information in 10 CFR 70.50(c)(1) as it becomes available, followed by a 
written report within 60 days:
    (1) Any event or condition that results in the facility being in a 
state that was not analyzed, was improperly analyzed, or is different 
from that analyzed in the Integrated Safety Analysis, and which results 
in failure to meet the performance requirements of Sec. 70.61.
    (2) Loss or degradation of items relied on for safety that results 
in failure to meet the performance requirement of Sec. 70.61.
    (3) An acute chemical exposure to an individual from licensed 
material or hazardous chemicals produced from licensed materials that 
exceeds the quantitative standards that satisfy the requirements of 
Sec. 70.61(c)(4).
    (4) Any natural phenomenon or other external event, including fires 
internal and external to the facility, that has affected or may have 
affected the intended safety function or availability or reliability of 
one or more items relied on for safety.
    (c) Concurrent Reports. Any event or situation, related to the 
health and safety of the public or onsite personnel, or protection of 
the environment, for which a news release is planned or notification to 
other government agencies has been or will be made, shall be reported to 
the NRC Operations Center concurrent to the news release or other 
notification.

[65 FR 56231, Sept. 18, 2000, as amended at 75 FR 73944, Nov. 30, 2010; 
79 FR 57725, Sept. 26, 2014]



PART 71_PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL--
Table of Contents



                      Subpart A_General Provisions

Sec.
71.0 Purpose and scope.
71.1 Communications and records.
71.2 Interpretations.
71.3 Requirement for license.
71.4 Definitions.
71.5 Transportation of licensed material.
71.6 Information collection requirements: OMB approval.
71.7 Completeness and accuracy of information.
71.8 Deliberate misconduct.
71.9 Employee protection.
71.10 Public inspection of application.
71.11 Protection of Safeguards Information.

[[Page 339]]

                          Subpart B_Exemptions

71.12 Specific exemptions.
71.13 Exemption of physicians.
71.14 Exemption for low-level materials.
71.15 Exemption from classification as fissile material.
71.16 [Reserved]

                       Subpart C_General Licenses

71.17 General license: NRC-approved package.
71.18 [Reserved]
71.19 Previously approved package.
71.21 General license: Use of foreign approved package.
71.22 General license: Fissile material.
71.23 General license: Plutonium-beryllium special form material.
71.24-71.25 [Reserved]

               Subpart D_Application for Package Approval

71.31 Contents of application.
71.33 Package description.
71.35 Package evaluation.
71.37 Quality assurance.
71.38 Renewal of a certificate of compliance.
71.39 Requirement for additional information.

                  Subpart E_Package Approval Standards

71.41 Demonstration of compliance.
71.43 General standards for all packages.
71.45 Lifting and tie-down standards for all packages.
71.47 External radiation standards for all packages.
71.51 Additional requirements for Type B packages.
71.53 [Reserved]
71.55 General requirements for fissile material packages.
71.57 [Reserved]
71.59 Standards for arrays of fissile material packages.
71.61 Special requirements for Type B packages containing more than 
          105A2.
71.63 Special requirement for plutonium shipments.
71.64 Special requirements for plutonium air shipments.
71.65 Additional requirements.

           Subpart F_Package, Special Form, and LSA-III Tests

71.70 Incorporation by reference.
71.71 Normal conditions of transport.
71.73 Hypothetical accident conditions.
71.74 Accident conditions for air transport of plutonium.
71.75 Qualification of special form radioactive material.
71.77 Qualification of LSA-III Material.

               Subpart G_Operating Controls and Procedures

71.81 Applicability of operating controls and procedures.
71.83 Assumptions as to unknown properties.
71.85 Preliminary determinations.
71.87 Routine determinations.
71.88 Air transport of plutonium.
71.89 Opening instructions.
71.91 Records.
71.93 Inspection and tests.
71.95 Reports.
71.97 Advance notification of shipment of irradiated reactor fuel and 
          nuclear waste.
71.99 Violations.
71.100 Criminal penalties.

                       Subpart H_Quality Assurance

71.101 Quality assurance requirements.
71.103 Quality assurance organization.
71.105 Quality assurance program.
71.106 Changes to quality assurance program.
71.107 Package design control.
71.109 Procurement document control.
71.111 Instructions, procedures, and drawings.
71.113 Document control.
71.115 Control of purchased material, equipment, and services.
71.117 Identification and control of materials, parts, and components.
71.119 Control of special processes.
71.121 Internal inspection.
71.123 Test control.
71.125 Control of measuring and test equipment.
71.127 Handling, storage, and shipping control.
71.129 Inspection, test, and operating status.
71.131 Nonconforming materials, parts, or components.
71.133 Corrective action.
71.135 Quality assurance records.
71.137 Audits.

Appendix A to Part 71--Determination of A1 and A2

    Authority: Atomic Energy Act of 1954, secs. 53, 57, 62, 63, 81, 161, 
182, 183, 223, 234, 1701 (42 U.S.C. 2073, 2077, 2092, 2093, 2111, 2201, 
2232, 2233, 2273, 2282, 2297f); Energy Reorganization Act of 1974, secs. 
201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste 
Policy Act of 1982, sec. 180 (42 U.S.C. 10175); 44 U.S.C. 3504 note.
    Section 71.97 also issued under Sec. 301, Pub. L. 96-295, 94 Stat. 
789 (42 U.S.C. 5841 note).

    Source: 60 FR 50264, Sept. 28, 1995, unless otherwise noted.

[[Page 340]]



                      Subpart A_General Provisions

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.



Sec. 71.0  Purpose and scope.

    (a) This part establishes--
    (1) Requirements for packaging, preparation for shipment, and 
transportation of licensed material; and
    (2) Procedures and standards for NRC approval of packaging and 
shipping procedures for fissile material and for a quantity of other 
licensed material in excess of a Type A quantity.
    (b) The packaging and transport of licensed material are also 
subject to other parts of this chapter (e.g., 10 CFR parts 20, 21, 30, 
40, 70, and 73) and to the regulations of other agencies (e.g., the U.S. 
Department of Transportation (DOT) and the U.S. Postal Service) \1\ 
having jurisdiction over means of transport. The requirements of this 
part are in addition to, and not in substitution for, other 
requirements.
---------------------------------------------------------------------------

    \1\ Postal Service manual (Domestic Mail Manual), Section 124, which 
is incorporated by reference at 39 CFR 111.1.
---------------------------------------------------------------------------

    (c) The regulations in this part apply to any licensee authorized by 
specific or general license issued by the Commission to receive, 
possess, use, or transfer licensed material, if the licensee delivers 
that material to a carrier for transport, transports the material 
outside the site of usage as specified in the NRC license, or transports 
that material on public highways. No provision of this part authorizes 
possession of licensed material.
    (d)(1) Exemptions from the requirement for license in Sec. 71.3 are 
specified in Sec. 71.14. General licenses for which no NRC package 
approval is required are issued in Sec. Sec. 71.21 through 71.23. The 
general license in Sec. 71.17 requires that an NRC certificate of 
compliance or other package approval be issued for the package to be 
used under this general license.
    (2) Application for package approval must be completed in accordance 
with subpart D of this part, demonstrating that the design of the 
package to be used satisfies the package approval standards contained in 
subpart E of this part, as related to the tests of subpart F of this 
part.
    (3) A licensee transporting licensed material, or delivering 
licensed material to a carrier for transport, shall comply with the 
operating control requirements of subpart G of this part; the quality 
assurance requirements of subpart H of this part; and the general 
provisions of subpart A of this part, including DOT regulations 
referenced in Sec. 71.5.
    (e) The regulations of this part apply to any person holding, or 
applying for, a certificate of compliance, issued pursuant to this part, 
for a package intended for the transportation of radioactive material, 
outside the confines of a licensee's facility or authorized place of 
use.
    (f) The regulations in this part apply to any person required to 
obtain a certificate of compliance, or an approved compliance plan, 
pursuant to part 76 of this chapter, if the person delivers radioactive 
material to a common or contract carrier for transport or transports the 
material outside the confines of the person's plant or other authorized 
place of use.
    (g) This part also gives notice to all persons who knowingly provide 
to any licensee, certificate holder, quality assurance program approval 
holder, applicant for a license, certificate, or quality assurance 
program approval, or to a contractor, or subcontractor of any of them, 
components, equipment, materials, or other goods or services, that 
relate to a licensee's, certificate holder's, quality assurance program 
approval holder's, or applicant's activities subject to this part, that 
they may be individually subject to NRC enforcement action for violation 
of Sec. 71.8.

[69 FR 3786, Jan. 26, 2004, as amended at 80 FR 34011, June 12, 2015]



Sec. 71.1  Communications and records.

    (a) Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk, 
Director, Division of Spent Fuel Management, Office of Nuclear Material 
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001, by

[[Page 341]]

hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland; or, where practicable, by electronic submission, for example, 
via Electronic Information Exchange, or CD-ROM. Electronic submissions 
must be made in a manner that enables the NRC to receive, read, 
authenticate, distribute, and archive the submission, and process and 
retrieve it a single page at a time. Detailed guidance on making 
electronic submissions can be obtained by visiting the NRC's Web site at 
http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information. If the submission date falls on a Saturday, Sunday, or a 
Federal holiday, the next Federal working day becomes the official due 
date.
    (b) Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform provided that the 
copy or microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period. The record may also be stored in electronic media with 
the capability for producing legible, accurate, and complete records 
during the required retention period. Records such as letters, drawings, 
and specifications must include all pertinent information such as 
stamps, initials, and signatures. The licensee shall maintain adequate 
safeguards against tampering with and loss of records.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004, as amended at 
74 FR 62683, Dec. 1, 2009; 75 FR 73945, Nov. 30, 2010; 79 FR 75741, Dec. 
19, 2014; 80 FR 74981, Dec. 1, 2015]



Sec. 71.2  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission, other than a written 
interpretation by the General Counsel, will be recognized to be binding 
upon the Commission.



Sec. 71.3  Requirement for license.

    Except as authorized in a general license or a specific license 
issued by the Commission, or as exempted in this part, no licensee may--
    (a) Deliver licensed material to a carrier for transport; or
    (b) Transport licensed material.



Sec. 71.4  Definitions.

    The following terms are as defined here for the purpose of this 
part. To ensure compatibility with international transportation 
standards, all limits in this part are given in terms of dual units: The 
International System of Units (SI) followed or preceded by U.S. standard 
or customary units. The U.S. customary units are not exact equivalents 
but are rounded to a convenient value, providing a functionally 
equivalent unit. For the purpose of this part, either unit may be used.
    A1 means the maximum activity of special form radioactive material 
permitted in a Type A package. This value is either listed in Appendix 
A, Table A-1, of this part, or may be derived in accordance with the 
procedures prescribed in Appendix A of this part.
    A2 means the maximum activity of radioactive material, other than 
special form material, LSA, and SCO material, permitted in a Type A 
package. This value is either listed in Appendix A, Table A-1, of this 
part, or may be derived in accordance with the procedures prescribed in 
Appendix A of this part.
    Carrier means a person engaged in the transportation of passengers 
or property by land or water as a common, contract, or private carrier, 
or by civil aircraft.
    Certificate holder means a person who has been issued a certificate 
of compliance or other package approval by the Commission.
    Certificate of Compliance (CoC) means the certificate issued by the 
Commission under subpart D of this part which approves the design of a 
package for the transportation of radioactive material.

[[Page 342]]

    Close reflection by water means immediate contact by water of 
sufficient thickness for maximum reflection of neutrons.
    Consignment means each shipment of a package or groups of packages 
or load of radioactive material offered by a shipper for transport.
    Containment system means the assembly of components of the packaging 
intended to retain the radioactive material during transport.
    Contamination means the presence of a radioactive substance on a 
surface in quantities in excess of 0.4 Bq/cm\2\ (1 x 10-5 
[micro]Ci/cm\2\) for beta and gamma emitters and low toxicity alpha 
emitters, or 0.04 Bq/cm\2\ (1 x 10-6 [micro]Ci/cm\2\) for all 
other alpha emitters.
    (1) Fixed contamination means contamination that cannot be removed 
from a surface during normal conditions of transport.
    (2) Non-fixed contamination means contamination that can be removed 
from a surface during normal conditions of transport.
    Conveyance means:
    (1) For transport by public highway or rail any transport vehicle or 
large freight container;
    (2) For transport by water any vessel, or any hold, compartment, or 
defined deck area of a vessel including any transport vehicle on board 
the vessel; and
    (3) For transport by any aircraft.
    Criticality Safety Index (CSI) means the dimensionless number 
(rounded up to the next tenth) assigned to and placed on the label of a 
fissile material package, to designate the degree of control of 
accumulation of packages, overpacks or freight containers containing 
fissile material during transportation. Determination of the criticality 
safety index is described in Sec. Sec. 71.22, 71.23, and 71.59. The 
criticality safety index for an overpack, freight container, consignment 
or conveyance containing fissile material packages is the arithmetic sum 
of the criticality safety indices of all the fissile material packages 
contained within the overpack, freight container, consignment or 
conveyance.
    Deuterium means, for the purposes of Sec. Sec. 71.15 and 71.22, 
deuterium and any deuterium compounds, including heavy water, in which 
the ratio of deuterium atoms to hydrogen atoms exceeds 1:5000.
    DOT means the U.S. Department of Transportation.
    Exclusive use means the sole use by a single consignor of a 
conveyance for which all initial, intermediate, and final loading and 
unloading are carried out in accordance with the direction of the 
consignor or consignee. The consignor and the carrier must ensure that 
any loading or unloading is performed by personnel having radiological 
training and resources appropriate for safe handling of the consignment. 
The consignor must issue specific instructions, in writing, for 
maintenance of exclusive use shipment controls, and include them with 
the shipping paper information provided to the carrier by the consignor.
    Fissile material means the radionuclides uranium-233, uranium-235, 
plutonium-239, and plutonium-241, or any combination of these 
radionuclides. Fissile material means the fissile nuclides themselves, 
not material containing fissile nuclides. Unirradiated natural uranium 
and depleted uranium and natural uranium or depleted uranium, that has 
been irradiated in thermal reactors only, are not included in this 
definition. Certain exclusions from fissile material controls are 
provided in Sec. 71.15.
    Graphite means, for the purposes of Sec. Sec. 71.15 and 71.22, 
graphite with a boron equivalent content less than 5 parts per million 
and density greater than 1.5 grams per cubic centimeter.
    Indian tribe means an Indian or Alaska Native Tribe, band, nation, 
pueblo, village, or community that the Secretary of the Interior 
acknowledges to exist as an Indian Tribe pursuant to the Federally 
Recognized Indian Tribe List Act of 1994, 25 U.S.C. 5130.
    Licensed material means byproduct, source, or special nuclear 
material received, possessed, used, or transferred under a general or 
specific license issued by the Commission pursuant to the regulations in 
this chapter.
    Low Specific Activity (LSA) material means radioactive material with 
limited specific activity which is nonfissile or is excepted under Sec. 
71.15, and which satisfies the descriptions

[[Page 343]]

and limits set forth in the following section. Shielding materials 
surrounding the LSA material may not be considered in determining the 
estimated average specific activity of the package contents. The LSA 
material must be in one of three groups:
    (1) LSA-I.
    (i) Uranium and thorium ores, concentrates of uranium and thorium 
ores, and other ores containing naturally occurring radionuclides that 
are intended to be processed for the use of these radionuclides;
    (ii) Natural uranium, depleted uranium, natural thorium or their 
compounds or mixtures, provided they are unirradiated and in solid or 
liquid form;
    (iii) Radioactive material other than fissile material, for which 
the A2 value is unlimited; or
    (iv) Other radioactive material in which the activity is distributed 
throughout and the estimated average specific activity does not exceed 
30 times the value for exempt material activity concentration determined 
in accordance with appendix A.
    (2) LSA-II.
    (i) Water with tritium concentration up to 0.8 TBq/liter (20.0 Ci/
liter); or
    (ii) Other radioactive material in which the activity is distributed 
throughout and the estimated average specific activity does not exceed 
10-4 A2/g for solids and gases, and 
10-5 A2/g for liquids.
    (3) LSA-III. Solids (e.g., consolidated wastes, activated 
materials), excluding powders, that satisfy the requirements of Sec. 
71.77, in which:
    (i) The radioactive material is distributed throughout a solid or a 
collection of solid objects, or is essentially uniformly distributed in 
a solid compact binding agent (such as concrete, bitumen, ceramic, 
etc.);
    (ii) The radioactive material is relatively insoluble, or it is 
intrinsically contained in a relatively insoluble material, so that even 
under loss of packaging, the loss of radioactive material per package by 
leaching when placed in water for 7 days will not exceed 0.1 
A2; and
    (iii) The estimated average specific activity of the solid, 
excluding any shielding material, does not exceed 2 x 10-3 
A2/g.
    Low toxicity alpha emitters means natural uranium, depleted uranium, 
natural thorium; uranium-235, uranium-238, thorium-232, thorium-228 or 
thorium-230 when contained in ores or physical or chemical concentrates 
or tailings; or alpha emitters with a half-life of less than 10 days.
    Maximum normal operating pressure means the maximum gauge pressure 
that would develop in the containment system in a period of 1 year under 
the heat condition specified in Sec. 71.71(c)(1), in the absence of 
venting, external cooling by an ancillary system, or operational 
controls during transport.
    Natural thorium means thorium with the naturally occurring 
distribution of thorium isotopes (essentially 100 weight percent 
thorium-232).
    Normal form radioactive material means radioactive material that has 
not been demonstrated to qualify as ``special form radioactive 
material.''
    Optimum interspersed hydrogenous moderation means the presence of 
hydrogenous material between packages to such an extent that the maximum 
nuclear reactivity results.
    Package means the packaging together with its radioactive contents 
as presented for transport.
    (1) Fissile material package or Type AF package, Type BF package, 
Type B(U)F package, or Type B(M)F package means a fissile material 
packaging together with its fissile material contents.
    (2) Type A package means a Type A packaging together with its 
radioactive contents. A Type A package is defined and must comply with 
the DOT regulations in 49 CFR part 173.
    (3) Type B package means a Type B packaging together with its 
radioactive contents. On approval, a Type B package design is designated 
by NRC as B(U) unless the package has a maximum normal operating 
pressure of more than 700 kPa (100 lbs/in\2\) gauge or a pressure relief 
device that would allow the release of radioactive material to the 
environment under the tests specified in Sec. 71.73 (hypothetical 
accident conditions), in which case it will receive a designation B(M). 
B(U) refers to the need for unilateral approval of

[[Page 344]]

international shipments; B(M) refers to the need for multilateral 
approval of international shipments. There is no distinction made in how 
packages with these designations may be used in domestic transportation. 
To determine their distinction for international transportation, see DOT 
regulations in 49 CFR Part 173. A Type B package approved before 
September 6, 1983, was designated only as Type B. Limitations on its use 
are specified in Sec. 71.19.
    Packaging means the assembly of components necessary to ensure 
compliance with the packaging requirements of this part. It may consist 
of one or more receptacles, absorbent materials, spacing structures, 
thermal insulation, radiation shielding, and devices for cooling or 
absorbing mechanical shocks. The vehicle, tie-down system, and auxiliary 
equipment may be designated as part of the packaging.
    Special form radioactive material means radioactive material that 
satisfies the following conditions:
    (1) It is either a single solid piece or is contained in a sealed 
capsule that can be opened only by destroying the capsule;
    (2) The piece or capsule has at least one dimension not less than 5 
mm (0.2 in); and
    (3) It satisfies the requirements of Sec. 71.75. A special form 
encapsulation designed in accordance with the requirements of Sec. 71.4 
in effect on June 30, 1983 (see 10 CFR part 71, revised as of January 1, 
1983), and constructed before July 1, 1985; a special form encapsulation 
designed in accordance with the requirements of Sec. 71.4 in effect on 
March 31, 1996 (see 10 CFR part 71, revised as of January 1, 1996), and 
constructed before April 1, 1998; and special form material that was 
successfully tested before September 10, 2015 in accordance with the 
requirements of Sec. 71.75(d) of this section in effect before 
September 10, 2015 may continue to be used. Any other special form 
encapsulation must meet the specifications of this definition.
    Specific activity of a radionuclide means the radioactivity of the 
radionuclide per unit mass of that nuclide. The specific activity of a 
material in which the radionuclide is essentially uniformly distributed 
is the radioactivity per unit mass of the material.
    Spent nuclear fuel or Spent fuel means fuel that has been withdrawn 
from a nuclear reactor following irradiation, has undergone at least 1 
year's decay since being used as a source of energy in a power reactor, 
and has not been chemically separated into its constituent elements by 
reprocessing. Spent fuel includes the special nuclear material, 
byproduct material, source material, and other radioactive materials 
associated with fuel assemblies.
    State means a State of the United States, the District of Columbia, 
the Commonwealth of Puerto Rico, the Virgin Islands, Guam, American 
Samoa, and the Commonwealth of the Northern Mariana Islands.
    Surface Contaminated Object (SCO) means a solid object that is not 
itself classed as radioactive material, but which has radioactive 
material distributed on any of its surfaces. SCO must be in one of two 
groups with surface activity not exceeding the following limits:
    (1) SCO-I: A solid object on which:
    (i) The nonfixed contamination on the accessible surface averaged 
over 300 cm\2\ (or the area of the surface if less than 300 cm\2\) does 
not exceed 4 Bq/cm\2\ (10-4 microcurie/cm\2\) for beta and 
gamma and low toxicity alpha emitters, or 0.4 Bq/cm\2\ (10-5 
microcurie/cm\2\) for all other alpha emitters;
    (ii) The fixed contamination on the accessible surface averaged over 
300 cm\2\ (or the area of the surface if less than 300 cm\2\) does not 
exceed 4 x 10\4\ Bq/cm\2\ (1.0 microcurie/cm\2\) for beta and gamma and 
low toxicity alpha emitters, or 4 x 10\3\ Bq/cm\2\ (0.1 microcurie/
cm\2\) for all other alpha emitters; and
    (iii) The nonfixed contamination plus the fixed contamination on the 
inaccessible surface averaged over 300 cm\2\ (or the area of the surface 
if less than 300 cm\2\) does not exceed 4 x 10\4\ Bq/cm\2\ (1 
microcurie/cm\2\) for beta and gamma and low toxicity alpha emitters, or 
4 x 10\3\ Bq/cm\2\ (0.1 microcurie/cm\2\) for all other alpha emitters.
    (2) SCO-II: A solid object on which the limits for SCO-I are 
exceeded and on which:

[[Page 345]]

    (i) The nonfixed contamination on the accessible surface averaged 
over 300 cm\2\ (or the area of the surface if less than 300 cm\2\) does 
not exceed 400 Bq/cm\2\ (10-2 microcurie/cm\2\) for beta and 
gamma and low toxicity alpha emitters or 40 Bq/cm\2\ (10-3 
microcurie/cm\2\) for all other alpha emitters;
    (ii) The fixed contamination on the accessible surface averaged over 
300 cm\2\ (or the area of the surface if less than 300 cm\2\) does not 
exceed 8 x 10\5\ Bq/cm\2\ (20 microcuries/cm\2\) for beta and gamma and 
low toxicity alpha emitters, or 8 x 10\4\ Bq/cm\2\ (2 microcuries/cm\2\) 
for all other alpha emitters; and
    (iii) The nonfixed contamination plus the fixed contamination on the 
inaccessible surface averaged over 300 cm\2\ (or the area of the surface 
if less than 300 cm\2\) does not exceed 8 x 10\5\ Bq/cm\2\ (20 
microcuries/cm\2\) for beta and gamma and low toxicity alpha emitters, 
or 8 x 10\4\ Bq/cm\2\ (2 microcuries/cm\2\) for all other alpha 
emitters.
    Transport index (TI) means the dimensionless number (rounded up to 
the next tenth) placed on the label of a package, to designate the 
degree of control to be exercised by the carrier during transportation. 
The transport index is the number determined by multiplying the maximum 
radiation level in millisievert (mSv) per hour at 1 meter (3.3 ft) from 
the external surface of the package by 100 (equivalent to the maximum 
radiation level in millirem per hour at 1 meter (3.3 ft)).
    Tribal official means the highest ranking individual that represents 
Tribal leadership, such as the Chief, President, or Tribal Council 
leadership.
    Type A quantity means a quantity of radioactive material, the 
aggregate radioactivity of which does not exceed A1 for 
special form radioactive material, or A2, for normal form 
radioactive material, where A1 and A2 are given in 
Table A-1 of this part, or may be determined by procedures described in 
Appendix A of this part.
    Type B quantity means a quantity of radioactive material greater 
than a Type A quantity.
    Unirradiated uranium means uranium containing not more than 2 x 
10\3\ Bq of plutonium per gram of uranium-235, not more than 9 x 10\6\ 
Bq of fission products per gram of uranium-235, and not more than 5 x 
10-3 g of uranium-236 per gram of uranium-235.
    Uranium--natural, depleted, enriched. (1) Natural uranium means 
uranium (which may be chemically separated) with the naturally occurring 
distribution of uranium isotopes (approximately 0.711 weight percent 
uranium-235, and the remainder by weight essentially uranium-238).
    (2) Depleted uranium means uranium containing less uranium-235 than 
the naturally occurring distribution of uranium isotopes.
    (3) Enriched uranium means uranium containing more uranium-235 than 
the naturally occurring distribution of uranium isotopes.

[69 FR 3786, Jan. 26, 2004, as amended at 69 FR 58038, Sept. 29, 2004; 
77 FR 34204, June 11, 2012; 80 FR 34011, June 12, 2015; 80 FR 48684, 
Aug. 14, 2015; 80 FR 74981, Dec. 1, 2015; 82 FR 52825, Nov. 15, 2017]



Sec. 71.5  Transportation of licensed material.

    (a) Each licensee who transports licensed material outside the site 
of usage, as specified in the NRC license, or where transport is on 
public highways, or who delivers licensed material to a carrier for 
transport, shall comply with the applicable requirements of the DOT 
regulations in 49 CFR parts 107, 171 through 180, and 390 through 397, 
appropriate to the mode of transport.
    (1) The licensee shall particularly note DOT regulations in the 
following areas:
    (i) Packaging--49 CFR part 173: subparts A, B, and I.
    (ii) Marking and labeling--49 CFR part 172: subpart D; and 
Sec. Sec. 172.400 through 172.407 and Sec. Sec. 172.436 through 
172.441 of subpart E.
    (iii) Placarding--49 CFR part 172: subpart F, especially Sec. Sec. 
172.500 through 172.519 and 172.556; and appendices B and C.
    (iv) Accident reporting--49 CFR part 171: Sec. Sec. 171.15 and 
171.16.
    (v) Shipping papers and emergency information--49 CFR part 172: 
subparts C and G.
    (vi) Hazardous material employee training--49 CFR part 172: subpart 
H.

[[Page 346]]

    (vii) Security plans--49 CFR part 172: subpart I.
    (viii) Hazardous material shipper/carrier registration--49 CFR part 
107: subpart G.
    (2) The licensee shall also note DOT regulations pertaining to the 
following modes of transportation:
    (i) Rail--49 CFR part 174: subparts A through D and K.
    (ii) Air--49 CFR part 175.
    (iii) Vessel--49 CFR part 176: subparts A through F and M.
    (iv) Public Highway--49 CFR part 177 and parts 390 through 397.
    (b) If DOT regulations are not applicable to a shipment of licensed 
material, the licensee shall conform to the standards and requirements 
of the DOT specified in paragraph (a) of this section to the same extent 
as if the shipment or transportation were subject to DOT regulations. A 
request for modification, waiver, or exemption from those requirements, 
and any notification referred to in those requirements, must be filed 
with, or made to, the Director, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]



Sec. 71.6  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0008.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 71.5, 71.7, 71.9, 71.12, 71.17, 71.19, 
71.22, 71.23, 71.31, 71.33, 71.35, 71.37, 71.38, 71.39, 71.41, 71.47, 
71.85, 71.87, 71.89, 71.91, 71.93, 71.95, 71.97, 71.101, 71.103, 71.105, 
71.106, 71.107, 71.109, 71.111, 71.113, 71.115, 71.117, 71.119, 71.121, 
71.123, 71.125, 71.127, 71.129, 71.131, 71.133, 71.135, 71.137, and 
appendix A, paragraph II.

[69 FR 3786, Jan. 26, 2004, as amended at 75 FR 73945, Nov. 30, 2010; 80 
FR 34012, June 12, 2015]



Sec. 71.7  Completeness and accuracy of information.

    (a) Information provided to the Commission by a licensee, 
certificate holder, or an applicant for a license or CoC; or information 
required by statute or by the Commission's regulations, orders, license 
or CoC conditions, to be maintained by the licensee or certificate 
holder, must be complete and accurate in all material respects.
    (b) Each licensee, certificate holder, or applicant for a license or 
CoC must notify the Commission of information identified by the 
licensee, certificate holder, or applicant for a license or CoC as 
having, for the regulated activity, a significant implication for public 
health and safety or common defense and security. A licensee, 
certificate holder, or an applicant for a license or CoC violates this 
paragraph only if the licensee, certificate holder, or applicant for a 
license or CoC fails to notify the Commission of information that the 
licensee, certificate holder, or applicant for a license or CoC has 
identified as having a significant implication for public health and 
safety or common defense and security. Notification must be provided to 
the Administrator of the appropriate Regional Office within 2 working 
days of identifying the information. This requirement is not applicable 
to information which is already required to be provided to the 
Commission by other reporting or updating requirements.



Sec. 71.8  Deliberate misconduct.

    (a) This section applies to any--
    (1) Licensee;
    (2) Certificate holder;
    (3) Quality assurance program approval holder;
    (4) Applicant for a license, certificate, or quality assurance 
program approval;
    (5) Contractor (including a supplier or consultant) or 
subcontractor, to any person identified in paragraph (a)(4) of this 
section; or

[[Page 347]]

    (6) Employees of any person identified in paragraphs (a)(1) through 
(a)(5) of this section.
    (b) A person identified in paragraph (a) of this section who 
knowingly provides to any entity, listed in paragraphs (a)(1) through 
(a)(5) of this section, any components, materials, or other goods or 
services that relate to a licensee's, certificate holder's, quality 
assurance program approval holder's, or applicant's activities subject 
to this part may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee, certificate holder, quality 
assurance program approval holder, or any applicant to be in violation 
of any rule, regulation, or order; or any term, condition or limitation 
of any license, certificate, or approval issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, a certificate 
holder, quality assurance program approval holder, an applicant for a 
license, certificate or quality assurance program approval, or a 
licensee's, applicant's, certificate holder's, or quality assurance 
program approval holder's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to the NRC.
    (c) A person who violates paragraph (b)(1) or (b)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (d) For the purposes of paragraph (b)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee, certificate holder, quality assurance 
program approval holder, or applicant for a license, certificate, or 
quality assurance program approval to be in violation of any rule, 
regulation, or order; or any term, condition, or limitation of any 
license or certificate issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
certificate holder, quality assurance program approval holder, 
applicant, or the contractor or subcontractor of any of them.



Sec. 71.9  Employee protection.

    (a) Discrimination by a Commission licensee, certificate holder, an 
applicant for a Commission license or a CoC, or a contractor or 
subcontractor of any of these, against an employee for engaging in 
certain protected activities, is prohibited. Discrimination includes 
discharge and other actions that relate to compensation, terms, 
conditions, or privileges of employment. The protected activities are 
established in section 211 of the Energy Reorganization Act of 1974, as 
amended, and in general are related to the administration or enforcement 
of a requirement imposed under the Atomic Energy Act of 1954, as 
amended, or the Energy Reorganization Act of 1974, as amended.
    (1) The protected activities include, but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) of this section or possible violations of requirements imposed under 
either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) of this section or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) of this 
section; and
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee's assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting

[[Page 348]]

without direction from his or her employer (or the employer's agent), 
deliberately causes a violation of any requirement of the Energy 
Reorganization Act of 1974, as amended, or the Atomic Energy Act of 
1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, certificate holder, applicant for a Commission 
license or a CoC, or a contractor or subcontractor of any of these may 
be grounds for:
    (1) Denial, revocation, or suspension of the license or the CoC;
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant; or
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee, certificate holder, and applicant for a 
license or CoC must prominently post the current revision of NRC Form 3, 
``Notice to Employees,'' referenced in Sec. 19.11(c) of this chapter. 
This form must be posted at locations sufficient to permit employees 
protected by this section to observe a copy on the way to or from their 
place of work. The premises must be posted not later than 30 days after 
an application is docketed and remain posted while the application is 
pending before the Commission, during the term of the license or CoC, 
and for 30 days following license or CoC termination.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in Appendix D to Part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in a protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[69 FR 3786, Jan. 26, 2004, as amended at 72 FR 63975, Nov. 14, 2007; 73 
FR 30459, May 28, 2008; 79 FR 66605, Nov. 10, 2014]



Sec. 71.10  Public inspection of application.

    Applications for approval of a package design under this part, which 
are submitted to the Commission, may be made available for public 
inspection, in accordance with provisions of parts 2 and 9 of this 
chapter. This includes an application to amend or revise an existing 
package design, any associated documents and drawings submitted with the 
application, and any responses to NRC requests for additional 
information.

[[Page 349]]



Sec. 71.11  Protection of Safeguards Information.

    Each licensee, certificate holder, or applicant for a Certificate of 
Compliance for a transportation package for transport of irradiated 
reactor fuel, strategic special nuclear material, a critical mass of 
special nuclear material, or byproduct material in quantities determined 
by the Commission through order or regulation to be significant to the 
public health and safety or the common defense and security, shall 
protect Safeguards Information against unauthorized disclosure in 
accordance with the requirements in Sec. 73.21 and the requirements of 
Sec. 73.22 or Sec. 73.23 of this chapter, as applicable.

[73 FR 63572, Oct. 24, 2008]



                          Subpart B_Exemptions

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.



Sec. 71.12  Specific exemptions.

    On application of any interested person or on its own initiative, 
the Commission may grant any exemption from the requirements of the 
regulations in this part that it determines is authorized by law and 
will not endanger life or property nor the common defense and security.



Sec. 71.13  Exemption of physicians.

    Any physician licensed by a State to dispense drugs in the practice 
of medicine is exempt from Sec. 71.5 with respect to transport by the 
physician of licensed material for use in the practice of medicine. 
However, any physician operating under this exemption must be licensed 
under 10 CFR part 35 or the equivalent Agreement State regulations.



Sec. 71.14  Exemption for low-level materials.

    (a) A licensee is exempt from all the requirements of this part with 
respect to shipment or carriage of the following low-level materials:
    (1) Natural material and ores containing naturally occurring 
radionuclides that are either in their natural state, or have only been 
processed for purposes other than for the extraction of the 
radionuclides, and which are not intended to be processed for the use of 
these radionuclides, provided the activity concentration of the material 
does not exceed 10 times the applicable radionuclide activity 
concentration values specified in appendix A, Table A-2, or Table A-3 of 
this part.
    (2) Materials for which the activity concentration is not greater 
than the activity concentration values specified in appendix A, Table A-
2, or Table A-3 of this part, or for which the consignment activity is 
not greater than the limit for an exempt consignment found in appendix 
A, Table A-2, or Table A-3 of this part.
    (3) Non-radioactive solid objects with radioactive substances 
present on any surfaces in quantities not in excess of the levels cited 
in the definition of contamination in Sec. 71.4.
    (b) A licensee is exempt from all the requirements of this part, 
other than Sec. Sec. 71.5 and 71.88, with respect to shipment or 
carriage of the following packages, provided the packages do not contain 
any fissile material, or the material is exempt from classification as 
fissile material under Sec. 71.15:
    (1) A package that contains no more than a Type A quantity of 
radioactive material;
    (2) A package transported within the United States that contains no 
more than 0.74 TBq (20 Ci) of special form plutonium-244; or
    (3) The package contains only LSA or SCO radioactive material, 
provided--
    (i) That the LSA or SCO material has an external radiation dose of 
less than or equal to 10 mSv/h (1 rem/h), at a distance of 3 m from the 
unshielded material; or
    (ii) That the package contains only LSA-I or SCO-I material.

[69 FR 3786, Jan. 26, 2004, as amended at 80 FR 34012, June 12, 2015]



Sec. 71.15  Exemption from classification as fissile material.

    Fissile material meeting the requirements of at least one of the 
paragraphs (a) through (f) of this section are exempt from 
classification as fissile material and from the fissile material package 
standards of Sec. Sec. 71.55 and 71.59, but are subject to all other 
requirements of this part, except as noted.

[[Page 350]]

    (a) Individual package containing 2 grams or less fissile material.
    (b) Individual or bulk packaging containing 15 grams or less of 
fissile material provided the package has at least 200 grams of solid 
nonfissile material for every gram of fissile material. Lead, beryllium, 
graphite, and hydrogenous material enriched in deuterium may be present 
in the package but must not be included in determining the required mass 
for solid nonfissile material.
    (c)(1) Low concentrations of solid fissile material commingled with 
solid nonfissile material, provided that:
    (i) There is at least 2000 grams of solid nonfissile material for 
every gram of fissile material, and
    (ii) There is no more than 180 grams of fissile material distributed 
within 360 kg of contiguous nonfissile material.
    (2) Lead, beryllium, graphite, and hydrogenous material enriched in 
deuterium may be present in the package but must not be included in 
determining the required mass of solid nonfissile material.
    (d) Uranium enriched in uranium-235 to a maximum of 1 percent by 
weight, and with total plutonium and uranium-233 content of up to 1 
percent of the mass of uranium-235, provided that the mass of any 
beryllium, graphite, and hydrogenous material enriched in deuterium 
constitutes less than 5 percent of the uranium mass, and that the 
fissile material is distributed homogeneously and does not form a 
lattice arrangement within the package.
    (e) Liquid solutions of uranyl nitrate enriched in uranium-235 to a 
maximum of 2 percent by mass, with a total plutonium and uranium-233 
content not exceeding 0.002 percent of the mass of uranium, and with a 
minimum nitrogen to uranium atomic ratio (N/U) of 2. The material must 
be contained in at least a DOT Type A package.
    (f) Packages containing, individually, a total plutonium mass of not 
more than 1000 grams, of which not more than 20 percent by mass may 
consist of plutonium-239, plutonium-241, or any combination of these 
radionuclides.

[69 FR 3786, Jan. 26, 2004, as amended at 80 FR 34012, June 12, 2015]



Sec. 71.16  [Reserved]



                       Subpart C_General Licenses

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.



Sec. 71.17  General license: NRC-approved package.

    (a) A general license is issued to any licensee of the Commission to 
transport, or to deliver to a carrier for transport, licensed material 
in a package for which a license, certificate of compliance (CoC), or 
other approval has been issued by the NRC.
    (b) This general license applies only to a licensee who has a 
quality assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) Each licensee issued a general license under paragraph (a) of 
this section shall--
    (1) Maintain a copy of the Certificate of Compliance, or other 
approval of the package, and the drawings and other documents referenced 
in the approval relating to the use and maintenance of the packaging and 
to the actions to be taken before shipment;
    (2) Comply with the terms and conditions of the license, 
certificate, or other approval, as applicable, and the applicable 
requirements of subparts A, G, and H of this part; and
    (3) Submit in writing before the first use of the package to: ATTN: 
Document Control Desk, Director, Division of Spent Fuel Storage and 
Transportation, Office of Nuclear Material Safety and Safeguards, using 
an appropriate method listed in Sec. 71.1(a), the licensee's name and 
license number and the package identification number specified in the 
package approval.
    (d) This general license applies only when the package approval 
authorizes use of the package under this general license.
    (e) For a Type B or fissile material package, the design of which 
was approved by NRC before April 1, 1996, the general license is subject 
to the additional restrictions of Sec. 71.19.

[69 FR 3786, Jan. 26, 2004, as amended at 75 FR 73945, Nov. 30, 2010; 79 
FR 75741, Dec. 19, 2014; 80 FR 34012, June 12, 2015]

[[Page 351]]



Sec. 71.18  [Reserved]



Sec. 71.19  Previously approved package.

    (a) A Type B(U) package, a Type B(M) package, or a fissile material 
package, previously approved by the NRC but without the designation ``-
85'' in the identification number of the NRC CoC, may be used under the 
general license of Sec. 71.17 with the following additional conditions:
    (1) Fabrication of the package is satisfactorily completed by April 
1, 1999, as demonstrated by application of its model number in 
accordance with Sec. 71.85(c);
    (2) A package used for a shipment to a location outside the United 
States is subject to multilateral approval as defined in DOT regulations 
at 49 CFR 173.403; and
    (3) A serial number which uniquely identifies each packaging which 
conforms to the approved design is assigned to and legibly and durably 
marked on the outside of each packaging.
    (b) A Type B(U) package, a Type B(M) package, or a fissile material 
package previously approved by the NRC with the designation ``-85'' in 
the identification number of the NRC CoC, may be used under the general 
license of Sec. 71.17 with the following additional conditions:
    (1) Fabrication of the package must be satisfactorily completed by 
December 31, 2006, as demonstrated by application of its model number in 
accordance with Sec. 71.85(c); and
    (2) A package used for a shipment to a location outside the United 
States is subject to multilateral approval as defined in the DOT's 
regulations at 49 CFR 173.403.
    (c) NRC will approve modifications to the design and authorized 
contents of a Type B package, or a fissile material package, previously 
approved by NRC, provided--
    (1) The modifications of a Type B package are not significant with 
respect to the design, operating characteristics, or safe performance of 
the containment system, when the package is subjected to the tests 
specified in Sec. Sec. 71.71 and 71.73;
    (2) The modifications of a fissile material package are not 
significant, with respect to the prevention of criticality, when the 
package is subjected to the tests specified in Sec. Sec. 71.71 and 
71.73; and
    (3) The modifications to the package satisfy the requirements of 
this part.
    (d) NRC will revise the package identification number to designate 
previously approved package designs as B, BF, AF, B(U), B(M), B(U)F, 
B(M)F, B(U)-85, B(U)F-85, B(M)-85, B(M)F-85, or AF-85 as appropriate, 
and with the identification number suffix ``-96'' after receipt of an 
application demonstrating that the design meets the requirements of this 
part.

[69 FR 3786, Jan. 26, 2004; 69 FR 6139, Feb. 10, 2004, as amended at 80 
FR 34012, June 12, 2015]



Sec. 71.21  General license: Use of foreign approved package.

    (a) A general license is issued to any licensee of the Commission to 
transport, or to deliver to a carrier for transport, licensed material 
in a package, the design of which has been approved in a foreign 
national competent authority certificate, that has been revalidated by 
the DOT as meeting the applicable requirements of 49 CFR 171.23.
    (b) Except as otherwise provided in this section, the general 
license applies only to a licensee who has a quality assurance program 
approved by the Commission as satisfying the applicable provisions of 
subpart H of this part.
    (c) This general license applies only to shipments made to or from 
locations outside the United States.
    (d) Each licensee issued a general license under paragraph (a) of 
this section shall--
    (1) Maintain a copy of the applicable certificate, the revalidation, 
and the drawings and other documents referenced in the certificate, 
relating to the use and maintenance of the packaging and to the actions 
to be taken before shipment; and
    (2) Comply with the terms and conditions of the certificate and 
revalidation, and with the applicable requirements of subparts A, G, and 
H of this part.

[69 FR 3786, Jan. 26, 2004, as amended at 80 FR 34012, June 12, 2015]

[[Page 352]]



Sec. 71.22  General license: Fissile material.

    (a) A general license is issued to any licensee of the Commission to 
transport fissile material, or to deliver fissile material to a carrier 
for transport, if the material is shipped in accordance with this 
section. The fissile material need not be contained in a package which 
meets the standards of subparts E and F of this part; however, the 
material must be contained in a Type A package. The Type A package must 
also meet the DOT requirements of 49 CFR 173.417(a).
    (b) The general license applies only to a licensee who has a quality 
assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) The general license applies only when a package's contents:
    (1) Contain no more than a Type A quantity of radioactive material; 
and
    (2) Contain less than 500 total grams of beryllium, graphite, or 
hydrogenous material enriched in deuterium.
    (d) The general license applies only to packages containing fissile 
material that are labeled with a CSI which:
    (1) Has been determined in accordance with paragraph (e) of this 
section;
    (2) Has a value less than or equal to 10; and
    (3) For a shipment of multiple packages containing fissile material, 
the sum of the CSIs must be less than or equal to 50 (for shipment on a 
nonexclusive use conveyance) and less than or equal to 100 (for shipment 
on an exclusive use conveyance).
    (e)(1) The value for the CSI must be greater than or equal to the 
number calculated by the following equation:
[GRAPHIC] [TIFF OMITTED] TR26JA04.012

    (2) The calculated CSI must be rounded up to the first decimal 
place;
    (3) The values of X, Y, and Z used in the CSI equation must be taken 
from Tables 71-1 or 71-2, as appropriate;
    (4) If Table 71-2 is used to obtain the value of X, then the values 
for the terms in the equation for uranium-233 and plutonium must be 
assumed to be zero; and
    (5) Table 71-1 values for X, Y, and Z must be used to determine the 
CSI if:
    (i) Uranium-233 is present in the package;
    (ii) The mass of plutonium exceeds 1 percent of the mass of uranium-
235;
    (iii) The uranium is of unknown uranium-235 enrichment or greater 
than 24 weight percent enrichment; or
    (iv) Substances having a moderating effectiveness (i.e., an average 
hydrogen density greater than H 2O) (e.g., certain 
hydrocarbon oils or plastics) are present in any form, except as 
polyethylene used for packing or wrapping.

  Table 71-1--Mass Limits for General License Packages Containing Mixed
 Quantities of Fissile Material or Uranium-235 of Unknown Enrichment per
                             Sec. 71.22(e)
------------------------------------------------------------------------
                                   Fissile material    Fissile material
                                    mass mixed with     mass mixed with
                                      moderating          moderating
                                   substances having   substances having
        Fissile material              an average          an average
                                   hydrogen density    hydrogen density
                                  less than or equal    greater than H
                                    to H 2O (grams)      2O\a\ (grams)
------------------------------------------------------------------------
\235\ U (X).....................                 60                  38
\233\ U (Y).....................                 43                  27
\239\ Pu or \241\ Pu (Z)........                 37                  24
------------------------------------------------------------------------
\a\ When mixtures of moderating substances are present, the lower mass
  limits shall be used if more than 15 percent of the moderating
  substance has an average hydrogen density greater than H2O.


[[Page 353]]


Table 71-2--Mass Limits for General License Packages Containing Uranium-
               235 of Known Enrichment per Sec. 71.22(e)
------------------------------------------------------------------------
                                                               Fissile
                                                              material
    Uranium enrichment in weight percent of \235\ U not        mass of
                         exceeding                           \235\ U (X)
                                                               (grams)
------------------------------------------------------------------------
24........................................................           60
20........................................................           63
15........................................................           67
11........................................................           72
10........................................................           76
9.5.......................................................           78
9.........................................................           81
8.5.......................................................           82
8.........................................................           85
7.5.......................................................           88
7.........................................................           90
6.5.......................................................           93
6.........................................................           97
5.5.......................................................          102
5.........................................................          108
4.5.......................................................          114
4.........................................................          120
3.5.......................................................          132
3.........................................................          150
2.5.......................................................          180
2.........................................................          246
1.5.......................................................          408
1.35......................................................          480
1.........................................................        1,020
0.92......................................................        1,800
------------------------------------------------------------------------


[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]



Sec. 71.23  General license: Plutonium-beryllium special form material.

    (a) A general license is issued to any licensee of the Commission to 
transport fissile material in the form of plutonium-beryllium (Pu-Be) 
special form sealed sources, or to deliver Pu-Be sealed sources to a 
carrier for transport, if the material is shipped in accordance with 
this section. This material need not be contained in a package which 
meets the standards of subparts E and F of this part; however, the 
material must be contained in a Type A package. The Type A package must 
also meet the DOT requirements of 49 CFR 173.417(a).
    (b) The general license applies only to a licensee who has a quality 
assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) The general license applies only when a package's contents:
    (1) Contain no more than a Type A quantity of radioactive material; 
and
    (2) Contain less than 1000 g of plutonium, provided that: plutonium-
239, plutonium-241, or any combination of these radionuclides, 
constitutes less than 240 g of the total quantity of plutonium in the 
package.
    (d) The general license applies only to packages labeled with a CSI 
which:
    (1) Has been determined in accordance with paragraph (e) of this 
section;
    (2) Has a value less than or equal to 100; and
    (3) For a shipment of multiple packages containing Pu-Be sealed 
sources, the sum of the CSIs must be less than or equal to 50 (for 
shipment on a nonexclusive use conveyance) and less than or equal to 100 
(for shipment on an exclusive use conveyance).
    (e)(1) The value for the CSI must be greater than or equal to the 
number calculated by the following equation:
[GRAPHIC] [TIFF OMITTED] TR26JA04.013

    (2) The calculated CSI must be rounded up to the first decimal 
place.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]



Sec. Sec. 71.24-71.25  [Reserved]



               Subpart D_Application for Package Approval



Sec. 71.31  Contents of application.

    (a) An application for an approval under this part must include, for 
each proposed packaging design, the following information:

[[Page 354]]

    (1) A package description as required by Sec. 71.33;
    (2) A package evaluation as required by Sec. 71.35; and
    (3) A quality assurance program description, as required by Sec. 
71.37, or a reference to a previously approved quality assurance 
program.
    (b) Except as provided in Sec. 71.19, an application for 
modification of a package design, whether for modification of the 
packaging or authorized contents, must include sufficient information to 
demonstrate that the proposed design satisfies the package standards in 
effect at the time the application is filed.
    (c) The applicant shall identify any established codes and standards 
proposed for use in package design, fabrication, assembly, testing, 
maintenance, and use. In the absence of any codes and standards, the 
applicant shall describe and justify the basis and rationale used to 
formulate the package quality assurance program.

[60 FR 50264, Sept. 28, 1995, as amended at 80 FR 34012, June 12, 2015]



Sec. 71.33  Package description.

    The application must include a description of the proposed package 
in sufficient detail to identify the package accurately and provide a 
sufficient basis for evaluation of the package. The description must 
include--
    (a) With respect to the packaging--
    (1) Classification as Type B(U), Type B(M), or fissile material 
packaging;
    (2) Gross weight;
    (3) Model number;
    (4) Identification of the containment system;
    (5) Specific materials of construction, weights, dimensions, and 
fabrication methods of--
    (i) Receptacles;
    (ii) Materials specifically used as nonfissile neutron absorbers or 
moderators;
    (iii) Internal and external structures supporting or protecting 
receptacles;
    (iv) Valves, sampling ports, lifting devices, and tie-down devices; 
and
    (v) Structural and mechanical means for the transfer and dissipation 
of heat; and
    (6) Identification and volumes of any receptacles containing 
coolant.
    (b) With respect to the contents of the package--
    (1) Identification and maximum radioactivity of radioactive 
constituents;
    (2) Identification and maximum quantities of fissile constituents;
    (3) Chemical and physical form;
    (4) Extent of reflection, the amount and identity of nonfissile 
materials used as neutron absorbers or moderators, and the atomic ratio 
of moderator to fissile constituents;
    (5) Maximum normal operating pressure;
    (6) Maximum weight;
    (7) Maximum amount of decay heat; and
    (8) Identification and volumes of any coolants.



Sec. 71.35  Package evaluation.

    The application must include the following:
    (a) A demonstration that the package satisfies the standards 
specified in subparts E and F of this part;
    (b) For a fissile material package, the allowable number of packages 
that may be transported in the same vehicle in accordance with Sec. 
71.59; and
    (c) For a fissile material shipment, any proposed special controls 
and precautions for transport, loading, unloading, and handling and any 
proposed special controls in case of an accident or delay.



Sec. 71.37  Quality assurance.

    (a) The applicant shall describe the quality assurance program (see 
Subpart H of this part) for the design, fabrication, assembly, testing, 
maintenance, repair, modification, and use of the proposed package.
    (b) The applicant shall identify any specific provisions of the 
quality assurance program that are applicable to the particular package 
design under consideration, including a description of the leak testing 
procedures.



Sec. 71.38  Renewal of a certificate of compliance.

    (a) Except as provided in paragraph (b) of this section, each 
Certificate of Compliance expires at the end of the day, in the month 
and year stated in the approval.

[[Page 355]]

    (b) In any case in which a person, not less than 30 days before the 
expiration of an existing Certificate of Compliance issued pursuant to 
the part, has filed an application in proper form for renewal, the 
existing Certificate of Compliance for which the renewal application was 
filed shall not be deemed to have expired until final action on the 
application for renewal has been taken by the Commission.
    (c) In applying for renewal of an existing Certificate of 
Compliance, an applicant may be required to submit a consolidated 
application that is comprised of as few documents as possible. The 
consolidated application should incorporate all changes to its 
certificate, including changes that are incorporated by reference in the 
existing certificate.

[80 FR 34012, June 12, 2015]



Sec. 71.39  Requirement for additional information.

    The Commission may at any time require additional information in 
order to enable it to determine whether a license, certificate of 
compliance, or other approval should be granted, renewed, denied, 
modified, suspended, or revoked.



                  Subpart E_Package Approval Standards



Sec. 71.41  Demonstration of compliance.

    (a) The effects on a package of the tests specified in Sec. 71.71 
(``Normal conditions of transport''), and the tests specified in Sec. 
71.73 (``Hypothetical accident conditions''), and Sec. 71.61 (``Special 
requirements for Type B packages containing more than 10\5\ 
A2''), must be evaluated by subjecting a specimen or scale 
model to a specific test, or by another method of demonstration 
acceptable to the Commission, as appropriate for the particular feature 
being considered.
    (b) Taking into account the type of vehicle, the method of securing 
or attaching the package, and the controls to be exercised by the 
shipper, the Commission may permit the shipment to be evaluated together 
with the transporting vehicle.
    (c) Environmental and test conditions different from those specified 
in Sec. Sec. 71.71 and 71.73 may be approved by the Commission if the 
controls proposed to be exercised by the shipper are demonstrated to be 
adequate to provide equivalent safety of the shipment.
    (d) Packages for which compliance with the other provisions of these 
regulations is impracticable shall not be transported except under 
special package authorization. Provided the applicant demonstrates that 
compliance with the other provisions of the regulations is impracticable 
and that the requisite standards of safety established by these 
regulations have been demonstrated through means alternative to the 
other provisions, a special package authorization may be approved for 
one-time shipments. The applicant shall demonstrate that the overall 
level of safety in transport for these shipments is at least equivalent 
to that which would be provided if all the applicable requirements had 
been met.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3794, Jan. 26, 2004; 
69 FR 58039, Sept. 29, 2004]



Sec. 71.43  General standards for all packages.

    (a) The smallest overall dimension of a package may not be less than 
10 cm (4 in).
    (b) The outside of a package must incorporate a feature, such as a 
seal, that is not readily breakable and that, while intact, would be 
evidence that the package has not been opened by unauthorized persons.
    (c) Each package must include a containment system securely closed 
by a positive fastening device that cannot be opened unintentionally or 
by a pressure that may arise within the package.
    (d) A package must be made of materials and construction that assure 
that there will be no significant chemical, galvanic, or other reaction 
among the packaging components, among package contents, or between the 
packaging components and the package contents, including possible 
reaction resulting from inleakage of water, to the maximum credible 
extent. Account must be taken of the behavior of materials under 
irradiation.

[[Page 356]]

    (e) A package valve or other device, the failure of which would 
allow radioactive contents to escape, must be protected against 
unauthorized operation and, except for a pressure relief device, must be 
provided with an enclosure to retain any leakage.
    (f) A package must be designed, constructed, and prepared for 
shipment so that under the tests specified in Sec. 71.71 (``Normal 
conditions of transport'') there would be no loss or dispersal of 
radioactive contents, no significant increase in external surface 
radiation levels, and no substantial reduction in the effectiveness of 
the packaging.
    (g) A package must be designed, constructed, and prepared for 
transport so that in still air at 38 [deg]C (100 [deg]F) and in the 
shade, no accessible surface of a package would have a temperature 
exceeding 50 [deg]C (122 [deg]F) in a nonexclusive use shipment, or 85 
[deg]C (185 [deg]F) in an exclusive use shipment.
    (h) A package may not incorporate a feature intended to allow 
continuous venting during transport.



Sec. 71.45  Lifting and tie-down standards for all packages.

    (a) Any lifting attachment that is a structural part of a package 
must be designed with a minimum safety factor of three against yielding 
when used to lift the package in the intended manner, and it must be 
designed so that failure of any lifting device under excessive load 
would not impair the ability of the package to meet other requirements 
of this subpart. Any other structural part of the package that could be 
used to lift the package must be capable of being rendered inoperable 
for lifting the package during transport, or must be designed with 
strength equivalent to that required for lifting attachments.
    (b) Tie-down devices:
    (1) If there is a system of tie-down devices that is a structural 
part of the package, the system must be capable of withstanding, without 
generating stress in any material of the package in excess of its yield 
strength, a static force applied to the center of gravity of the package 
having a vertical component of 2 times the weight of the package with 
its contents, a horizontal component along the direction in which the 
vehicle travels of 10 times the weight of the package with its contents, 
and a horizontal component in the transverse direction of 5 times the 
weight of the package with its contents.
    (2) Any other structural part of the package that could be used to 
tie down the package must be capable of being rendered inoperable for 
tying down the package during transport, or must be designed with 
strength equivalent to that required for tie-down devices.
    (3) Each tie-down device that is a structural part of a package must 
be designed so that failure of the device under excessive load would not 
impair the ability of the package to meet other requirements of this 
part.



Sec. 71.47  External radiation standards for all packages.

    (a) Except as provided in paragraph (b) of this section, each 
package of radioactive materials offered for transportation must be 
designed and prepared for shipment so that under conditions normally 
incident to transportation the radiation level does not exceed 2 mSv/h 
(200 mrem/h) at any point on the external surface of the package, and 
the transport index does not exceed 10.
    (b) A package that exceeds the radiation level limits specified in 
paragraph (a) of this section must be transported by exclusive use 
shipment only, and the radiation levels for such shipment must not 
exceed the following during transportation:
    (1) 2 mSv/h (200 mrem/h) on the external surface of the package, 
unless the following conditions are met, in which case the limit is 10 
mSv/h (1000 mrem/h):
    (i) The shipment is made in a closed transport vehicle;
    (ii) The package is secured within the vehicle so that its position 
remains fixed during transportation; and
    (iii) There are no loading or unloading operations between the 
beginning and end of the transportation;
    (2) 2 mSv/h (200 mrem/h) at any point on the outer surface of the 
vehicle, including the top and underside of the vehicle; or in the case 
of a flat-bed style vehicle, at any point on the vertical planes 
projected from the outer edges

[[Page 357]]

of the vehicle, on the upper surface of the load or enclosure, if used, 
and on the lower external surface of the vehicle; and
    (3) 0.1 mSv/h (10 mrem/h) at any point 2 meters (80 in) from the 
outer lateral surfaces of the vehicle (excluding the top and underside 
of the vehicle); or in the case of a flat-bed style vehicle, at any 
point 2 meters (6.6 feet) from the vertical planes projected by the 
outer edges of the vehicle (excluding the top and underside of the 
vehicle); and
    (4) 0.02 mSv/h (2 mrem/h) in any normally occupied space, except 
that this provision does not apply to private carriers, if exposed 
personnel under their control wear radiation dosimetry devices in 
conformance with 10 CFR 20.1502.
    (c) For shipments made under the provisions of paragraph (b) of this 
section, the shipper shall provide specific written instructions to the 
carrier for maintenance of the exclusive use shipment controls. The 
instructions must be included with the shipping paper information.
    (d) The written instructions required for exclusive use shipments 
must be sufficient so that, when followed, they will cause the carrier 
to avoid actions that will unnecessarily delay delivery or unnecessarily 
result in increased radiation levels or radiation exposures to transport 
workers or members of the general public.



Sec. 71.51  Additional requirements for Type B packages.

    (a) A Type B package, in addition to satisfying the requirements of 
Sec. Sec. 71.41 through 71.47, must be designed, constructed, and 
prepared for shipment so that under the tests specified in:
    (1) Section 71.71 (``Normal conditions of transport''), there would 
be no loss or dispersal of radioactive contents--as demonstrated to a 
sensitivity of 10-6 A2 per hour, no significant 
increase in external surface radiation levels, and no substantial 
reduction in the effectiveness of the packaging; and
    (2) Section 71.73 (``Hypothetical accident conditions''), there 
would be no escape of krypton-85 exceeding 10 A2 in 1 week, 
no escape of other radioactive material exceeding a total amount 
A2 in 1 week, and no external radiation dose rate exceeding 
10 mSv/h (1 rem/h) at 1 m (40 in) from the external surface of the 
package.
    (b) Where mixtures of different radionuclides are present, the 
provisions of appendix A, paragraph IV of this part shall apply, except 
that for Krypton-85, an effective A2 value equal to 10 
A2 may be used.
    (c) Compliance with the permitted activity release limits of 
paragraph (a) of this section may not depend on filters or on a 
mechanical cooling system.
    (d) For packages which contain radioactive contents with activity 
greater than 10\5\ A2, the requirements of Sec. 71.61 must 
be met.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3794, Jan. 26, 2004; 
69 FR 58039, Sept. 29, 2004]



Sec. 71.53  [Reserved]



Sec. 71.55  General requirements for fissile material packages.

    (a) A package used for the shipment of fissile material must be 
designed and constructed in accordance with Sec. Sec. 71.41 through 
71.47. When required by the total amount of radioactive material, a 
package used for the shipment of fissile material must also be designed 
and constructed in accordance with Sec. 71.51.
    (b) Except as provided in paragraph (c) or (g) of this section, a 
package used for the shipment of fissile material must be so designed 
and constructed and its contents so limited that it would be subcritical 
if water were to leak into the containment system, or liquid contents 
were to leak out of the containment system so that, under the following 
conditions, maximum reactivity of the fissile material would be 
attained:
    (1) The most reactive credible configuration consistent with the 
chemical and physical form of the material;
    (2) Moderation by water to the most reactive credible extent; and
    (3) Close full reflection of the containment system by water on all 
sides, or such greater reflection of the containment system as may 
additionally be provided by the surrounding material of the packaging.

[[Page 358]]

    (c) The Commission may approve exceptions to the requirements of 
paragraph (b) of this section if the package incorporates special design 
features that ensure that no single packaging error would permit 
leakage, and if appropriate measures are taken before each shipment to 
ensure that the containment system does not leak.
    (d) A package used for the shipment of fissile material must be so 
designed and constructed and its contents so limited that under the 
tests specified in Sec. 71.71 (``Normal conditions of transport'')--
    (1) The contents would be subcritical;
    (2) The geometric form of the package contents would not be 
substantially altered;
    (3) There would be no leakage of water into the containment system 
unless, in the evaluation of undamaged packages under Sec. 71.59(a)(1), 
it has been assumed that moderation is present to such an extent as to 
cause maximum reactivity consistent with the chemical and physical form 
of the material; and
    (4) There will be no substantial reduction in the effectiveness of 
the packaging, including:
    (i) No more than 5 percent reduction in the total effective volume 
of the packaging on which nuclear safety is assessed;
    (ii) No more than 5 percent reduction in the effective spacing 
between the fissile contents and the outer surface of the packaging; and
    (iii) No occurrence of an aperture in the outer surface of the 
packaging large enough to permit the entry of a 10 cm (4 in) cube.
    (e) A package used for the shipment of fissile material must be so 
designed and constructed and its contents so limited that under the 
tests specified in Sec. 71.73 (``Hypothetical accident conditions''), 
the package would be subcritical. For this determination, it must be 
assumed that:
    (1) The fissile material is in the most reactive credible 
configuration consistent with the damaged condition of the package and 
the chemical and physical form of the contents;
    (2) Water moderation occurs to the most reactive credible extent 
consistent with the damaged condition of the package and the chemical 
and physical form of the contents; and
    (3) There is full reflection by water on all sides, as close as is 
consistent with the damaged condition of the package.
    (f) For fissile material package designs to be transported by air:
    (1) The package must be designed and constructed, and its contents 
limited so that it would be subcritical, assuming reflection by 20 cm 
(7.9 in) of water but no water inleakage, when subjected to sequential 
application of:
    (i) The free drop test in Sec. 71.73(c)(1);
    (ii) The crush test in Sec. 71.73(c)(2);
    (iii) A puncture test, for packages of 250 kg or more, consisting of 
a free drop of the specimen through a distance of 3 m (120 in) in a 
position for which maximum damage is expected at the conclusion of the 
test sequence, onto the upper end of a solid, vertical, cylindrical, 
mild steel probe mounted on an essentially unyielding, horizontal 
surface. The probe must be 20 cm (7.9 in) in diameter, with the striking 
end forming the frustum of a right circular cone with the dimensions of 
30 cm height, 2.5 cm top diameter, and a top edge rounded to a radius of 
not more than 6 mm (0.25 in). For packages less than 250 kg, the 
puncture test must be the same, except that a 250 kg probe must be 
dropped onto the specimen which must be placed on the surface; and
    (iv) The thermal test in Sec. 71.73(c)(4), except that the duration 
of the test must be 60 minutes.
    (2) The package must be designed and constructed, and its contents 
limited, so that it would be subcritical, assuming reflection by 20 cm 
(7.9 in) of water but no water inleakage, when subjected to an impact on 
an unyielding surface at a velocity of 90 m/s normal to the surface, at 
such orientation so as to result in maximum damage. A separate, 
undamaged specimen can be used for this evaluation.
    (3) Allowance may not be made for the special design features in 
paragraph (c) of this section, unless water leakage into or out of void 
spaces is prevented following application of the tests in paragraphs 
(f)(1) and (f)(2) of

[[Page 359]]

this section, and subsequent application of the immersion test in Sec. 
71.73(c)(5).
    (g) Packages containing uranium hexafluoride only are excepted from 
the requirements of paragraph (b) of this section provided that:
    (1) Following the tests specified in Sec. 71.73 (``Hypothetical 
accident conditions''), there is no physical contact between the valve 
body and any other component of the packaging, other than at its 
original point of attachment, and the valve remains leak tight;
    (2) There is an adequate quality control in the manufacture, 
maintenance, and repair of packagings;
    (3) Each package is tested to demonstrate closure before each 
shipment; and
    (4) The uranium is enriched to not more than 5 weight percent 
uranium-235.

[60 FR 50264, Sept. 28, 1995; 61 FR 28724, June 6, 1996, as amended at 
69 FR 3794, Jan. 26, 2004]



Sec. 71.57  [Reserved]



Sec. 71.59  Standards for arrays of fissile material packages.

    (a) A fissile material package must be controlled by either the 
shipper or the carrier during transport to assure that an array of such 
packages remains subcritical. To enable this control, the designer of a 
fissile material package shall derive a number ``N'' based on all the 
following conditions being satisfied, assuming packages are stacked 
together in any arrangement and with close full reflection on all sides 
of the stack by water:
    (1) Five times ``N'' undamaged packages with nothing between the 
packages would be subcritical;
    (2) Two times ``N'' damaged packages, if each package were subjected 
to the tests specified in Sec. 71.73 (``Hypothetical accident 
conditions'') would be subcritical with optimum interspersed hydrogenous 
moderation; and
    (3) The value of ``N'' cannot be less than 0.5.
    (b) The CSI must be determined by dividing the number 50 by the 
value of ``N'' derived using the procedures specified in paragraph (a) 
of this section. The value of the CSI may be zero provided that an 
unlimited number of packages are subcritical, such that the value of 
``N'' is effectively equal to infinity under the procedures specified in 
paragraph (a) of this section. Any CSI greater than zero must be rounded 
up to the first decimal place.
    (c) For a fissile material package which is assigned a CSI value--
    (1) Less than or equal to 50, that package may be shipped by a 
carrier in a nonexclusive use conveyance, provided the sum of the CSIs 
is limited to less than or equal to 50.
    (2) Less than or equal to 50, that package may be shipped by a 
carrier in an exclusive use conveyance, provided the sum of the CSIs is 
limited to less than or equal to 100.
    (3) Greater than 50, that package must be shipped by a carrier in an 
exclusive use conveyance, provided the sum of the CSIs is limited to 
less than or equal to 100.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]



Sec. 71.61  Special requirements for Type B packages containing more 
than 10 [bds5] A[bdi2].

    A Type B package containing more than 105A2 
must be designed so that its undamaged containment system can withstand 
an external water pressure of 2 MPa (290 psi) for a period of not less 
than 1 hour without collapse, buckling, or inleakage of water.

[69 FR 3795, Jan. 26, 2004]



Sec. 71.63  Special requirement for plutonium shipments.

    Shipments containing plutonium must be made with the contents in 
solid form, if the contents contain greater than 0.74 TBq (20 Ci) of 
plutonium.

[69 FR 3795, Jan. 26, 2004]



Sec. 71.64  Special requirements for plutonium air shipments.

    (a) A package for the shipment of plutonium by air subject to Sec. 
71.88(a)(4), in addition to satisfying the requirements of Sec. Sec. 
71.41 through 71.63, as applicable, must be designed, constructed, and 
prepared for shipment so that under the tests specified in--

[[Page 360]]

    (1) Section 71.74 (``Accident conditions for air transport of 
plutonium'')--
    (i) The containment vessel would not be ruptured in its post-tested 
condition, and the package must provide a sufficient degree of 
containment to restrict accumulated loss of plutonium contents to not 
more than an A2 quantity in a period of 1 week;
    (ii) The external radiation level would not exceed 10 mSv/h (1 rem/
h) at a distance of 1 m (40 in) from the surface of the package in its 
post-tested condition in air; and
    (iii) A single package and an array of packages are demonstrated to 
be subcritical in accordance with this part, except that the damaged 
condition of the package must be considered to be that which results 
from the plutonium accident tests in Sec. 71.74, rather than the 
hypothetical accident tests in Sec. 71.73; and
    (2) Section 71.74(c), there would be no detectable leakage of water 
into the containment vessel of the package.
    (b) With respect to the package requirements of paragraph (a), there 
must be a demonstration or analytical assessment showing that--
    (1) The results of the physical testing for package qualification 
would not be adversely affected to a significant extent by--
    (i) The presence, during the tests, of the actual contents that will 
be transported in the package; and
    (ii) Ambient water temperatures ranging from 0.6 [deg]C ( + 33 
[deg]F) to 38 [deg]C ( + 100 [deg]F) for those qualification tests 
involving water, and ambient atmospheric temperatures ranging from -40 
[deg]C (-40 [deg]F) to + 54 [deg]C ( + 130[deg]F) for the other 
qualification tests.
    (2) The ability of the package to meet the acceptance standards 
prescribed for the accident condition sequential tests would not be 
adversely affected if one or more tests in the sequence were deleted.



Sec. 71.65  Additional requirements.

    The Commission may, by rule, regulation, or order, impose 
requirements on any licensee, in addition to those established in this 
part, as it deems necessary or appropriate to protect public health or 
to minimize danger to life or property.



         Subpart F_Package, Special Form, and LSA-III Tests \2\
---------------------------------------------------------------------------

    \2\ The package standards related to the tests in this subpart are 
contained in subpart E of this part.
---------------------------------------------------------------------------



Sec. 71.70  Incorporations by reference.

    (a) The materials listed in this section are incorporated by 
reference in the corresponding sections noted and made a part of the 
regulations in part 71. These incorporations by reference were approved 
by the Director of the Federal Register under 5 U.S.C. 552(a) and 1 CFR 
part 51. These materials are incorporated as they exist on the date of 
the approval. A notice of any changes made to the material incorporated 
by reference will be published in the Federal Register, and the material 
must be available to the public. The materials can be examined, by 
appointment, at the NRC's Technical Library, which is located at Two 
White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852; 
telephone: 301-415-7000; email: [email protected]. The materials 
are also available from the sources listed below. All approved material 
is available for inspection at the National Archives and Records 
Administration (NARA). For information on the availability of this 
material at NARA, call 1-202-741-6030 or go to http://www.archives.gov/
federal-register/cfr/ibr-locations.html.
    (b) International Organization for Standardization, ISO Central 
Secretariat, Chemin de Blandonnet 8 CP 401, 1214 Vernier, Geneva, 
Switzerland; email: [email protected]; phone: + 41 22 749 01 11; Web site: 
http://www.iso.org.
    (1) ISO 9978:1992(E), ``Radiation protection--Sealed radioactive 
sources--Leakage test methods,'' First Edition (February 15, 1992), 
incorporation by reference approved for Sec. 71.75(a), is available for 
purchase from the American National Standards Institute, 25 West 43rd 
Street, 4th Floor, New York, NY 10036, 212-642-4900, http://
www.ansi.org, or [email protected].
    (2) ISO 2919:1999(E), ``Radiation protection--Sealed radioactive 
sources--General requirements and classification,'' Second Edition 
(February 15,

[[Page 361]]

1999), incorporation by reference approved for Sec. 71.75(d), is 
available on http://www.amazon.com.

[80 FR 34013, June 12, 2015, as amended at 80 FR 48684, Aug. 14, 2015]



Sec. 71.71  Normal conditions of transport.

    (a) Evaluation. Evaluation of each package design under normal 
conditions of transport must include a determination of the effect on 
that design of the conditions and tests specified in this section. 
Separate specimens may be used for the free drop test, the compression 
test, and the penetration test, if each specimen is subjected to the 
water spray test before being subjected to any of the other tests.
    (b) Initial conditions. With respect to the initial conditions for 
the tests in this section, the demonstration of compliance with the 
requirements of this part must be based on the ambient temperature 
preceding and following the tests remaining constant at that value 
between -29 [deg]C (-20 [deg]F) and + 38 [deg]C ( + 100 [deg]F) which is 
most unfavorable for the feature under consideration. The initial 
internal pressure within the containment system must be considered to be 
the maximum normal operating pressure, unless a lower internal pressure 
consistent with the ambient temperature considered to precede and follow 
the tests is more unfavorable.
    (c) Conditions and tests--(1) Heat. An ambient temperature of 38 
[deg]C (100 [deg]F) in still air, and insolation according to the 
following table:

                             Insolation Data
------------------------------------------------------------------------
                                             Total insolation for a 12-
       Form and location of surface           hour period (g cal/cm\2\)
------------------------------------------------------------------------
Flat surfaces transported horizontally:
    Base..................................  None
    Other surfaces........................  800
Flat surfaces not transported horizontally  200
Curved surfaces...........................  400
------------------------------------------------------------------------

    (2) Cold. An ambient temperature of -40 [deg]C (-40 [deg]F) in still 
air and shade.
    (3) Reduced external pressure. An external pressure of 25 kPa (3.5 
lbf/in\2\) absolute.
    (4) Increased external pressure. An external pressure of 140 kPa (20 
lbf/in\2\) absolute.
    (5) Vibration. Vibration normally incident to transport.
    (6) Water spray. A water spray that simulates exposure to rainfall 
of approximately 5 cm/h (2 in/h) for at least 1 hour.
    (7) Free drop. Between 1.5 and 2.5 hours after the conclusion of the 
water spray test, a free drop through the distance specified below onto 
a flat, essentially unyielding, horizontal surface, striking the surface 
in a position for which maximum damage is expected.

              Criteria for Free Drop Test (Weight/Distance)
------------------------------------------------------------------------
                    Package weight                          Free drop
-------------------------------------------------------     distance
                                                       -----------------
            Kilograms                    (Pounds)        Meters   (Feet)
------------------------------------------------------------------------
Less than 5,000..................  (Less than 11,000).      1.2      (4)
5,000 to 10,000..................  (11,000 to 22,000).      0.9      (3)
10,000 to 15,000.................  (22,000 to 33,100).      0.6      (2)
More than 15,000.................  (More than 33,100).      0.3      (1)
------------------------------------------------------------------------

    (8) Corner drop. A free drop onto each corner of the package in 
succession, or in the case of a cylindrical package onto each quarter of 
each rim, from a height of 0.3 m (1 ft) onto a flat, essentially 
unyielding, horizontal surface. This test applies only to fiberboard, 
wood, or fissile material rectangular packages not exceeding 50 kg (110 
lbs) and fiberboard, wood, or fissile material cylindrical packages not 
exceeding 100 kg (220 lbs).
    (9) Compression. For packages weighing up to 5000 kg (11,000 lbs), 
the package must be subjected, for a period of 24 hours, to a 
compressive load applied uniformly to the top and bottom of the package 
in the position in which the package would normally be transported. The 
compressive load must be the greater of the following:
    (i) The equivalent of 5 times the weight of the package; or
    (ii) The equivalent of 13 kPa (2 lbf/in\2\) multiplied by the 
vertically projected area of the package.
    (10) Penetration. Impact of the hemispherical end of a vertical 
steel cylinder of 3.2 cm (1.25 in) diameter and 6 kg (13 lbs) mass, 
dropped from a height of 1 m (40 in) onto the exposed surface of the 
package that is expected to be most vulnerable to puncture. The long

[[Page 362]]

axis of the cylinder must be perpendicular to the package surface.

[60 FR 50264, Sept. 28, 1995, as amended at 81 FR 86910, Dec. 2, 2016]



Sec. 71.73  Hypothetical accident conditions.

    (a) Test procedures. Evaluation for hypothetical accident conditions 
is to be based on sequential application of the tests specified in this 
section, in the order indicated, to determine their cumulative effect on 
a package or array of packages. An undamaged specimen may be used for 
the water immersion tests specified in paragraph (c)(6) of this section.
    (b) Test conditions. With respect to the initial conditions for the 
tests, except for the water immersion tests, to demonstrate compliance 
with the requirements of this part during testing, the ambient air 
temperature before and after the tests must remain constant at that 
value between -29 [deg]C (-20 [deg]F) and + 38 [deg]C ( + 100 [deg]F) 
which is most unfavorable for the feature under consideration. The 
initial internal pressure within the containment system must be the 
maximum normal operating pressure, unless a lower internal pressure, 
consistent with the ambient temperature assumed to precede and follow 
the tests, is more unfavorable.
    (c) Tests. Tests for hypothetical accident conditions must be 
conducted as follows:
    (1) Free drop. A free drop of the specimen through a distance of 9 m 
(30 ft) onto a flat, essentially unyielding, horizontal surface, 
striking the surface in a position for which maximum damage is expected.
    (2) Crush. Subjection of the specimen to a dynamic crush test by 
positioning the specimen on a flat, essentially unyielding horizontal 
surface so as to suffer maximum damage by the drop of a 500-kg (1100-lb) 
mass from 9 m (30 ft) onto the specimen. The mass must consist of a 
solid mild steel plate 1 m (40 in) by 1 m (40 in) and must fall in a 
horizontal attitude. The crush test is required only when the specimen 
has a mass not greater than 500 kg (1100 lb), an overall density not 
greater than 1000 kg/m \3\ (62.4 lb/ft \3\) based on external dimension, 
and radioactive contents greater than 1000 A2 not as special 
form radioactive material. For packages containing fissile material, the 
radioactive contents greater than 1000 A2 criterion does not 
apply.
    (3) Puncture. A free drop of the specimen through a distance of 1 m 
(40 in) in a position for which maximum damage is expected, onto the 
upper end of a solid, vertical, cylindrical, mild steel bar mounted on 
an essentially unyielding, horizontal surface. The bar must be 15 cm (6 
in) in diameter, with the top horizontal and its edge rounded to a 
radius of not more than 6 mm (0.25 in), and of a length as to cause 
maximum damage to the package, but not less than 20 cm (8 in) long. The 
long axis of the bar must be vertical.
    (4) Thermal. Exposure of the specimen fully engulfed, except for a 
simple support system, in a hydrocarbon fuel/air fire of sufficient 
extent, and in sufficiently quiescent ambient conditions, to provide an 
average emissivity coefficient of at least 0.9, with an average flame 
temperature of at least 800 [deg]C (1475 [deg]F) for a period of 30 
minutes, or any other thermal test that provides the equivalent total 
heat input to the package and which provides a time averaged 
environmental temperature of 800 [deg]C. The fuel source must extend 
horizontally at least 1 m (40 in), but may not extend more than 3 m (10 
ft), beyond any external surface of the specimen, and the specimen must 
be positioned 1 m (40 in) above the surface of the fuel source. For 
purposes of calculation, the surface absorptivity coefficient must be 
either that value which the package may be expected to possess if 
exposed to the fire specified or 0.8, whichever is greater; and the 
convective coefficient must be that value which may be demonstrated to 
exist if the package were exposed to the fire specified. Artificial 
cooling may not be applied after cessation of external heat input, and 
any combustion of materials of construction, must be allowed to proceed 
until it terminates naturally.
    (5) Immersion--fissile material. For fissile material subject to 
Sec. 71.55, in those cases where water inleakage has not been assumed 
for criticality analysis, immersion under a head of water of at least 
0.9 m (3 ft) in the attitude for which maximum leakage is expected.

[[Page 363]]

    (6) Immersion--all packages. A separate, undamaged specimen must be 
subjected to water pressure equivalent to immersion under a head of 
water of at least 15 m (50 ft). For test purposes, an external pressure 
of water of 150 kPa (21.7 lbf/in\2\) gauge is considered to meet these 
conditions.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]



Sec. 71.74  Accident conditions for air transport of plutonium.

    (a) Test conditions--Sequence of tests. A package must be physically 
tested to the following conditions in the order indicated to determine 
their cumulative effect.
    (1) Impact at a velocity of not less than 129 m/sec (422 ft/sec) at 
a right angle onto a flat, essentially unyielding, horizontal surface, 
in the orientation (e.g., side, end, corner) expected to result in 
maximum damage at the conclusion of the test sequence.
    (2) A static compressive load of 31,800 kg (70,000 lbs) applied in 
the orientation expected to result in maximum damage at the conclusion 
of the test sequence. The force on the package must be developed between 
a flat steel surface and a 5 cm (2 in) wide, straight, solid, steel bar. 
The length of the bar must be at least as long as the diameter of the 
package, and the longitudinal axis of the bar must be parallel to the 
plane of the flat surface. The load must be applied to the bar in a 
manner that prevents any members or devices used to support the bar from 
contacting the package.
    (3) Packages weighing less than 227 kg (500 lbs) must be placed on a 
flat, essentially unyielding, horizontal surface, and subjected to a 
weight of 227 kg (500 lbs) falling from a height of 3 m (10 ft) and 
striking in the position expected to result in maximum damage at the 
conclusion of the test sequence. The end of the weight contacting the 
package must be a solid probe made of mild steel. The probe must be the 
shape of the frustum of a right circular cone, 30 cm (12 in) long, 20 cm 
(8 in) in diameter at the base, and 2.5 cm (1 in) in diameter at the 
end. The longitudinal axis of the probe must be perpendicular to the 
horizontal surface. For packages weighing 227 kg (500 lbs) or more, the 
base of the probe must be placed on a flat, essentially unyielding 
horizontal surface, and the package dropped from a height of 3 m (10 ft) 
onto the probe, striking in the position expected to result in maximum 
damage at the conclusion of the test sequence.
    (4) The package must be firmly restrained and supported such that 
its longitudinal axis is inclined approximately 45[deg] to the 
horizontal. The area of the package that made first contact with the 
impact surface in paragraph (a)(1) of this section must be in the 
lowermost position. The package must be struck at approximately the 
center of its vertical projection by the end of a structural steel angle 
section falling from a height of at least 46 m (150 ft). The angle 
section must be at least 1.8 m (6 ft) in length with equal legs at least 
13 cm (5 in) long and 1.3 cm (0.5 in) thick. The angle section must be 
guided in such a way as to fall end-on, without tumbling. The package 
must be rotated approximately 90[deg] about its longitudinal axis and 
struck by the steel angle section falling as before.
    (5) The package must be exposed to luminous flames from a pool fire 
of JP-4 or JP-5 aviation fuel for a period of at least 60 minutes. The 
luminous flames must extend an average of at least 0.9 m (3 ft) and no 
more than 3 m (10 ft) beyond the package in all horizontal directions. 
The position and orientation of the package in relation to the fuel must 
be that which is expected to result in maximum damage at the conclusion 
of the test sequence. An alternate method of thermal testing may be 
substituted for this fire test, provided that the alternate test is not 
of shorter duration and would not result in a lower heating rate to the 
package. At the conclusion of the thermal test, the package must be 
allowed to cool naturally or must be cooled by water sprinkling, 
whichever is expected to result in maximum damage at the conclusion of 
the test sequence.
    (6) Immersion under at least 0.9 m (3 ft) of water.
    (b) Individual free-fall impact test. (1) An undamaged package must 
be physically subjected to an impact at a velocity not less than the 
calculated terminal free-fall velocity, at mean sea

[[Page 364]]

level, at a right angle onto a flat, essentially unyielding, horizontal 
surface, in the orientation (e.g., side, end, corner) expected to result 
in maximum damage.
    (2) This test is not required if the calculated terminal free-fall 
velocity of the package is less than 129 m/sec (422 ft/sec), or if a 
velocity not less than either 129 m/sec (422 ft/sec) or the calculated 
terminal free-fall velocity of the package is used in the sequential 
test of paragraph (a)(1) of this section.
    (c) Individual deep submersion test. An undamaged package must be 
physically submerged and physically subjected to an external water 
pressure of at least 4 MPa (600 lbs/in \2\).



Sec. 71.75  Qualification of special form radioactive material.

    (a) Special form radioactive materials must meet the test 
requirements of paragraph (b) of this section. Each solid radioactive 
material or capsule specimen to be tested must be manufactured or 
fabricated so that it is representative of the actual solid material or 
capsule that will be transported, with the proposed radioactive content 
duplicated as closely as practicable. Any differences between the 
material to be transported and the test material, such as the use of 
non-radioactive contents, must be taken into account in determining 
whether the test requirements have been met. In addition:
    (1) A different specimen may be used for each of the tests;
    (2) The specimen may not break or shatter when subjected to the 
impact, percussion, or bending tests;
    (3) The specimen may not melt or disperse when subjected to the heat 
test;
    (4) After each test, leaktightness or indispersibility of the 
specimen must be determined by a method no less sensitive than the 
leaching assessment procedure prescribed in paragraph (c) of this 
section. For a capsule resistant to corrosion by water, and which has an 
internal void volume greater than 0.1 milliliter, an alternative to the 
leaching assessment is a demonstration of leaktightness of x 
10-4 torr-liter/s (1.3 x x 10-4 atm-cm\3\/s) based 
on air at 25 [deg]C (77 [deg]F) and one atmosphere differential pressure 
for solid radioactive content, or x 10-6 torr-liter/s (1.3 x 
x 10-6 atm-cm\3\/s) for liquid or gaseous radioactive 
content; and
    (5) A specimen that comprises or simulates radioactive material 
contained in a sealed capsule need not be subjected to the leaktightness 
procedure specified in this section, provided it is alternatively 
subjected to any of the tests prescribed in ISO 9978:1992(E), 
``Radiation protection--Sealed radioactive sources--Leakage test 
methods'' (incorporated by reference, see Sec. 71.70).
    (b) Test methods--(1) Impact Test. The specimen must fall onto the 
target from a height of 9 m (30 ft) or greater in the orientation 
expected to result in maximum damage. The target must be a flat, 
horizontal surface of such mass and rigidity that any increase in its 
resistance to displacement or deformation, on impact by the specimen, 
would not significantly increase the damage to the specimen.
    (2) Percussion Test. (i) The specimen must be placed on a sheet of 
lead that is supported by a smooth solid surface, and struck by the flat 
face of a steel billet so as to produce an impact equivalent to that 
resulting from a free drop of 1.4 kg (3 lbs) through 1 m (40 in);
    (ii) The flat face of the billet must be 25 millimeters (mm) (1 
inch) in diameter with the edge rounded off to a radius of 3 mm 0.3 mm (0.12 in 0.012 in);
    (iii) The lead must be hardness number 3.5 to 4.5 on the Vickers 
scale and not more than 25 mm (1 inch) thick, and must cover an area 
greater than that covered by the specimen;
    (iv) A fresh surface of lead must be used for each impact; and
    (v) The billet must strike the specimen so as to cause maximum 
damage.
    (3) Bending test. (i) This test applies only to long, slender 
sources with a length of 10 cm (4 inches) or greater and a length to 
width ratio of 10 or greater;
    (ii) The specimen must be rigidly clamped in a horizontal position 
so that one half of its length protrudes from the face of the clamp;
    (iii) The orientation of the specimen must be such that the specimen 
will suffer maximum damage when its free end is struck by the flat face 
of a steel billet;

[[Page 365]]

    (iv) The billet must strike the specimen so as to produce an impact 
equivalent to that resulting from a free vertical drop of 1.4 kg (3 lbs) 
through 1 m (40 in); and
    (v) The flat face of the billet must be 25 mm (1 inch) in diameter 
with the edges rounded off to a radius of 3 mm 0.3 
mm (.12 in 0.012 in).
    (4) Heat test. The specimen must be heated in air to a temperature 
of not less than 800 [deg]C (1475 [deg]F), held at that temperature for 
a period of 10 minutes, and then allowed to cool.
    (c) Leaching assessment methods. (1) For indispersible solid 
material--
    (i) The specimen must be immersed for 7 days in water at ambient 
temperature. The water must have a pH of 6-8 and a maximum conductivity 
of 10 micromho per centimeter at 20[deg] (68 [deg]F);
    (ii) The water with specimen must then be heated to a temperature of 
50 [deg]C 5 [deg]C (122 [deg]F 9 [deg]F) and maintained at this temperature for 4 
hours.
    (iii) The activity of the water must then be determined;
    (iv) The specimen must then be stored for at least 7 days in still 
air of relative humidity not less than 90 percent at 30 [deg]C (86 
[deg]F);
    (v) The specimen must then be immersed in water under the same 
conditions as in paragraph (c)(1)(i) of this section, and the water with 
specimen must be heated to 50 [deg]C 5 [deg]C (122 
[deg]F 9 [deg]F) and maintained at that 
temperature for 4 hours;
    (vi) The activity of the water must then be determined. The sum of 
the activities determined here and in paragraph (c)(1)(iii) of this 
section must not exceed 2 kilobecquerels (kBq) (0.05 microcurie 
([micro]Ci)).
    (2) For encapsulated material--
    (i) The specimen must be immersed in water at ambient temperature. 
The water must have a pH of 6-8 and a maximum conductivity of 10 
micromho per centimeter;
    (ii) The water and specimen must be heated to a temperature of 50 
[deg]C 5 [deg]C (122 [deg]F 9 [deg]F) and maintained at this temperature for 4 
hours;
    (iii) The activity of the water must then be determined;
    (iv) The specimen must then be stored for at least 7 days in still 
air at a temperature of 30 [deg]C (86 [deg]F) or greater;
    (v) The process in paragraph (c)(2)(i), (ii), and (iii) of this 
section must be repeated; and
    (vi) The activity of the water must then be determined. The sum of 
the activities determined here and in paragraph (c)(2)(iii) of this 
section must not exceed 2 kilobecquerels (kBq) (0.05 microcurie 
([micro]Ci)).
    (d) A specimen that comprises or simulates radioactive material 
contained in a sealed capsule need not be subjected to--
    (1) The impact test and the percussion test of this section, 
provided that the specimen is:
    (i) Less than 200 grams and alternatively subjected to the Class 4 
impact test prescribed in ISO 2919:1999(E), ``Radiation protection--
Sealed radioactive sources--General requirements and classification'' 
(incorporated by reference, see Sec. 71.70); or
    (ii) Less than 500 grams and alternatively subjected to the Class 5 
impact test prescribed in ISO 2919:1999(E), ``Radioactive protection--
Sealed radioactive sources--General requirements and classification'' 
(incorporated by reference, see Sec. 71.70); and
    (2) The heat test of this section, provided the specimen is 
alternatively subjected to the Class 6 temperature test specified in ISO 
2919:1999(E), ``Radioactive protection--Sealed radioactive sources--
General requirements and classification'' (incorporated by reference, 
see Sec. 71.70).

[60 FR 50264, Sept. 28, 1995, as amended at 80 FR 34013, June 12, 2015]



Sec. 71.77  Qualification of LSA-III Material.

    (a) LSA-III material must meet the test requirements of paragraph 
(b) of this section. Any differences between the specimen to be tested 
and the material to be transported must be taken into account in 
determining whether the test requirements have been met.
    (b) Leaching test. (1) The specimen, representing no less than the 
entire contents of the package, must be immersed for 7 days in water at 
ambient temperature;
    (2) The volume of water to be used in the test must be sufficient to 
ensure

[[Page 366]]

that at the end of the test period the free volume of the unabsorbed and 
unreacted water remaining will be at least 10% of the volume of the 
specimen itself;
    (3) The water must have an initial pH of 6-8 and a maximum 
conductivity 10 micromho/cm at 20 [deg]C (68 [deg]F); and
    (4) The total activity of the free volume of water must be measured 
following the 7 day immersion test and must not exceed 0.1 
A2.



               Subpart G_Operating Controls and Procedures



Sec. 71.81  Applicability of operating controls and procedures.

    A licensee subject to this part, who, under a general or specific 
license, transports licensed material or delivers licensed material to a 
carrier for transport, shall comply with the requirements of this 
subpart G, with the quality assurance requirements of subpart H of this 
part, and with the general provisions of subpart A of this part.



Sec. 71.83  Assumptions as to unknown properties.

    When the isotopic abundance, mass, concentration, degree of 
irradiation, degree of moderation, or other pertinent property of 
fissile material in any package is not known, the licensee shall package 
the fissile material as if the unknown properties have credible values 
that will cause the maximum neutron multiplication.



Sec. 71.85  Preliminary determinations.

    Before the first use of any packaging for the shipment of licensed 
material--
    (a) The certificate holder shall ascertain that there are no cracks, 
pinholes, uncontrolled voids, or other defects that could significantly 
reduce the effectiveness of the packaging;
    (b) Where the maximum normal operating pressure will exceed 35 kPa 
(5 lbf/in\2\) gauge, the certificate holder shall test the containment 
system at an internal pressure at least 50 percent higher than the 
maximum normal operating pressure, to verify the capability of that 
system to maintain its structural integrity at that pressure;
    (c) The certificate holder shall conspicuously and durably mark the 
packaging with its model number, serial number, gross weight, and a 
package identification number assigned by the NRC. Before applying the 
model number, the certificate holder shall determine that the packaging 
has been fabricated in accordance with the design approved by the 
Commission; and
    (d) The licensee shall ascertain that the determinations in 
paragraphs (a) through (c) of this section have been made.

[60 FR 50264, Sept. 28, 1995, as amended at 80 FR 34013, June 12, 2015]



Sec. 71.87  Routine determinations.

    Before each shipment of licensed material, the licensee shall ensure 
that the package with its contents satisfies the applicable requirements 
of this part and of the license. The licensee shall determine that--
    (a) The package is proper for the contents to be shipped;
    (b) The package is in unimpaired physical condition except for 
superficial defects such as marks or dents;
    (c) Each closure device of the packaging, including any required 
gasket, is properly installed and secured and free of defects;
    (d) Any system for containing liquid is adequately sealed and has 
adequate space or other specified provision for expansion of the liquid;
    (e) Any pressure relief device is operable and set in accordance 
with written procedures;
    (f) The package has been loaded and closed in accordance with 
written procedures;
    (g) For fissile material, any moderator or neutron absorber, if 
required, is present and in proper condition;
    (h) Any structural part of the package that could be used to lift or 
tie down the package during transport is rendered inoperable for that 
purpose, unless it satisfies the design requirements of Sec. 71.45;
    (i) The level of non-fixed (removable) radioactive contamination on 
the external surfaces of each package offered for shipment is as low as 
reasonably achievable, and within the limits specified in DOT 
regulations in 49 CFR 173.443;
    (j) External radiation levels around the package and around the 
vehicle, if

[[Page 367]]

applicable, will not exceed the limits specified in Sec. 71.47 at any 
time during transportation; and
    (k) Accessible package surface temperatures will not exceed the 
limits specified in Sec. 71.43(g) at any time during transportation.



Sec. 71.88  Air transport of plutonium.

    (a) Notwithstanding the provisions of any general licenses and 
notwithstanding any exemptions stated directly in this part or included 
indirectly by citation of 49 CFR chapter I, as may be applicable, the 
licensee shall assure that plutonium in any form, whether for import, 
export, or domestic shipment, is not transported by air or delivered to 
a carrier for air transport unless:
    (1) The plutonium is contained in a medical device designed for 
individual human application; or
    (2) The plutonium is contained in a material in which the specific 
activity is less than or equal to the activity concentration values for 
plutonium specified in Appendix A, Table A-2, of this part, and in which 
the radioactivity is essentially uniformly distributed; or
    (3) The plutonium is shipped in a single package containing no more 
than an A2 quantity of plutonium in any isotope or form, and 
is shipped in accordance with Sec. 71.5; or
    (4) The plutonium is shipped in a package specifically authorized 
for the shipment of plutonium by air in the Certificate of Compliance 
for that package issued by the Commission.
    (b) Nothing in paragraph (a) of this section is to be interpreted as 
removing or diminishing the requirements of Sec. 73.24 of this chapter.
    (c) For a shipment of plutonium by air which is subject to paragraph 
(a)(4) of this section, the licensee shall, through special arrangement 
with the carrier, require compliance with 49 CFR 175.704, U.S. 
Department of Transportation regulations applicable to the air transport 
of plutonium.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]



Sec. 71.89  Opening instructions.

    Before delivery of a package to a carrier for transport, the 
licensee shall ensure that any special instructions needed to safely 
open the package have been sent to, or otherwise made available to, the 
consignee for the consignee's use in accordance with 10 CFR 20.1906(e).



Sec. 71.91  Records.

    (a) Each licensee shall maintain, for a period of 3 years after 
shipment, a record of each shipment of licensed material not exempt 
under Sec. 71.14, showing where applicable--
    (1) Identification of the packaging by model number and serial 
number;
    (2) Verification that there are no significant defects in the 
packaging, as shipped;
    (3) Volume and identification of coolant;
    (4) Type and quantity of licensed material in each package, and the 
total quantity of each shipment;
    (5) For each item of irradiated fissile material--
    (i) Identification by model number and serial number;
    (ii) Irradiation and decay history to the extent appropriate to 
demonstrate that its nuclear and thermal characteristics comply with 
license conditions; and
    (iii) Any abnormal or unusual condition relevant to radiation 
safety;
    (6) Date of the shipment;
    (7) For fissile packages and for Type B packages, any special 
controls exercised;
    (8) Name and address of the transferee;
    (9) Address to which the shipment was made; and
    (10) Results of the determinations required by Sec. 71.87 and by 
the conditions of the package approval.
    (b) Each certificate holder shall maintain, for a period of 3 years 
after the life of the packaging to which they apply, records identifying 
the packaging by model number, serial number, and date of manufacture.
    (c) The licensee, certificate holder, and an applicant for a CoC, 
shall make available to the Commission for inspection, upon reasonable 
notice, all records required by this part. Records are only valid if 
stamped, initialed, or signed and dated by authorized personnel, or 
otherwise authenticated.

[[Page 368]]

    (d) The licensee, certificate holder, and an applicant for a CoC 
shall maintain sufficient written records to furnish evidence of the 
quality of packaging. The records to be maintained include results of 
the determinations required by Sec. 71.85; design, fabrication, and 
assembly records; results of reviews, inspections, tests, and audits; 
results of monitoring work performance and materials analyses; and 
results of maintenance, modification, and repair activities. Inspection, 
test, and audit records must identify the inspector or data recorder, 
the type of observation, the results, the acceptability, and the action 
taken in connection with any deficiencies noted. These records must be 
retained for 3 years after the life of the packaging to which they 
apply.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004; 
80 FR 34013, June 12, 2015]



Sec. 71.93  Inspection and tests.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
permit the Commission, at all reasonable times, to inspect the licensed 
material, packaging, premises, and facilities in which the licensed 
material or packaging is used, provided, constructed, fabricated, 
tested, stored, or shipped.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
perform, and permit the Commission to perform, any tests the Commission 
deems necessary or appropriate for the administration of the regulations 
in this chapter.
    (c) The certificate holder and applicant for a CoC shall notify the 
NRC, in accordance with Sec. 71.1, 45 days in advance of starting 
fabrication of the first packaging under a CoC. This paragraph applies 
to any packaging used for the shipment of licensed material which has 
either--
    (1) A decay heat load in excess of 5 kW; or
    (2) A maximum normal operating pressure in excess of 103 kPa (15 
lbf/in \2\) gauge.

[69 FR 3796, Jan. 26, 2004]



Sec. 71.95  Reports.

    (a) The licensee, after requesting the certificate holder's input, 
shall submit a written report to the Commission of--
    (1) Instances in which there is a significant reduction in the 
effectiveness of any NRC-approved Type B or Type AF packaging during 
use; or
    (2) Details of any defects with safety significance in any NRC-
approved Type B or fissile material packaging, after first use.
    (3) Instances in which the conditions of approval in the Certificate 
of Compliance were not observed in making a shipment.
    (b) The licensee shall submit a written report to the Commission of 
instances in which the conditions in the certificate of compliance were 
not followed during a shipment.
    (c) Each licensee shall submit, in accordance with Sec. 71.1, a 
written report required by paragraph (a) or (b) of this section within 
60 days of the event or discovery of the event. The licensee shall also 
provide a copy of each report submitted to the NRC to the applicable 
certificate holder. Written reports prepared under other regulations may 
be submitted to fulfill this requirement if the reports contain all the 
necessary information, and the appropriate distribution is made. Using 
an appropriate method listed in Sec. 71.1(a), the licensee shall report 
to: ATTN: Document Control Desk, Director, Division of Spent Fuel 
Management, Office of Nuclear Material Safety and Safeguards. These 
written reports must include the following:
    (1) A brief abstract describing the major occurrences during the 
event, including all component or system failures that contributed to 
the event and significant corrective action taken or planned to prevent 
recurrence.
    (2) A clear, specific, narrative description of the event that 
occurred so that knowledgeable readers conversant with the requirements 
of part 71, but not familiar with the design of the packaging, can 
understand the complete event. The narrative description must include 
the following specific information as appropriate for the particular 
event.

[[Page 369]]

    (i) Status of components or systems that were inoperable at the 
start of the event and that contributed to the event;
    (ii) Dates and approximate times of occurrences;
    (iii) The cause of each component or system failure or personnel 
error, if known;
    (iv) The failure mode, mechanism, and effect of each failed 
component, if known;
    (v) A list of systems or secondary functions that were also affected 
for failures of components with multiple functions;
    (vi) The method of discovery of each component or system failure or 
procedural error;
    (vii) For each human performance-related root cause, a discussion of 
the cause(s) and circumstances;
    (viii) The manufacturer and model number (or other identification) 
of each component that failed during the event; and
    (ix) For events occurring during use of a packaging, the quantities 
and chemical and physical form(s) of the package contents.
    (3) An assessment of the safety consequences and implications of the 
event. This assessment must include the availability of other systems or 
components that could have performed the same function as the components 
and systems that failed during the event.
    (4) A description of any corrective actions planned as a result of 
the event, including the means employed to repair any defects, and 
actions taken to reduce the probability of similar events occurring in 
the future.
    (5) Reference to any previous similar events involving the same 
packaging that are known to the licensee or certificate holder.
    (6) The name and telephone number of a person within the licensee's 
organization who is knowledgeable about the event and can provide 
additional information.
    (7) The extent of exposure of individuals to radiation or to 
radioactive materials without identification of individuals by name.
    (d) Report legibility. The reports submitted by licensees and/or 
certificate holders under this section must be of sufficient quality to 
permit reproduction and micrographic processing.

[69 FR 3796, Jan. 26, 2004, as amended at 75 FR 73945, Nov. 30, 2010; 79 
FR 75740, Dec. 19, 2014]



Sec. 71.97  Advance notification of shipment of irradiated reactor
fuel and nuclear waste.

    (a)(1) As specified in paragraphs (b), (c), and (d) of this section, 
each licensee shall provide advance notification to the governor of a 
State, or the governor's designee, of the shipment of licensed material, 
within or across the boundary of the State, before the transport, or 
delivery to a carrier, for transport, of licensed material outside the 
confines of the licensee's plant or other place of use or storage.
    (2) As specified in paragraphs (b), (c), and (d) of this section, 
after June 11, 2013, each licensee shall provide advance notification to 
the Tribal official of participating Tribes referenced in paragraph 
(c)(3)(iii) of this section, or the official's designee, of the shipment 
of licensed material, within or across the boundary of the Tribe's 
reservation, before the transport, or delivery to a carrier, for 
transport, of licensed material outside the confines of the licensee's 
plant or other place of use or storage.
    (b) Advance notification is also required under this section for the 
shipment of licensed material, other than irradiated fuel, meeting the 
following three conditions:
    (1) The licensed material is required by this part to be in Type B 
packaging for transportation;
    (2) The licensed material is being transported to or across a State 
boundary en route to a disposal facility or to a collection point for 
transport to a disposal facility; and
    (3) The quantity of licensed material in a single package exceeds 
the least of the following:
    (i) 3000 times the A1 value of the radionuclides as 
specified in appendix A, Table A-1 for special form radioactive 
material;
    (ii) 3000 times the A2 value of the radionuclides as 
specified in appendix A, Table A-1 for normal form radioactive material; 
or

[[Page 370]]

    (iii) 1000 TBq (27,000 Ci).
    (c) Procedures for submitting advance notification. (1) The 
notification must be made in writing to:
    (i) The office of each appropriate governor or governor's designee;
    (ii) The office of each appropriate Tribal official or Tribal 
official's designee; and
    (iii) The Director, Division of Security Policy, Office of Nuclear 
Security and Incident Response.
    (2) A notification delivered by mail must be postmarked at least 7 
days before the beginning of the 7-day period during which departure of 
the shipment is estimated to occur.
    (3) A notification delivered by any other means than mail must reach 
the office of the governor or of the governor's designee or the Tribal 
official or Tribal official's designee at least 4 days before the 
beginning of the 7-day period during which departure of the shipment is 
estimated to occur.
    (i) A list of the names and mailing addresses of the governors' 
designees receiving advance notification of transportation of nuclear 
waste was published in the Federal Register on June 30, 1995 (60 FR 
34306).
    (ii) Contact information for each State, including telephone and 
mailing addresses of governors and governors' designees, and 
participating Tribes, including telephone and mailing addresses of 
Tribal officials and Tribal official's designees, is available on the 
NRC Web site at: https://scp.nrc.gov/special/designee.pdf.
    (iii) A list of the names and mailing addresses of the governors' 
designees and Tribal officials' designees of participating Tribes is 
available on request from the Director, Division of Material Safety, 
State, Tribal, and Rulemaking Programs, Office of Nuclear Material 
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    (4) The licensee shall retain a copy of the notification as a record 
for 3 years.
    (d) Information to be furnished in advance notification of shipment. 
Each advance notification of shipment of irradiated reactor fuel or 
nuclear waste must contain the following information:
    (1) The name, address, and telephone number of the shipper, carrier, 
and receiver of the irradiated reactor fuel or nuclear waste shipment;
    (2) A description of the irradiated reactor fuel or nuclear waste 
contained in the shipment, as specified in the regulations of DOT in 49 
CFR 172.202 and 172.203(d);
    (3) The point of origin of the shipment and the 7-day period during 
which departure of the shipment is estimated to occur;
    (4) The 7-day period during which arrival of the shipment at State 
boundaries or Tribal reservation boundaries is estimated to occur;
    (5) The destination of the shipment, and the 7-day period during 
which arrival of the shipment is estimated to occur; and
    (6) A point of contact, with a telephone number, for current 
shipment information.
    (e) Revision notice. A licensee who finds that schedule information 
previously furnished to a governor or governor's designee or a Tribal 
official or Tribal official's designee, in accordance with this section, 
will not be met, shall telephone a responsible individual in the office 
of the governor of the State or of the governor's designee or the Tribal 
official or the Tribal official's designee and inform that individual of 
the extent of the delay beyond the schedule originally reported. The 
licensee shall maintain a record of the name of the individual contacted 
for 3 years.
    (f) Cancellation notice. (1) Each licensee who cancels an irradiated 
reactor fuel or nuclear waste shipment for which advance notification 
has been sent shall send a cancellation notice to the governor of each 
State or to the governor's designee previously notified, each Tribal 
official or to the Tribal official's designee previously notified, and 
to the Director, Division of Security Policy, Office of Nuclear Security 
and Incident Response.
    (2) The licensee shall state in the notice that it is a cancellation 
and identify the advance notification that is

[[Page 371]]

being canceled. The licensee shall retain a copy of the notice as a 
record for 3 years.

[60 FR 50264, Sept. 28, 1995, as amended at 67 FR 3586, Jan. 25, 2002; 
68 FR 14529, Mar. 26, 2003; 68 FR 23575, May 5, 2003; 68 FR 58818, Oct. 
10, 2003; 74 FR 62683, Dec. 1, 2009; 75 FR 73945, Nov. 30, 2010; 77 FR 
34204, June 11, 2012; 78 FR 17021, Mar. 19, 2013; 79 FR 75741, Dec. 19, 
2014; 80 FR 74981, Dec. 1, 2015]



Sec. 71.99  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section; or
    (iv) Any term , condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.



Sec. 71.100  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 71 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 71 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 71.0, 71.2, 71.4, 71.6, 71.7, 71.10, 71.31, 71.33, 71.35, 
71.37, 71.38, 71.39, 71.40, 71.41, 71.43, 71.45, 71.47, 71.51, 71.55, 
71.59, 71.65, 71.71, 71.73, 71.74, 71.75, 71.77, 71.99, and 71.100.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3796, Jan. 26, 2004]



                       Subpart H_Quality Assurance

    Source: 69 FR 3796, Jan. 26, 2004, unless otherwise noted.



Sec. 71.101  Quality assurance requirements.

    (a) Purpose. This subpart describes quality assurance requirements 
applying to design, purchase, fabrication, handling, shipping, storing, 
cleaning, assembly, inspection, testing, operation, maintenance, repair, 
and modification of components of packaging that are important to 
safety. As used in this subpart, ``quality assurance'' comprises all 
those planned and systematic actions necessary to provide adequate 
confidence that a system or component will perform satisfactorily in 
service. Quality assurance includes quality control, which comprises 
those quality assurance actions related to control of the physical 
characteristics and quality of the material or component to 
predetermined requirements. Each certificate holder and applicant for a 
package approval is responsible for satisfying the quality assurance 
requirements that apply to design, fabrication, testing, and 
modification of packaging subject to this subpart. Each licensee is 
responsible for satisfying the quality assurance requirements that apply 
to its use of a packaging for the shipment of licensed material subject 
to this subpart.
    (b) Establishment of program. Each licensee, certificate holder, and 
applicant for a CoC shall establish, maintain, and execute a quality 
assurance program satisfying each of the applicable criteria of 
Sec. Sec. 71.101 through 71.137 and satisfying any specific provisions 
that are applicable to the licensee's activities including procurement 
of packaging. The licensee, certificate holder, and applicant for a CoC 
shall execute

[[Page 372]]

the applicable criteria in a graded approach to an extent that is 
commensurate with the quality assurance requirement's importance to 
safety.
    (c) Approval of program. (1) Before the use of any package for the 
shipment of licensed material subject to this subpart, each licensee 
shall obtain Commission approval of its quality assurance program. Using 
an appropriate method listed in Sec. 71.1(a), each licensee shall file 
a description of its quality assurance program, including a discussion 
of which requirements of this subpart are applicable and how they will 
be satisfied, by submitting the description to: ATTN: Document Control 
Desk, Director, Division of Spent Fuel Management, Office of Nuclear 
Material Safety and Safeguards.
    (2) Before the fabrication, testing, or modification of any package 
for the shipment of licensed material subject to this subpart, each 
certificate holder, or applicant for a Certificate of Compliance shall 
obtain Commission approval of its quality assurance program. Each 
certificate holder or applicant for a CoC shall, in accordance with 
Sec. 71.1, file a description of its quality assurance program, 
including a discussion of which requirements of this subpart are 
applicable and how they will be satisfied.
    (d) Existing package designs. The provisions of this paragraph deal 
with packages that have been approved for use in accordance with this 
part before January 1, 1979, and which have been designed in accordance 
with the provisions of this part in effect at the time of application 
for package approval. Those packages will be accepted as having been 
designed in accordance with a quality assurance program that satisfies 
the provisions of paragraph (b) of this section.
    (e) Existing packages. The provisions of this paragraph deal with 
packages that have been approved for use in accordance with this part 
before January 1, 1979, have been at least partially fabricated before 
that date, and for which the fabrication is in accordance with the 
provisions of this part in effect at the time of application for 
approval of package design. These packages will be accepted as having 
been fabricated and assembled in accordance with a quality assurance 
program that satisfies the provisions of paragraph (b) of this section.
    (f) Previously approved programs. A Commission-approved quality 
assurance program that satisfies the applicable criteria of subpart H of 
this part, Appendix B of part 50 of this chapter, or subpart G of part 
72 of this chapter, and that is established, maintained, and executed 
regarding transport packages, will be accepted as satisfying the 
requirements of paragraph (b) of this section. Before first use, the 
licensee, certificate holder, and applicant for a CoC shall notify the 
NRC, in accordance with Sec. 71.1, of its intent to apply its 
previously approved subpart H, Appendix B, or subpart G quality 
assurance program to transportation activities. The licensee, 
certificate holder, and applicant for a CoC shall identify the program 
by date of submittal to the Commission, Docket Number, and date of 
Commission approval.
    (g) Radiography containers. A program for transport container 
inspection and maintenance limited to radiographic exposure devices, 
source changers, or packages transporting these devices and meeting the 
requirements of Sec. 34.31(b) of this chapter or equivalent Agreement 
State requirement, is deemed to satisfy the requirements of Sec. Sec. 
71.17(b) and 71.101(b).

[69 FR 3796, Jan. 26, 2004, as amended at 75 FR 73945, Nov. 30, 2010; 79 
FR 75741, Dec. 19, 2014; 80 FR 34013, June 12, 2015]



Sec. 71.103  Quality assurance organization.

    (a) The licensee, certificate holder, and applicant for a 
Certificate of Compliance shall be responsible for the establishment and 
execution of the quality assurance program. The licensee, certificate 
holder, and applicant for a Certificate of Compliance may delegate to 
others, such as contractors, agents, or consultants, the work of 
establishing and executing the quality assurance program, or any part of 
the quality assurance program, but shall retain responsibility for the 
program. These activities include performing the functions associated 
with attaining quality objectives and the quality assurance functions.

[[Page 373]]

    (b) The quality assurance functions are--
    (1) Assuring that an appropriate quality assurance program is 
established and effectively executed; and
    (2) Verifying, by procedures such as checking, auditing, and 
inspection, that activities affecting the functions that are important 
to safety have been correctly performed.
    (c) The persons and organizations performing quality assurance 
functions must have sufficient authority and organizational freedom to--
    (1) Identify quality problems;
    (2) Initiate, recommend, or provide solutions; and
    (3) Verify implementation of solutions.
    (d) The persons and organizations performing quality assurance 
functions shall report to a management level that assures that the 
required authority and organizational freedom, including sufficient 
independence from cost and schedule, when opposed to safety 
considerations, are provided.
    (e) Because of the many variables involved, such as the number of 
personnel, the type of activity being performed, and the location or 
locations where activities are performed, the organizational structure 
for executing the quality assurance program may take various forms, 
provided that the persons and organizations assigned the quality 
assurance functions have the required authority and organizational 
freedom.
    (f) Irrespective of the organizational structure, the individual(s) 
assigned the responsibility for assuring effective execution of any 
portion of the quality assurance program, at any location where 
activities subject to this section are being performed, must have direct 
access to the levels of management necessary to perform this function.

[69 FR 3796, Jan. 26, 2004, as amended at 80 FR 34014, June 12, 2015]



Sec. 71.105  Quality assurance program.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish, at the earliest practicable time consistent with the schedule 
for accomplishing the activities, a quality assurance program that 
complies with the requirements of Sec. Sec. 71.101 through 71.137. The 
licensee, certificate holder, and applicant for a CoC shall document the 
quality assurance program by written procedures or instructions and 
shall carry out the program in accordance with those procedures 
throughout the period during which the packaging is used. The licensee, 
certificate holder, and applicant for a CoC shall identify the material 
and components to be covered by the quality assurance program, the major 
organizations participating in the program, and the designated functions 
of these organizations.
    (b) The licensee, certificate holder, and applicant for a CoC, 
through its quality assurance program, shall provide control over 
activities affecting the quality of the identified materials and 
components to an extent consistent with their importance to safety, and 
as necessary to assure conformance to the approved design of each 
individual package used for the shipment of radioactive material. The 
licensee, certificate holder, and applicant for a CoC shall assure that 
activities affecting quality are accomplished under suitably controlled 
conditions. Controlled conditions include the use of appropriate 
equipment; suitable environmental conditions for accomplishing the 
activity, such as adequate cleanliness; and assurance that all 
prerequisites for the given activity have been satisfied. The licensee, 
certificate holder, and applicant for a CoC shall take into account the 
need for special controls, processes, test equipment, tools, and skills 
to attain the required quality, and the need for verification of quality 
by inspection and test.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
base the requirements and procedures of its quality assurance program on 
the following considerations concerning the complexity and proposed use 
of the package and its components:
    (1) The impact of malfunction or failure of the item to safety;
    (2) The design and fabrication complexity or uniqueness of the item;
    (3) The need for special controls and surveillance over processes 
and equipment;
    (4) The degree to which functional compliance can be demonstrated by 
inspection or test; and

[[Page 374]]

    (5) The quality history and degree of standardization of the item.
    (d) The licensee, certificate holder, and applicant for a CoC shall 
provide for indoctrination and training of personnel performing 
activities affecting quality, as necessary to assure that suitable 
proficiency is achieved and maintained. The licensee, certificate 
holder, and applicant for a CoC shall review the status and adequacy of 
the quality assurance program at established intervals. Management of 
other organizations participating in the quality assurance program shall 
review regularly the status and adequacy of that part of the quality 
assurance program they are executing.



Sec. 71.106  Changes to quality assurance program.

    (a) Each quality assurance program approval holder shall submit, in 
accordance with Sec. 71.1(a), a description of a proposed change to its 
NRC-approved quality assurance program that will reduce commitments in 
the program description as approved by the NRC. The quality assurance 
program approval holder shall not implement the change before receiving 
NRC approval.
    (1) The description of a proposed change to the NRC-approved quality 
assurance program must identify the change, the reason for the change, 
and the basis for concluding that the revised program incorporating the 
change continues to satisfy the applicable requirements of subpart H of 
this part.
    (2) [Reserved]
    (b) Each quality assurance program approval holder may change a 
previously approved quality assurance program without prior NRC 
approval, if the change does not reduce the commitments in the quality 
assurance program previously approved by the NRC. Changes to the quality 
assurance program that do not reduce the commitments shall be submitted 
to the NRC every 24 months, in accordance with Sec. 71.1(a). In 
addition to quality assurance program changes involving administrative 
improvements and clarifications, spelling corrections, and non-
substantive changes to punctuation or editorial items, the following 
changes are not considered reductions in commitment:
    (1) The use of a quality assurance standard approved by the NRC that 
is more recent than the quality assurance standard in the certificate 
holder's or applicant's current quality assurance program at the time of 
the change;
    (2) The use of generic organizational position titles that clearly 
denote the position function, supplemented as necessary by descriptive 
text, rather than specific titles, provided that there is no substantive 
change to either the functions of the position or reporting 
responsibilities;
    (3) The use of generic organizational charts to indicate functional 
relationships, authorities, and responsibilities, or alternatively, the 
use of descriptive text, provided that there is no substantive change to 
the functional relationships, authorities, or responsibilities;
    (4) The elimination of quality assurance program information that 
duplicates language in quality assurance regulatory guides and quality 
assurance standards to which the quality assurance program approval 
holder has committed to on record; and
    (5) Organizational revisions that ensure that persons and 
organizations performing quality assurance functions continue to have 
the requisite authority and organizational freedom, including sufficient 
independence from cost and schedule when opposed to safety 
considerations.
    (c) Each quality assurance program approval holder shall maintain 
records of quality assurance program changes.

[80 FR 34014, June 12, 2015]



Sec. 71.107  Package design control.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that applicable regulatory requirements and 
the package design, as specified in the license or CoC for those 
materials and components to which this section applies, are correctly 
translated into specifications, drawings, procedures, and instructions. 
These measures must include provisions to assure that appropriate 
quality standards are specified and included in design documents and

[[Page 375]]

that deviations from standards are controlled. Measures must be 
established for the selection and review for suitability of application 
of materials, parts, equipment, and processes that are essential to the 
functions of the materials, parts, and components of the packaging that 
are important to safety.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
establish measures for the identification and control of design 
interfaces and for coordination among participating design 
organizations. These measures must include the establishment of written 
procedures, among participating design organizations, for the review, 
approval, release, distribution, and revision of documents involving 
design interfaces. The design control measures must provide for 
verifying or checking the adequacy of design, by methods such as design 
reviews, alternate or simplified calculational methods, or by a suitable 
testing program. For the verifying or checking process, the licensee 
shall designate individuals or groups other than those who were 
responsible for the original design, but who may be from the same 
organization. Where a test program is used to verify the adequacy of a 
specific design feature in lieu of other verifying or checking 
processes, the licensee, certificate holder, and applicant for a CoC 
shall include suitable qualification testing of a prototype or sample 
unit under the most adverse design conditions. The licensee, certificate 
holder, and applicant for a CoC shall apply design control measures to 
the following:
    (1) Criticality physics, radiation shielding, stress, thermal, 
hydraulic, and accident analyses;
    (2) Compatibility of materials;
    (3) Accessibility for inservice inspection, maintenance, and repair;
    (4) Features to facilitate decontamination; and
    (5) Delineation of acceptance criteria for inspections and tests.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
subject design changes, including field changes, to design control 
measures commensurate with those applied to the original design. Changes 
in the conditions specified in the CoC require prior NRC approval.



Sec. 71.109  Procurement document control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that adequate quality is required in the 
documents for procurement of material, equipment, and services, whether 
purchased by the licensee, certificate holder, and applicant for a CoC 
or by its contractors or subcontractors. To the extent necessary, the 
licensee, certificate holder, and applicant for a CoC shall require 
contractors or subcontractors to provide a quality assurance program 
consistent with the applicable provisions of this part.



Sec. 71.111  Instructions, procedures, and drawings.

    The licensee, certificate holder, and applicant for a CoC shall 
prescribe activities affecting quality by documented instructions, 
procedures, or drawings of a type appropriate to the circumstances and 
shall require that these instructions, procedures, and drawings be 
followed. The instructions, procedures, and drawings must include 
appropriate quantitative or qualitative acceptance criteria for 
determining that important activities have been satisfactorily 
accomplished.



Sec. 71.113  Document control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control the issuance of documents such as 
instructions, procedures, and drawings, including changes, that 
prescribe all activities affecting quality. These measures must assure 
that documents, including changes, are reviewed for adequacy, approved 
for release by authorized personnel, and distributed and used at the 
location where the prescribed activity is performed.



Sec. 71.115  Control of purchased material, equipment, and services.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that purchased material, equipment, and 
services, whether purchased directly or through contractors and 
subcontractors, conform

[[Page 376]]

to the procurement documents. These measures must include provisions, as 
appropriate, for source evaluation and selection, objective evidence of 
quality furnished by the contractor or subcontractor, inspection at the 
contractor or subcontractor source, and examination of products on 
delivery.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
have available documentary evidence that material and equipment conform 
to the procurement specifications before installation or use of the 
material and equipment. The licensee, certificate holder, and applicant 
for a CoC shall retain, or have available, this documentary evidence for 
the life of the package to which it applies. The licensee, certificate 
holder, and applicant for a CoC shall assure that the evidence is 
sufficient to identify the specific requirements met by the purchased 
material and equipment.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
assess the effectiveness of the control of quality by contractors and 
subcontractors at intervals consistent with the importance, complexity, 
and quantity of the product or services.



Sec. 71.117  Identification and control of materials, parts, 
and components.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures for the identification and control of materials, 
parts, and components. These measures must assure that identification of 
the item is maintained by heat number, part number, or other appropriate 
means, either on the item or on records traceable to the item, as 
required throughout fabrication, installation, and use of the item. 
These identification and control measures must be designed to prevent 
the use of incorrect or defective materials, parts, and components.



Sec. 71.119  Control of special processes.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that special processes, including welding, 
heat treating, and nondestructive testing are controlled and 
accomplished by qualified personnel using qualified procedures in 
accordance with applicable codes, standards, specifications, criteria, 
and other special requirements.



Sec. 71.121  Internal inspection.

    The licensee, certificate holder, and applicant for a CoC shall 
establish and execute a program for inspection of activities affecting 
quality by or for the organization performing the activity, to verify 
conformance with the documented instructions, procedures, and drawings 
for accomplishing the activity. The inspection must be performed by 
individuals other than those who performed the activity being inspected. 
Examination, measurements, or tests of material or products processed 
must be performed for each work operation where necessary to assure 
quality. If direct inspection of processed material or products is not 
carried out, indirect control by monitoring processing methods, 
equipment, and personnel must be provided. Both inspection and process 
monitoring must be provided when quality control is inadequate without 
both. If mandatory inspection hold points, which require witnessing or 
inspecting by the licensee's designated representative and beyond which 
work should not proceed without the consent of its designated 
representative, are required, the specific hold points must be indicated 
in appropriate documents.



Sec. 71.123  Test control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish a test program to assure that all testing required to 
demonstrate that the packaging components will perform satisfactorily in 
service is identified and performed in accordance with written test 
procedures that incorporate the requirements of this part and the 
requirements and acceptance limits contained in the package approval. 
The test procedures must include provisions for assuring that all 
prerequisites for the given test are met, that adequate test 
instrumentation is available and used, and that the test is performed 
under suitable environmental conditions. The licensee, certificate 
holder, and applicant for a CoC shall document and evaluate the test 
results to assure that test requirements have been satisfied.

[[Page 377]]



Sec. 71.125  Control of measuring and test equipment.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that tools, gauges, instruments, and other 
measuring and testing devices used in activities affecting quality are 
properly controlled, calibrated, and adjusted at specified times to 
maintain accuracy within necessary limits.



Sec. 71.127  Handling, storage, and shipping control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control, in accordance with instructions, the 
handling, storage, shipping, cleaning, and preservation of materials and 
equipment to be used in packaging to prevent damage or deterioration. 
When necessary for particular products, special protective environments, 
such as inert gas atmosphere, and specific moisture content and 
temperature levels must be specified and provided.



Sec. 71.129  Inspection, test, and operating status.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to indicate, by the use of markings such as stamps, 
tags, labels, routing cards, or other suitable means, the status of 
inspections and tests performed upon individual items of the packaging. 
These measures must provide for the identification of items that have 
satisfactorily passed required inspections and tests, where necessary to 
preclude inadvertent bypassing of the inspections and tests.
    (b) The licensee shall establish measures to identify the operating 
status of components of the packaging, such as tagging valves and 
switches, to prevent inadvertent operation.



Sec. 71.131  Nonconforming materials, parts, or components.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control materials, parts, or components that do 
not conform to the licensee's requirements to prevent their inadvertent 
use or installation. These measures must include, as appropriate, 
procedures for identification, documentation, segregation, disposition, 
and notification to affected organizations. Nonconforming items must be 
reviewed and accepted, rejected, repaired, or reworked in accordance 
with documented procedures.



Sec. 71.133  Corrective action.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that conditions adverse to quality, such as 
deficiencies, deviations, defective material and equipment, and 
nonconformances, are promptly identified and corrected. In the case of a 
significant condition adverse to quality, the measures must assure that 
the cause of the condition is determined and corrective action taken to 
preclude repetition. The identification of the significant condition 
adverse to quality, the cause of the condition, and the corrective 
action taken must be documented and reported to appropriate levels of 
management.



Sec. 71.135  Quality assurance records.

    The licensee, certificate holder, and applicant for a Certificate of 
Compliance shall maintain sufficient written records to describe the 
activities affecting quality. These records must include changes to the 
quality assurance program as required by Sec. 71.106, the instructions, 
procedures, and drawings required by Sec. 71.111 to prescribe quality 
assurance activities, and closely related specifications such as 
required qualifications of personnel, procedures, and equipment. The 
records must include the instructions or procedures that establish a 
records retention program that is consistent with applicable regulations 
and designates factors such as duration, location, and assigned 
responsibility. The licensee, certificate holder, and applicant for a 
Certificate of Compliance shall retain these records for 3 years beyond 
the date when the licensee, certificate holder, and applicant for a 
Certificate of Compliance last engage in the activity for which the 
quality assurance program was developed. If any portion of the quality 
assurance program, written procedures or instructions is superseded, the 
licensee, certificate holder,

[[Page 378]]

and applicant for a Certificate of Compliance shall retain the 
superseded material for 3 years after it is superseded.

[80 FR 34014, June 12, 2015]



Sec. 71.137  Audits.

    The licensee, certificate holder, and applicant for a CoC shall 
carry out a comprehensive system of planned and periodic audits to 
verify compliance with all aspects of the quality assurance program and 
to determine the effectiveness of the program. The audits must be 
performed in accordance with written procedures or checklists by 
appropriately trained personnel not having direct responsibilities in 
the areas being audited. Audited results must be documented and reviewed 
by management having responsibility in the area audited. Followup 
action, including reaudit of deficient areas, must be taken where 
indicated.



     Sec. Appendix A to Part 71--Determination of A1 and 
                              A2

    I. Values of A1 and A2 for individual 
radionuclides, which are the bases for many activity limits elsewhere in 
these regulations, are given in Table A-1. The curie (Ci) values 
specified are obtained by converting from the Terabecquerel (TBq) value. 
The Terabecquerel values are the regulatory standard. The curie values 
are for information only and are not intended to be the regulatory 
standard. Where values of A1 and A2 are unlimited, 
it is for radiation control purposes only. For nuclear criticality 
safety, some materials are subject to controls placed on fissile 
material.
    II. a. For individual radionuclides whose identities are known, but 
which are not listed in Table A-1, the A1 and A2 
values contained in Table A-3 may be used. Otherwise, the licensee shall 
obtain prior Commission approval of the A1 and A2 
values for radionuclides not listed in Table A-1, before shipping the 
material.
    b. For individual radionuclides whose identities are known, but 
which are not listed in Table A-2, the exempt material activity 
concentration and exempt consignment activity values contained in Table 
A-3 may be used. Otherwise, the licensee shall obtain prior Commission 
approval of the exempt material activity concentration and exempt 
consignment activity values for radionuclides not listed in Table A-2, 
before shipping the material.
    c. The licensee shall submit requests for prior approval, described 
under paragraphs II.a. and II.b. of this Appendix, to the Commission, in 
accordance with Sec. 71.1 of this part.
    III. In the calculations of A1 and A2 for a 
radionuclide not in Table A-1, a single radioactive decay chain, in 
which radionuclides are present in their naturally occurring 
proportions, and in which no daughter radionuclide has a half-life 
either longer than 10 days, or longer than that of the parent 
radionuclide, shall be considered as a single radionuclide, and the 
activity to be taken into account, and the A1 and 
A2 value to be applied, shall be those corresponding to the 
parent radionuclide of that chain. In the case of radioactive decay 
chains in which any daughter radionuclide has a half-life either longer 
than 10 days, or greater than that of the parent radionuclide, the 
parent and those daughter radionuclides shall be considered as mixtures 
of different radionuclides.
    IV. For mixtures of radionuclides whose identities and respective 
activities are known, the following conditions apply:
    a. For special form radioactive material, the maximum quantity 
transported in a Type A package is as follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.094

where B(i) is the activity of radionuclide i in special form, and 
A1(i) is the A1 value for radionuclide i.
    b. For normal form radioactive material, the maximum quantity 
transported in a Type A package is as follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.095


[[Page 379]]


where B(i) is the activity of radionuclide i in normal form, and 
A2(i) is the A2 value for radionuclide i.
    c. If the package contains both special and normal form radioactive 
material, the activity that may be transported in a Type A package is as 
follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.096

where B(i) is the activity of radionuclide i as special form radioactive 
material, A1(i) is the A1 value for radionuclide 
i, C(j) is the activity of radionuclide j as normal form radioactive 
material, and A2(j) is the A2 value for 
radionuclide j.
    d. Alternatively, the A1 value for mixtures of special 
form material may be determined as follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.097

where f(i) is the fraction of activity for radionuclide i in the mixture 
and A1(i) is the appropriate A1 value for 
radionuclide i.
    e. Alternatively, the A2 value for mixtures of normal 
form material may be determined as follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.098

where f(i) is the fraction of activity for radionuclide i in the mixture 
and A2(i) is the appropriate A2 value for 
radionuclide i.
    f. The exempt activity concentration for mixtures of nuclides may be 
determined as follows:
[GRAPHIC] [TIFF OMITTED] TR12JN15.099

where f(i) is the fraction of activity concentration of radionuclide i 
in the mixture and [A](i) is the activity concentration for exempt 
material containing radionuclide i.
    g. The activity limit for an exempt consignment for mixtures of 
radionuclides may be determined as follows:

[[Page 380]]

[GRAPHIC] [TIFF OMITTED] TR12JN15.100

where f(i) is the fraction of activity of radionuclide i in the mixture 
and A(i) is the activity limit for exempt consignments for radionuclide 
i.

    V.a. When the identity of each radionuclide is known, but the 
individual activities of some of the radionuclides are not known, the 
radionuclides may be grouped, and the lowest A1 or 
A2 value, as appropriate, for the radionuclides in each group 
may be used in applying the formulas in paragraph IV. Groups may be 
based on the total alpha activity and the total beta/gamma activity when 
these are known, using the lowest A1 or A2 values 
for the alpha emitters and beta/gamma emitters.
    b. When the identity of each radionuclide is known but the 
individual activities of some of the radionuclides are not known, the 
radionuclides may be grouped and the lowest [A] (activity concentration 
for exempt material) or A (activity limit for exempt consignment) value, 
as appropriate, for the radionuclides in each group may be used in 
applying the formulas in paragraph IV of this appendix. Groups may be 
based on the total alpha activity and the total beta/gamma activity when 
these are known, using the lowest [A] or A values for the alpha emitters 
and beta/gamma emitters, respectively.

                                                      Table A-1--A1 and A2 Values For Radionuclides
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                                                                                                                 Specific activity
      Symbol of radionuclide        Element and atomic       A1 (TBq)       A1 (Ci)\b\       A2 (TBq)       A2 (Ci)\b\   -------------------------------
                                          number                                                                              (TBq/g)         (Ci/g)
--------------------------------------------------------------------------------------------------------------------------------------------------------
Ac-225 (a).......................  Actinium (89).......  8.0 x 10-1       2.2 x 10\1\     6.0 x 10-3      1.6 x 10-1      2.1 x 103       5.8 x 10\4\
Ac-227 (a).......................  ....................  9.0 x 10-1       2.4 x 10\1\     9.0 x 10-5      2.4 x 10-3      2.7             7.2 x 10\1\
Ac-228...........................  ....................  6.0 x 10-1       1.6 x 10\1\     5.0 x 10-1      1.4 x 10\1\     8.4 x 10\4\     2.2 x 10\6\
Ag-105...........................  Silver (47).........  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     1.1 x 103       3.0 x 10\4\
Ag-108m (a)......................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     9.7 x 10-1      2.6 x 10\1\
Ag-110m (a)......................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.8 x 102       4.7 x 103
Ag-111...........................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     5.8 x 103       1.6 x 10\5\
Al-26............................  Aluminum (13).......  1.0 x 10-1       2.7             1.0 x 10-1      2.7             7.0 x 10-4      1.9 x 10-2
Am-241...........................  Americium (95)......  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      1.3 x 10-1      3.4
Am-242m (a)......................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      3.6 x 10-1      1.0 x 10\1\
Am-243 (a).......................  ....................  5.0              1.4 x 102       1.0 x 10-3      2.7 x 10-2      7.4 x 10-3      2.0 x 10-1
Ar-37............................  Argon (18)..........  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       3.7 x 103       9.9 x 10\4\
Ar-39............................  ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10\1\     5.4 x 102       1.3             3.4 x 10\1\
Ar-41............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.5 x 10\6\     4.2 x 10\7\
As-72............................  Arsenic (33)........  3.0 x 10-1       8.1             3.0 x 10-1      8.1             6.2 x 10\4\     1.7 x 10\6\
As-73............................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       8.2 x 102       2.2 x 10\4\
As-74............................  ....................  1.0              2.7 x 10\1\     9.0 x 10-1      2.4 x 10\1\     3.7 x 103       9.9 x 10\4\
As-76............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             5.8 x 10\4\     1.6 x 10\6\
As-77............................  ....................  2.0 x 10\1\      5.4 x 102       7.0 x 10-1      1.9 x 10\1\     3.9 x 10\4\     1.0 x 10\6\
At-211 (a).......................  Astatine (85).......  2.0 x 10\1\      5.4 x 102       5.0 x 10-1      1.4 x 10\1\     7.6 x 10\4\     2.1 x 10\6\
Au-193...........................  Gold (79)...........  7.0              1.9 x 102       2.0             5.4 x 10\1\     3.4 x 10\4\     9.2 x 10\5\
Au-194...........................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.5 x 10\4\     4.1 x 10\5\
Au-195...........................  ....................  1.0 x 10\1\      2.7 x 102       6.0             1.6 x 102       1.4 x 102       3.7 x 103
Au-198...........................  ....................  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     9.0 x 103       2.4 x 10\5\
Au-199...........................  ....................  1.0 x 10\1\      2.7 x 102       6.0 x 10-1      1.6 x 10\1\     7.7 x 103       2.1 x 10\5\
Ba-131 (a).......................  Barium (56).........  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     3.1 x 103       8.4 x 10\4\
Ba-133...........................  ....................  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     9.4             2.6 x 102
Ba-133m..........................  ....................  2.0 x 10\1\      5.4 x 102       6.0 x 10-1      1.6 x 10\1\     2.2 x 10\4\     6.1 x 10\5\
Ba-140 (a).......................  ....................  5.0 x 10-1       1.4 x 10\1\     3.0 x 10-1      8.1             2.7 x 103       7.3 x 10\4\
Be-7.............................  Beryllium (4).......  2.0 x 10\1\      5.4 x 102       2.0 x 10\1\     5.4 x 102       1.3 x 10\4\     3.5 x 10\5\
Be-10............................  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-1      1.6 x 10\1\     8.3 x 10-4      2.2 x 10-2
Bi-205...........................  Bismuth (83)........  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     1.5 x 103       4.2 x 10\4\
Bi-206...........................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             3.8 x 103       1.0 x 10\5\
Bi-207...........................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     1.9             5.2 x 10\1\
Bi-210...........................  ....................  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     4.6 x 103       1.2 x 10\5\
Bi-210m (a)......................  ....................  6.0 x 10-1       1.6 x 10\1\     2.0 x 10-2      5.4 x 10-1      2.1 x 10-5      5.7 x 10-4
Bi-212 (a).......................  ....................  7.0 x 10-1       1.9 x 10\1\     6.0 x 10-1      1.6 x 10\1\     5.4 x 10\5\     1.5 x 10\7\
Bk-247...........................  Berkelium (97)......  8.0              2.2 x 102       8.0 x 10-4      2.2 x 10-2      3.8 x 10-2      1.0
Bk-249 (a).......................  ....................  4.0 x 10\1\      1.1 x 103       3.0 x 10-1      8.1             6.1 x 10\1\     1.6 x 103
Br-76............................  Bromine (35)........  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     9.4 x 10\4\     2.5 x 10\6\
Br-77............................  ....................  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     2.6 x 10\4\     7.1 x 10\5\
Br-82............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     4.0 x 10\4\     1.1 x 10\6\

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C-11.............................  Carbon (6)..........  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.1 x 10\7\     8.4 x 10\8\
C-14.............................  ....................  4.0 x 10\1\      1.1 x 103       3.0             8.1 x 10\1\     1.6 x 10-1      4.5
Ca-41............................  Calcium (20)........  Unlimited        Unlimited       Unlimited       Unlimited       3.1 x 10-3      8.5 x 10-2
Ca-45............................  ....................  4.0 x 10\1\      1.1 x 103       1.0             2.7 x 10\1\     6.6 x 102       1.8 x 10\4\
Ca-47 (a)........................  ....................  3.0              8.1 x 10\1\     3.0 x 10-1      8.1             2.3 x 10\4\     6.1 x 10\5\
Cd-109...........................  Cadmium (48)........  3.0 x 10\1\      8.1 x 102       2.0             5.4 x 10\1\     9.6 x 10\1\     2.6 x 103
Cd-113m..........................  ....................  4.0 x 10\1\      1.1 x 103       5.0 x 10-1      1.4 x 10\1\     8.3             2.2 x 102
Cd-115 (a).......................  ....................  3.0              8.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.9 x 10\4\     5.1 x 10\5\
Cd-115m..........................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     9.4 x 102       2.5 x 10\4\
Ce-139...........................  Cerium (58).........  7.0              1.9 x 102       2.0             5.4 x 10\1\     2.5 x 102       6.8 x 103
Ce-141...........................  ....................  2.0 x 10\1\      5.4 x 102       6.0 x 10-1      1.6 x 10\1\     1.1 x 103       2.8 x 10\4\
Ce-143...........................  ....................  9.0 x 10-1       2.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.5 x 10\4\     6.6 x 10\5\
Ce-144 (a).......................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             1.2 x 102       3.2 x 103
Cf-248...........................  Californium (98)....  4.0 x 10\1\      1.1 x 103       6.0 x 10-3      1.6 x 10-1      5.8 x 10\1\     1.6 x 103
Cf-249...........................  ....................  3.0              8.1 x 10\1\     8.0 x 10-4      2.2 x 10-2      1.5 x 10-1      4.1
Cf-250...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10-3      5.4 x 10-2      4.0             1.1 x 102
Cf-251...........................  ....................  7.0              1.9 x 102       7.0 x 10-4      1.9 x 10-2      5.9 x 10-2      1.6
Cf-252...........................  ....................  1.0 x 10-\1\     2.7             3.0 x 10-\3\    8.1 x 10-\2\    2.0 x 10\1\     5.4 x 10\2\
Cf-253 (a).......................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10-2      1.1             1.1 x 103       2.9 x 10\4\
Cf-254...........................  ....................  1.0 x 10-3       2.7 x 10-2      1.0 x 10-3      2.7 x 10-2      3.1 x 102       8.5 x 103
Cl-36............................  Chlorine (17).......  1.0 x 10\1\      2.7 x 102       6.0 x 10-1      1.6 x 10\1\     1.2 x 10-3      3.3 x 10-2
Cl-38............................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             4.9 x 10\6\     1.3 x 10\8\
Cm-240...........................  Curium (96).........  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      7.5 x 102       2.0 x 10\4\
Cm-241...........................  ....................  2.0              5.4 x 10\1\     1.0             2.7 x 10\1\     6.1 x 102       1.7 x 10\4\
Cm-242...........................  ....................  4.0 x 10\1\      1.1 x 103       1.0 x 10-2      2.7 x 10-1      1.2 x 102       3.3 x 103
Cm-243...........................  ....................  9.0              2.4 x 102       1.0 x 10-3      2.7 x 10-2      1.9 x 10-3      5.2 x 10\1\
Cm-244...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10-3      5.4 x 10-2      3.0             8.1 x 10\1\
Cm-245...........................  ....................  9.0              2.4 x 102       9.0 x 10-4      2.4 x 10-2      6.4 x 10-3      1.7 x 10-1
Cm-246...........................  ....................  9.0              2.4 x 102       9.0 x 10-4      2.4 x 10-2      1.1 x 10-2      3.1 x 10-1
Cm-247 (a).......................  ....................  3.0              8.1 x 10\1\     1.0 x 10-3      2.7 x 10-2      3.4 x 10-6      9.3 x 10-5
Cm-248...........................  ....................  2.0 x 10-2       5.4 x 10-1      3.0 x 10-4      8.1 x 10-3      1.6 x 10-4      4.2 x 10-3
Co-55............................  Cobalt (27).........  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     1.1 x 10\5\     3.1 x 10\6\
Co-56............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.1 x 103       3.0 x 10\4\
Co-57............................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10\1\     2.7 x 102       3.1 x 102       8.4 x 103
Co-58............................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.2 x 103       3.2 x 10\4\
Co-58m...........................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       2.2 x 10\5\     5.9 x 10\6\
Co-60............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     4.2 x 10\1\     1.1 x 103
Cr-51............................  Chromium (24).......  3.0 x 10\1\      8.1 x 102       3.0 x 10\1\     8.1 x 102       3.4 x 103       9.2 x 10\4\
Cs-129...........................  Cesium (55).........  4.0              1.1 x 102       4.0             1.1 x 102       2.8 x 10\4\     7.6 x 10\5\
Cs-131...........................  ....................  3.0 x 10\1\      8.1 x 102       3.0 x 10\1\     8.1 x 102       3.8 x 103       1.0 x 10\5\
Cs-132...........................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     5.7 x 103       1.5 x 10\5\
Cs-134...........................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     4.8 x 10\1\     1.3 x 103
Cs-134m..........................  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-1      1.6 x 10\1\     3.0 x 10\5\     8.0 x 10\6\
Cs-135...........................  ....................  4.0 x 10\1\      1.1 x 103       1.0             2.7 x 10\1\     4.3 x 10-5      1.2 x 10-3
Cs-136...........................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     2.7 x 103       7.3 x 10\4\
Cs-137 (a).......................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.2             8.7 x 10\1\
Cu-64............................  Copper (29).........  6.0              1.6 x 102       1.0             2.7 x 10\1\     1.4 x 10\5\     3.9 x 10\6\
Cu-67............................  ....................  1.0 x 10\1\      2.7 x 102       7.0 x 10-1      1.9 x 10\1\     2.8 x 10\4\     7.6 x 10\5\
Dy-159...........................  Dysprosium (66).....  2.0 x 10\1\      5.4 x 102       2.0 x 10\1\     5.4 x 102       2.1 x 102       5.7 x 103
Dy-165...........................  ....................  9.0 x 10-1       2.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.0 x 10\5\     8.2 x 10\6\
Dy-166 (a).......................  ....................  9.0 x 10-1       2.4 x 10\1\     3.0 x 10-1      8.1             8.6 x 103       2.3 x 10\5\
Er-169...........................  Erbium (68).........  4.0 x 10\1\      1.1 x 103       1.0             2.7 x 10\1\     3.1 x 103       8.3 x 10\4\
Er-171...........................  ....................  8.0 x 10-1       2.2 x 10\1\     5.0 x 10-1      1.4 x 10\1\     9.0 x 10\4\     2.4 x 10\6\
Eu-147...........................  Europium (63).......  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     1.4 x 103       3.7 x 10\4\
Eu-148...........................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     6.0 x 102       1.6 x 10\4\
Eu-149...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10\1\     5.4 x 102       3.5 x 102       9.4 x 103
Eu-150 (short lived).............  ....................  2.0              5.4 x 10\1\     7.0 x 10-1      1.9 x 10\1\     6.1 x 10\4\     1.6 x 10\6\
Eu-150 (long lived)..............  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     6.1 x 10\4\     1.6 x 10\6\
Eu-152...........................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     6.5             1.8 x 102
Eu-152m..........................  ....................  8.0 x 10-1       2.2 x 10\1\     8.0 x 10-1      2.2 x 10\1\     8.2 x 10\4\     2.2 x 10\6\
Eu-154...........................  ....................  9.0 x 10-1       2.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     9.8             2.6 x 102
Eu-155...........................  ....................  2.0 x 10\1\      5.4 x 102       3.0             8.1 x 10\1\     1.8 x 10\1\     4.9 x 102
Eu-156...........................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     2.0 x 103       5.5 x 10\4\
F-18.............................  Fluorine (9)........  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.5 x 10\6\     9.5 x 10\7\
Fe-52 (a)........................  Iron (26)...........  3.0 x 10-1       8.1             3.0 x 10-1      8.1             2.7 x 10\5\     7.3 x 10\6\
Fe-55............................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       8.8 x 10\1\     2.4 x 103
Fe-59............................  ....................  9.0 x 10-1       2.4 x 10\1\     9.0 x 10-1      2.4 x 10\1\     1.8 x 103       5.0 x 10\4\
Fe-60 (a)........................  ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10-1      5.4             7.4 x 10-4      2.0 x 10-2
Ga-67............................  Gallium (31)........  7.0              1.9 x 102       3.0             8.1 x 10\1\     2.2 x 10\4\     6.0 x 10\5\
Ga-68............................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     1.5 x 10\6\     4.1 x 10\7\

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Ga-72............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.1 x 10\5\     3.1 x 10\6\
Gd-146 (a).......................  Gadolinium (64).....  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     6.9 x 102       1.9 x 10\4\
Gd-148...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10-3      5.4 x 10-2      1.2             3.2 x 10\1\
Gd-153...........................  ....................  1.0 x 10\1\      2.7 x 102       9.0             2.4 x 102       1.3 x 102       3.5 x 103
Gd-159...........................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.9 x 10\4\     1.1 x 10\6\
Ge-68 (a)........................  Germanium (32)......  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     2.6 x 102       7.1 x 103
Ge-71............................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       5.8 x 103       1.6 x 10\5\
Ge-77............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.3 x 10\5\     3.6 x 10\6\
Hf-172 (a).......................  Hafnium (72)........  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     4.1 x 10\1\     1.1 x 103
Hf-175...........................  ....................  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     3.9 x 102       1.1 x 10\4\
Hf-181...........................  ....................  2.0              5.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     6.3 x 102       1.7 x 10\4\
Hf-182...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       8.1 x 10-6      2.2 x 10-4
Hg-194 (a).......................  Mercury (80)........  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.3 x 10-1      3.5
Hg-195m (a)......................  ....................  3.0              8.1 x 10\1\     7.0 x 10-1      1.9 x 10\1\     1.5 x 10\4\     4.0 x 10\5\
Hg-197...........................  ....................  2.0 x 10\1\      5.4 x 102       1.0 x 10\1\     2.7 x 102       9.2 x 103       2.5 x 10\5\
Hg-197m..........................  ....................  1.0 x 10\1\      2.7 x 102       4.0 x 10-1      1.1 x 10\1\     2.5 x 10\4\     6.7 x 10\5\
Hg-203...........................  ....................  5.0              1.4 x 102       1.0             2.7 x 10\1\     5.1 x 102       1.4 x 10\4\
Ho-166...........................  Holmium (67)........  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     2.6 x 10\4\     7.0 x 10\5\
Ho-166m..........................  ....................  6.0 x 10-1       1.6 x 10\1\     5.0 x 10-1      1.4 x 10\1\     6.6 x 10-2      1.8
I-123............................  Iodine (53).........  6.0              1.6 x 102       3.0             8.1 x 10\1\     7.1 x 10\4\     1.9 x 10\6\
I-124............................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     9.3 x 103       2.5 x 10\5\
I-125............................  ....................  2.0 x 10\1\      5.4 x 102       3.0             8.1 x 10\1\     6.4 x 102       1.7 x 10\4\
I-126............................  ....................  2.0              5.4 x 10\1\     1.0             2.7 x 10\1\     2.9 x 103       8.0 x 10\4\
I-129............................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       6.5 x 10-6      1.8 x 10-4
I-131............................  ....................  3.0              8.1 x 10\1\     7.0 x 10-1      1.9 x 10\1\     4.6 x 103       1.2 x 10\5\
I-132............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     3.8 x 10\5\     1.0 x 10\7\
I-133............................  ....................  7.0 x 10-1       1.9 x 10\1\     6.0 x 10-1      1.6 x 10\1\     4.2 x 10\4\     1.1 x 10\6\
I-134............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             9.9 x 10\5\     2.7 x 10\7\
I-135 (a)........................  ....................  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.3 x 10\5\     3.5 x 10\6\
In-111...........................  Indium (49).........  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     1.5 x 10\4\     4.2 x 10\5\
In-113m..........................  ....................  4.0              1.1 x 102       2.0             5.4 x 10\1\     6.2 x 10\5\     1.7 x 10\7\
In-114m (a)......................  ....................  1.0 x 10\1\      2.7 x 102       5.0 x 10-1      1.4 x 10\1\     8.6 x 102       2.3 x 10\4\
In-115m..........................  ....................  7.0              1.9 x 102       1.0             2.7 x 10\1\     2.2 x 10\5\     6.1 x 10\6\
Ir-189 (a).......................  Iridium (77)........  1.0 x 10\1\      2.7 x 102       1.0 x 10\1\     2.7 x 102       1.9 x 103       5.2 x 10\4\
Ir-190...........................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     2.3 x 103       6.2 x 10\4\
Ir-192...........................  ....................  \c\ 1.0          \c\ 2.7 x       6.0 x 10-\1\    1.6 x 10\1\     3.4 x 10\2\     9.2 x 10\3\
                                                                           10\1\
Ir-194...........................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             3.1 x 10\4\     8.4 x 10\5\
K-40.............................  Potassium (19)......  9.0 x 10-1       2.4 x 10\1\     9.0 x 10-1      2.4 x 10\1\     2.4 x 10-7      6.4 x 10-6
K-42.............................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             2.2 x 10\5\     6.0 x 10\6\
K-43.............................  ....................  7.0 x 10-1       1.9 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.2 x 10\5\     3.3 x 10\6\
Kr-79............................  Krypton (36)........  4.0              1.1 x 10\2\     2.0             5.4 x 10\1\     4.2 x 10\4\     1.1 x 10\6\
Kr-81............................  ....................  4.0 x 10\1\      1.1 x 10\3\     4.0 x 10\1\     1.1 x 10\3\     7.8 x 10-\4\    2.1 x 10-\2\
Kr-85............................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10\1\     2.7 x 102       1.5 x 10\1\     3.9 x 102
Kr-85m...........................  ....................  8.0              2.2 x 102       3.0             8.1 x 10\1\     3.0 x 10\5\     8.2 x 10\6\
Kr-87............................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             1.0 x 10\6\     2.8 x 10\7\
La-137...........................  Lanthanum (57)......  3.0 x 10\1\      8.1 x 102       6.0             1.6 x 102       1.6 x 10-3      4.4 x 10-2
La-140...........................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     2.1 x 10\4\     5.6 x 10\5\
Lu-172...........................  Lutetium (71).......  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     4.2 x 103       1.1 x 10\5\
Lu-173...........................  ....................  8.0              2.2 x 102       8.0             2.2 x 102       5.6 x 10\1\     1.5 x 103
Lu-174...........................  ....................  9.0              2.4 x 102       9.0             2.4 x 102       2.3 x 10\1\     6.2 x 102
Lu-174m..........................  ....................  2.0 x 10\1\      5.4 x 102       1.0 x 10\1\     2.7 x 102       2.0 x 102       5.3 x 103
Lu-177...........................  ....................  3.0 x 10\1\      8.1 x 102       7.0 x 10-1      1.9 x 10\1\     4.1 x 103       1.1 x 10\5\
Mg-28 (a)........................  Magnesium (12)......  3.0 x 10-1       8.1             3.0 x 10-1      8.1             2.0 x 10\5\     5.4 x 10\6\
Mn-52............................  Manganese (25)......  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.6 x 10\4\     4.4 x 10\5\
Mn-53............................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       6.8 x 10-5      1.8 x 10-3
Mn-54............................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     2.9 x 102       7.7 x 103
Mn-56............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             8.0 x 10\5\     2.2 x 10\7\
Mo-93............................  Molybdenum (42).....  4.0 x 10\1\      1.1 x 103       2.0 x 10\1\     5.4 x 102       4.1 x 10-2      1.1
Mo-99 \a\ \h\....................  ....................  1.0              2.7 x 10\1\     6.0 x 10-\1\    1.6 x 10\1\     1.8 x 10\4\     4.8 x 10\5\
N-13.............................  Nitrogen (7)........  9.0 x 10-1       2.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     5.4 x 10\7\     1.5 x 10\9\
Na-22............................  Sodium (11).........  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     2.3 x 102       6.3 x 103
Na-24............................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             3.2 x 10\5\     8.7 x 10\6\
Nb-93m...........................  Niobium (41)........  4.0 x 10\1\      1.1 x 103       3.0 x 10\1\     8.1 x 102       8.8             2.4 x 102
Nb-94............................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     6.9 x 10-3      1.9 x 10-1
Nb-95............................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.5 x 103       3.9 x 10\4\
Nb-97............................  ....................  9.0 x 10-1       2.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     9.9 x 10\5\     2.7 x 10\7\
Nd-147...........................  Neodymium (60)......  6.0              1.6 x 102       6.0 x 10-1      1.6 x 10\1\     3.0 x 103       8.1 x 10\4\
Nd-149...........................  ....................  6.0 x 10-1       1.6 x 10\1\     5.0 x 10-1      1.4 x 10\1\     4.5 x 10\5\     1.2 x 10\7\
Ni-59............................  Nickel (28).........  Unlimited        Unlimited       Unlimited       Unlimited       3.0 x 10-3      8.0 x 10-2
Ni-63............................  ....................  4.0 x 10\1\      1.1 x 103       3.0 x 10\1\     8.1 x 102       2.1             5.7 x 10\1\

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Ni-65............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     7.1 x 10\5\     1.9 x 10\7\
Np-235...........................  Neptunium (93)......  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       5.2 x 10\1\     1.4 x 103
Np-236 (short-lived).............  ....................  2.0 x 10\1\      5.4 x 102       2.0             5.4 x 10\1\     4.7 x 10-4      1.3 x 10-2
Np-236 (long-lived)..............  ....................  9.0 x 10\0\      2.4 x 102       2.0 x 10-2      5.4 x 10-1      4.7 x 10-4      1.3 x 10-2
Np-237...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10-3      5.4 x 10-2      2.6 x 10-5      7.1 x 10-4
Np-239...........................  ....................  7.0              1.9 x 102       4.0 x 10-1      1.1 x 10\1\     8.6 x 103       2.3 x 10\5\
Os-185...........................  Osmium (76).........  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     2.8 x 102       7.5 x 103
Os-191...........................  ....................  1.0 x 10\1\      2.7 x 102       2.0             5.4 x 10\1\     1.6 x 103       4.4 x 10\4\
Os-191m..........................  ....................  4.0 x 10\1\      1.1 x 103       3.0 x 10\1\     8.1 x 102       4.6 x 10\4\     1.3 x 10\6\
Os-193...........................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.0 x 10\4\     5.3 x 10\5\
Os-194 (a).......................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.1 x 10\1\     3.1 x 102
P-32.............................  Phosphorus (15).....  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     1.1 x 10\4\     2.9 x 10\5\
P-33.............................  ....................  4.0 x 10\1\      1.1 x 103       1.0             2.7 x 10\1\     5.8 x 103       1.6 x 10\5\
Pa-230 (a).......................  Protactinium (91)...  2.0              5.4 x 10\1\     7.0 x 10-2      1.9             1.2 x 103       3.3 x 10\4\
Pa-231...........................  ....................  4.0              1.1 x 102       4.0 x 10-4      1.1 x 10-2      1.7 x 10-3      4.7 x 10-2
Pa-233...........................  ....................  5.0              1.4 x 102       7.0 x 10-1      1.9 x 10\1\     7.7 x 102       2.1 x 10\4\
Pb-201...........................  Lead (82)...........  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     6.2 x 10\4\     1.7 x 10\6\
Pb-202...........................  ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10\1\     5.4 x 102       1.2 x 10-4      3.4 x 10-3
Pb-203...........................  ....................  4.0              1.1 x 102       3.0             8.1 x 10\1\     1.1 x 10\4\     3.0 x 10\5\
Pb-205...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       4.5 x 10-6      1.2 x 10-4
Pb-210 (a).......................  ....................  1.0              2.7 x 10\1\     5.0 x 10-2      1.4             2.8             7.6 x 10\1\
Pb-212 (a).......................  ....................  7.0 x 10-1       1.9 x 10\1\     2.0 x 10-1      5.4             5.1 x 10\4\     1.4 x 10\6\
Pd-103 (a).......................  Palladium (46)......  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       2.8 x 103       7.5 x 10\4\
Pd-107...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       1.9 x 10-5      5.1 x 10-4
Pd-109...........................  ....................  2.0              5.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     7.9 x 10\4\     2.1 x 10\6\
Pm-143...........................  Promethium (61).....  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     1.3 x 102       3.4 x 103
Pm-144...........................  ....................  7.0 x 10-1       1.9 x 10\1\     7.0 x 10-1      1.9 x 10\1\     9.2 x 10\1\     2.5 x 103
Pm-145...........................  ....................  3.0 x 10\1\      8.1 x 102       1.0 x 10\1\     2.7 x 102       5.2             1.4 x 102
Pm-147...........................  ....................  4.0 x 10\1\      1.1 x 103       2.0             5.4 x 10\1\     3.4 x 10\1\     9.3 x 102
Pm-148m (a)......................  ....................  8.0 x 10-1       2.2 x 10\1\     7.0 x 10-1      1.9 x 10\1\     7.9 x 102       2.1 x 10\4\
Pm-149...........................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.5 x 10\4\     4.0 x 10\5\
Pm-151...........................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.7 x 10\4\     7.3 x 10\5\
Po-210...........................  Polonium (84).......  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      1.7 x 102       4.5 x 103
Pr-142...........................  Praseodymium (59)...  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     4.3 x 10\4\     1.2 x 10\6\
Pr-143...........................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.5 x 103       6.7 x 10\4\
Pt-188 (a).......................  Platinum (78).......  1.0              2.7 x 10\1\     8.0 x 10-1      2.2 x 10\1\     2.5 x 103       6.8 x 10\4\
Pt-191...........................  ....................  4.0              1.1 x 102       3.0             8.1 x 10\1\     8.7 x 103       2.4 x 10\5\
Pt-193...........................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       1.4             3.7 x 10\1\
Pt-193m..........................  ....................  4.0 x 10\1\      1.1 x 103       5.0 x 10-1      1.4 x 10\1\     5.8 x 103       1.6 x 10\5\
Pt-195m..........................  ....................  1.0 x 10\1\      2.7 x 102       5.0 x 10-1      1.4 x 10\1\     6.2 x 103       1.7 x 10\5\
Pt-197...........................  ....................  2.0 x 10\1\      5.4 x 102       6.0 x 10-1      1.6 x 10\1\     3.2 x 10\4\     8.7 x 10\5\
Pt-197m..........................  ....................  1.0 x 10\1\      2.7 x 102       6.0 x 10-1      1.6 x 10\1\     3.7 x 10\5\     1.0 x 10\7\
Pu-236...........................  Plutonium (94)......  3.0 x 10\1\      8.1 x 102       3.0 x 10-3      8.1 x 10-2      2.0 x 10\1\     5.3 x 102
Pu-237...........................  ....................  2.0 x 10\1\      5.4 x 102       2.0 x 10\1\     5.4 x 102       4.5 x 102       1.2 x 10\4\
Pu-238...........................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      6.3 x 10-1      1.7 x 10\1\
Pu-239...........................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      2.3 x 10-3      6.2 x 10-2
Pu-240...........................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      8.4 x 10-3      2.3 x 10-1
Pu-241 (a).......................  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-2      1.6             3.8             1.0 x 102
Pu-242...........................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      1.5 x 10-4      3.9 x 10-3
Pu-244 (a).......................  ....................  4.0 x 10-1       1.1 x 10\1\     1.0 x 10-3      2.7 x 10-2      6.7 x 10-7      1.8 x 10-5
Ra-223 (a).......................  Radium (88).........  4.0 x 10-1       1.1 x 10\1\     7.0 x 10-3      1.9 x 10-1      1.9 x 103       5.1 x 10\4\
Ra-224 (a).......................  ....................  4.0 x 10-1       1.1 x 10\1\     2.0 x 10-2      5.4 x 10-1      5.9 x 103       1.6 x 10\5\
Ra-225 (a).......................  ....................  2.0 x 10-1       5.4             4.0 x 10-3      1.1 x 10-1      1.5 x 103       3.9 x 10\4\
Ra-226 (a).......................  ....................  2.0 x 10-1       5.4             3.0 x 10-3      8.1 x 10-2      3.7 x 10-2      1.0
Ra-228 (a).......................  ....................  6.0 x 10-1       1.6 x 10\1\     2.0 x 10-2      5.4 x 10-1      1.0 x 10\1\     2.7 x 102
Rb-81............................  Rubidium (37).......  2.0              5.4 x 10\1\     8.0 x 10-1      2.2 x 10\1\     3.1 x 10\5\     8.4 x 10\6\
Rb-83 (a)........................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     6.8 x 102       1.8 x 10\4\
Rb-84............................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.8 x 103       4.7 x 10\4\
Rb-86............................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     3.0 x 103       8.1 x 10\4\
Rb-87............................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       3.2 x 10-9      8.6 x 10-8
Rb(nat)..........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       6.7 x 10\6\     1.8 x 10\8\
Re-184...........................  Rhenium (75)........  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     6.9 x 102       1.9 x 10\4\
Re-184m..........................  ....................  3.0              8.1 x 10\1\     1.0             2.7 x 10\1\     1.6 x 102       4.3 x 103
Re-186...........................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     6.9 x 103       1.9 x 10\5\
Re-187...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       1.4 x 10-9      3.8 x 10-8
Re-188...........................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     3.6 x 10\4\     9.8 x 10\5\
Re-189 (a).......................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.5 x 10\4\     6.8 x 10\5\
Re(nat)..........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       0.0             2.4 x 10-8
Rh-99............................  Rhodium (45)........  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     3.0 x 103       8.2 x 10\4\
Rh-101...........................  ....................  4.0              1.1 x 102       3.0             8.1 x 10\1\     4.1 x 10\1\     1.1 x 103

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Rh-102...........................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     4.5 x 10\1\     1.2 x 103
Rh-102m..........................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     2.3 x 102       6.2 x 103
Rh-103m..........................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       1.2 x 10\6\     3.3 x 10\7\
Rh-105...........................  ....................  1.0 x 10\1\      2.7 x 102       8.0 x 10-1      2.2 x 10\1\     3.1 x 10\4\     8.4 x 10\5\
Rn-222 (a).......................  Radon (86)..........  3.0 x 10-1       8.1             4.0 x 10-3      1.1 x 10-1      5.7 x 103       1.5 x 10\5\
Ru-97............................  Ruthenium (44)......  5.0              1.4 x 102       5.0             1.4 x 102       1.7 x 10\4\     4.6 x 10\5\
Ru-103 (a).......................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     1.2 x 103       3.2 x 10\4\
Ru-105...........................  ....................  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.5 x 10\5\     6.7 x 10\6\
Ru-106 (a).......................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             1.2 x 102       3.3 x 103
S-35.............................  Sulphur (16)........  4.0 x 10\1\      1.1 x 103       3.0             8.1 x 10\1\     1.6 x 103       4.3 x 10\4\
Sb-122...........................  Antimony (51).......  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.5 x 10\4\     4.0 x 10\5\
Sb-124...........................  ....................  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     6.5 x 102       1.7 x 10\4\
Sb-125...........................  ....................  2.0              5.4 x 10\1\     1.0             2.7 x 10\1\     3.9 x 10\1\     1.0 x 103
Sb-126...........................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     3.1 x 103       8.4 x 10\4\
Sc-44............................  Scandium (21).......  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     6.7 x 10\5\     1.8 x 10\7\
Sc-46............................  ....................  5.0 x 10-1       1.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     1.3 x 103       3.4 x 10\4\
Sc-47............................  ....................  1.0 x 10\1\      2.7 x 102       7.0 x 10-1      1.9 x 10\1\     3.1 x 10\4\     8.3 x 10\5\
Sc-48............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             5.5 x 10\4\     1.5 x 10\6\
Se-75............................  Selenium (34).......  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     5.4 x 102       1.5 x 10\4\
Se-79............................  ....................  4.0 x 10\1\      1.1 x 103       2.0             5.4 x 10\1\     2.6 x 10-3      7.0 x 10-2
Si-31............................  Silicon (14)........  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.4 x 10\6\     3.9 x 10\7\
Si-32............................  ....................  4.0 x 10\1\      1.1 x 103       5.0 x 10-1      1.4 x 10\1\     3.9             1.1 x 102
Sm-145...........................  Samarium (62).......  1.0 x 10\1\      2.7 x 102       1.0 x 10\1\     2.7 x 102       9.8 x 10\1\     2.6 x 103
Sm-147...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       8.5 x 10-1      2.3 x 10-8
Sm-151...........................  ....................  4.0 x 10\1\      1.1 x 103       1.0 x 10\1\     2.7 x 102       9.7 x 10-1      2.6 x 10\1\
Sm-153...........................  ....................  9.0              2.4 x 102       6.0 x 10-1      1.6 x 10\1\     1.6 x 10\4\     4.4 x 10\5\
Sn-113 (a).......................  Tin (50)............  4.0              1.1 x 102       2.0             5.4 x 10\1\     3.7 x 102       1.0 x 10\4\
Sn-117m..........................  ....................  7.0              1.9 x 102       4.0 x 10-1      1.1 x 10\1\     3.0 x 103       8.2 x 10\4\
Sn-119m..........................  ....................  4.0 x 10\1\      1.1 x 103       3.0 x 10\1\     8.1 x 102       1.4 x 102       3.7 x 103
Sn-121m (a)......................  ....................  4.0 x 10\1\      1.1 x 103       9.0 x 10-1      2.4 x 10\1\     2.0             5.4 x 10\1\
Sn-123...........................  ....................  8.0 x 10-1       2.2 x 10\1\     6.0 x 10-1      1.6 x 10\1\     3.0 x 102       8.2 x 103
Sn-125...........................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     4.0 x 103       1.1 x 10\5\
Sn-126 (a).......................  ....................  6.0 x 10-1       1.6 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.0 x 10-3      2.8 x 10-2
Sr-82 (a)........................  Strontium (38)......  2.0 x 10-1       5.4             2.0 x 10-1      5.4             2.3 x 103       6.2 x 10\4\
Sr-85............................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     8.8 x 102       2.4 x 10\4\
Sr-85m...........................  ....................  5.0              1.4 x 102       5.0             1.4 x 102       1.2 x 10\6\     3.3 x 10\7\
Sr-87m...........................  ....................  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     4.8 x 10\5\     1.3 x 10\7\
Sr-89............................  ....................  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.1 x 103       2.9 x 10\4\
Sr-90 (a)........................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             5.1             1.4 x 102
Sr-91 (a)........................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.3 x 10\5\     3.6 x 10\6\
Sr-92 (a)........................  ....................  1.0              2.7 x 10\1\     3.0 x 10-1      8.1             4.7 x 10\5\     1.3 x 10\7\
T(H-3)...........................  Tritium (1).........  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       3.6 x 102       9.7 x 103
Ta-178 (long-lived)..............  Tantalum (73).......  1.0              2.7 x 10\1\     8.0 x 10-1      2.2 x 10\1\     4.2 x 10\6\     1.1 x 10\8\
Ta-179...........................  ....................  3.0 x 10\1\      8.1 x 102       3.0 x 10\1\     8.1 x 102       4.1 x 10\1\     1.1 x 103
Ta-182...........................  ....................  9.0 x 10-1       2.4 x 10\1\     5.0 x 10-1      1.4 x 10\1\     2.3 x 102       6.2 x 103
Tb-157...........................  Terbium (65)........  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       5.6 x 10-1      1.5 x 10\1\
Tb-158...........................  ....................  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     5.6 x 10-1      1.5 x 10\1\
Tb-160...........................  ....................  1.0              2.7 x 10\1\     6.0 x 10-1      1.6 x 10\1\     4.2 x 102       1.1 x 10\4\
Tc-95m (a).......................  Technetium (43).....  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     8.3 x 102       2.2 x 10\4\
Tc-96............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.2 x 10\4\     3.2 x 10\5\
Tc-96m (a).......................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.4 x 10\6\     3.8 x 10\7\
Tc-97............................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       5.2 x 10-5      1.4 x 10-3
Tc-97m...........................  ....................  4.0 x 10\1\      1.1 x 103       1.0             2.7 x 10\1\     5.6 x 102       1.5 x 10\4\
Tc-98............................  ....................  8.0 x 10-1       2.2 x 10\1\     7.0 x 10-1      1.9 x 10\1\     3.2 x 10-5      8.7 x 10-4
Tc-99............................  ....................  4.0 x 10\1\      1.1 x 103       9.0 x 10-1      2.4 x 10\1\     6.3 x 10-4      1.7 x 10-2
Tc-99m...........................  ....................  1.0 x 10\1\      2.7 x 102       4.0             1.1 x 102       1.9 x 10\5\     5.3 x 10\6\
Te-121...........................  Tellurium (52)......  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     2.4 x 103       6.4 x 10\4\
Te-121m..........................  ....................  5.0              1.4 x 102       3.0             8.1 x 10\1\     2.6 x 102       7.0 x 103
Te-123m..........................  ....................  8.0              2.2 x 102       1.0             2.7 x 10\1\     3.3 x 102       8.9 x 103
Te-125m..........................  ....................  2.0 x 10\1\      5.4 x 102       9.0 x 10-1      2.4 x 10\1\     6.7 x 102       1.8 x 10\4\
Te-127...........................  ....................  2.0 x 10\1\      5.4 x 102       7.0 x 10-1      1.9 x 10\1\     9.8 x 10\4\     2.6 x 10\6\
Te-127m (a)......................  ....................  2.0 x 10\1\      5.4 x 102       5.0 x 10-1      1.4 x 10\1\     3.5 x 102       9.4 x 103
Te-129...........................  ....................  7.0 x 10-1       1.9 x 10\1\     6.0 x 10-1      1.6 x 10\1\     7.7 x 10\5\     2.1 x 10\7\
Te-129m (a)......................  ....................  8.0 x 10-1       2.2 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.1 x 103       3.0 x 10\4\
Te-131m (a)......................  ....................  7.0 x 10-1       1.9 x 10\1\     5.0 x 10-1      1.4 x 10\1\     3.0 x 10\4\     8.0 x 10\5\
Te-132 (a).......................  ....................  5.0 x 10-1       1.4 x 10\1\     4.0 x 10-1      1.1 x 10\1\     1.1 x 10\4\     3.0 x 10\5\
Th-227...........................  Thorium (90)........  1.0 x 10\1\      2.7 x 102       5.0 x 10-3      1.4 x 10-1      1.1 x 103       3.1 x 10\4\
Th-228 (a).......................  ....................  5.0 x 10-1       1.4 x 10\1\     1.0 x 10-3      2.7 x 10-2      3.0 x 10\1\     8.2 x 102
Th-229...........................  ....................  5.0              1.4 x 102       5.0 x 10-4      1.4 x 10-2      7.9 x 10-3      2.1 x 10-1
Th-230...........................  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      7.6 x 10-4      2.1 x 10-2

[[Page 385]]

 
Th-231...........................  ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      2.0 x 10\4\     5.3 x 10\5\
Th-232...........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       4.0 x 10-9      1.1 x 10-7
Th-234 (a).......................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             8.6 x 102       2.3 x 10\4\
Th(nat)..........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       8.1 x 10-9      2.2 x 10-7
Ti-44 (a)........................  Titanium (22).......  5.0 x 10-1       1.4 x 10\1\     4.0 x 10-1      1.1 x 10\1\     6.4             1.7 x 102
Tl-200...........................  Thallium (81).......  9.0 x 10-1       2.4 x 10\1\     9.0 x 10-1      2.4 x 10\1\     2.2 x 10\4\     6.0 x 10\5\
Tl-201...........................  ....................  1.0 x 10\1\      2.7 x 102       4.0             1.1 x 102       7.9 x 103       2.1 x 10\5\
Tl-202...........................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     2.0 x 103       5.3 x 10\4\
Tl-204...........................  ....................  1.0 x 10\1\      2.7 x 102       7.0 x 10-1      1.9 x 10\1\     1.7 x 10\1\     4.6 x 102
Tm-167...........................  Thulium (69)........  7.0              1.9 x 102       8.0 x 10-1      2.2 x 10\1\     3.1 x 103       8.5 x 10\4\
Tm-170...........................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.2 x 102       6.0 x 103
Tm-171...........................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       4.0 x 10\1\     1.1 x 103
U-230 (fast lung absorption)       Uranium (92)........  4.0 x 10\1\      1.1 x 103       1.0 x 10-1      2.7             1.0 x 103       2.7 x 10\4\
 (a)(d).
U-230 (medium lung absorption)     ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10-3      1.1 x 10-1      1.0 x 103       2.7 x 10\4\
 (a)(e).
U-230 (slow lung absorption)       ....................  3.0 x 10\1\      8.1 x 102       3.0 x 10-3      8.1 x 10-2      1.0 x 103       2.7 x 10\4\
 (a)(f).
U-232 (fast lung absorption) (d).  ....................  4.0 x 10\1\      1.1 x 103       1.0 x 10-2      2.7 x 10-1      8.3 x 10-1      2.2 x 10\1\
U-232 (medium lung absorption)     ....................  4.0 x 10\1\      1.1 x 103       7.0 x 10-3      1.9 x 10-1      8.3 x 10-1      2.2 x 10\1\
 (e).
U-232 (slow lung absorption) (f).  ....................  1.0 x 10\1\      2.7 x 102       1.0 x 10-3      2.7 x 10-2      8.3 x 10-1      2.2 x 10\1\
U-233 (fast lung absorption) (d).  ....................  4.0 x 10\1\      1.1 x 103       9.0 x 10-2      2.4             3.6 x 10-4      9.7 x 10-3
U-233 (medium lung absorption)     ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      3.6 x 10-4      9.7 x 10-3
 (e).
U-233 (slow lung absorption) (f).  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-3      1.6 x 10-1      3.6 x 10-4      9.7 x 10-3
U-234 (fast lung absorption) (d).  ....................  4.0 x 10\1\      1.1 x 103       9.0 x 10-2      2.4             2.3 x 10-4      6.2 x 10-3
U-234 (medium lung absorption)     ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      2.3 x 10-4      6.2 x 10-3
 (e).
U-234 (slow lung absorption) (f).  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-3      1.6 x 10-1      2.3 x 10-4      6.2 x 10-3
U-235 (all lung absorption types)  ....................  Unlimited        Unlimited       Unlimited       Unlimited       8.0 x 10-8      2.2 x 10-6
 (a),(d),(e),(f).
U-236 (fast lung absorption) (d).  ....................  Unlimited        Unlimited       Unlimited       Unlimited       2.4 x 10-6      6.5 x 10-5
U-236 (medium lung absorption)     ....................  4.0 x 10\1\      1.1 x 103       2.0 x 10-2      5.4 x 10-1      2.4 x 10-6      6.5 x 10-5
 (e).
U-236 (slow lung absorption) (f).  ....................  4.0 x 10\1\      1.1 x 103       6.0 x 10-3      1.6 x 10-1      2.4 x 10-6      6.5 x 10-5
U-238 (all lung absorption types)  ....................  Unlimited        Unlimited       Unlimited       Unlimited       1.2 x 10-8      3.4 x 10-7
 (d),(e),(f).
U (nat)..........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       2.6 x 10-8      7.1 x 10-7
U (enriched to 20% or less)(g)...  ....................  Unlimited        Unlimited       Unlimited       Unlimited       See Table A-4   See Table A-4
U (dep)..........................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       See Table A-4   See Table A-4
V-48.............................  Vanadium (23).......  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     6.3 x 103       1.7 x 10\5\
V-49.............................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       3.0 x 102       8.1 x 103
W-178 (a)........................  Tungsten (74).......  9.0              2.4 x 102       5.0             1.4 x 102       1.3 x 103       3.4 x 10\4\
W-181............................  ....................  3.0 x 10\1\      8.1 x 102       3.0 x 10\1\     8.1 x 102       2.2 x 102       6.0 x 103
W-185............................  ....................  4.0 x 10\1\      1.1 x 103       8.0 x 10-1      2.2 x 10\1\     3.5 x 102       9.4 x 103
W-187............................  ....................  2.0              5.4 x 10\1\     6.0 x 10-1      1.6 x 10\1\     2.6 x 10\4\     7.0 x 10\5\
W-188 (a)........................  ....................  4.0 x 10-1       1.1 x 10\1\     3.0 x 10-1      8.1             3.7 x 102       1.0 x 10\4\
Xe-122 (a).......................  Xenon (54)..........  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     4.8 x 10\4\     1.3 x 10\6\
Xe-123...........................  ....................  2.0              5.4 x 10\1\     7.0 x 10-1      1.9 x 10\1\     4.4 x 10\5\     1.2 x 10\7\
Xe-127...........................  ....................  4.0              1.1 x 102       2.0             5.4 x 10\1\     1.0 x 103       2.8 x 10\4\
Xe-131m..........................  ....................  4.0 x 10\1\      1.1 x 103       4.0 x 10\1\     1.1 x 103       3.1 x 103       8.4 x 10\4\
Xe-133...........................  ....................  2.0 x 10\1\      5.4 x 102       1.0 x 10\1\     2.7 x 102       6.9 x 103       1.9 x 10\5\
Xe-135...........................  ....................  3.0              8.1 x 10\1\     2.0             5.4 x 10\1\     9.5 x 10\4\     2.6 x 10\6\
Y-87 (a).........................  Yttrium (39)........  1.0              2.7 x 10\1\     1.0             2.7 x 10\1\     1.7 x 10\4\     4.5 x 10\5\
Y-88.............................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     5.2 x 102       1.4 x 10\4\
Y-90.............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             2.0 x 10\4\     5.4 x 10\5\
Y-91.............................  ....................  6.0 x 10-1       1.6 x 10\1\     6.0 x 10-1      1.6 x 10\1\     9.1 x 102       2.5 x 10\4\
Y-91m............................  ....................  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     1.5 x 10\6\     4.2 x 10\7\

[[Page 386]]

 
Y-92.............................  ....................  2.0 x 10-1       5.4             2.0 x 10-1      5.4             3.6 x 10\5\     9.6 x 10\6\
Y-93.............................  ....................  3.0 x 10-1       8.1             3.0 x 10-1      8.1             1.2 x 10\5\     3.3 x 10\6\
Yb-169...........................  Ytterbium (70)......  4.0              1.1 x 102       1.0             2.7 x 10\1\     8.9 x 102       2.4 x 10\4\
Yb-175...........................  ....................  3.0 x 10\1\      8.1 x 102       9.0 x 10-1      2.4 x 10\1\     6.6 x 103       1.8 x 10\5\
Zn-65............................  Zinc (30)...........  2.0              5.4 x 10\1\     2.0             5.4 x 10\1\     3.0 x 102       8.2 x 103
Zn-69............................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.8 x 10\6\     4.9 x 10\7\
Zn-69m (a).......................  ....................  3.0              8.1 x 10\1\     6.0 x 10-1      1.6 x 10\1\     1.2 x 10\5\     3.3 x 10\6\
Zr-88............................  Zirconium (40)......  3.0              8.1 x 10\1\     3.0             8.1 x 10\1\     6.6 x 102       1.8 x 10\4\
Zr-93............................  ....................  Unlimited        Unlimited       Unlimited       Unlimited       9.3 x 10-5      2.5 x 10-3
Zr-95 (a)........................  ....................  2.0              5.4 x 10\1\     8.0 x 10-1      2.2 x 10\1\     7.9 x 102       2.1 x 10\4\
Zr-97 (a)........................  ....................  4.0 x 10-1       1.1 x 10\1\     4.0 x 10-1      1.1 x 10\1\     7.1 x 10\4\     1.9 x 10\6\
--------------------------------------------------------------------------------------------------------------------------------------------------------
\a\ A1 and/or A2 values include contributions from daughter nuclides with half-lives less than 10 days, as listed in the following:


Mg-28                    Al-28
Ca-47                    Sc-47
Ti-44                    Sc-44
Fe-52                    Mn-52m
Fe-60                    Co-60m
Zn-69m                   Zn-69
Ge-68                    Ga-68
Rb-83                    Kr-83m
Sr-82                    Rb-82
Sr-90                    Y-90
Sr-91                    Y-91m
Sr-92                    Y-92
Y-87                     Sr-87m
Zr-95                    Nb-95m
Zr-97                    Nb-97m, Nb-97
Mo-99                    Tc-99m
Tc-95m                   Tc-95
Tc-96m                   Tc-96
Ru-103                   Rh-103m
Ru-106                   Rh-106
Pd-103                   Rh-103m
Ag-108m                  Ag-108
Ag-110m                  Ag-110
Cd-115                   In-115m
In-114m                  In-114
Sn-113                   In-113m
Sn-121m                  Sn-121
Sn-126                   Sb-126m
Te-127m                  Te-127
Te-129m                  Te-129
Te-131m                  Te-131
Te-132                   I-132
I-135                    Xe-135m
Xe-122                   I-122
Cs-137                   Ba-137m
Ba-131                   Cs-131
Ba-140                   La-140
Ce-144                   Pr-144m, Pr-144
Pm-148m                  Pm-148
Gd-146                   Eu-146
Dy-166                   Ho-166
Hf-172                   Lu-172
W-178                    Ta-178
W-188                    Re-188
Re-189                   Os-189m

[[Page 387]]

 
Os-194                   Ir-194
Ir-189                   Os-189m
Pt-188                   Ir-188
Hg-194                   Au-194
Hg-195m                  Hg-195
Pb-210                   Bi-210
Pb-212                   Bi-212, Tl-208, Po-212
Bi-210m                  Tl-206
Bi-212                   Tl-208, Po-212
At-211                   Po-211
Rn-222                   Po-218, Pb-214, At-218, Bi-214, Po-214
Ra-223                   Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207
Ra-224                   Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
Ra-225                   Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213,
                          Pb-209
Ra-226                   Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214
Ra-228                   Ac-228
Ac-225                   Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209
Ac-227                   Fr-223
Th-228                   Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208,
                          Po-212
Th-234                   Pa-234m, Pa-234
Pa-230                   Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214
U-230                    Th-226, Ra-222, Rn-218, Po-214
U-235                    Th-231
Pu-241                   U-237
Pu-244                   U-240, Np-240m
Am-242m                  Am-242, Np-238
Am-243                   Np-239
Cm-247                   Pu-243
Bk-249                   Am-245
Cf-253                   Cm-249
 
\b\ The values of A1 and A2 in Curies (Ci) are approximate and for
  information only; the regulatory standard units are Terabecquerels
  (TBq) (see Appendix A to Part 71--Determination of A1 and A2, Section
  I).
\c\ The activity of Ir-192 in special form may be determined from a
  measurement of the rate of decay or a measurement of the radiation
  level at a prescribed distance from the source.
\d\ These values apply only to compounds of uranium that take the
  chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident
  conditions of transport.
\e\ These values apply only to compounds of uranium that take the
  chemical form of UO3, UF4, UCl4 and hexavalent compounds in both
  normal and accident conditions of transport.
\f\ These values apply to all compounds of uranium other than those
  specified in notes (d) and (e) of this table.
\g\ These values apply to unirradiated uranium only.
\h\ A2 = 0.74 TBq (20 Ci) for Mo-99 for domestic use.


                       Table A-2--Exempt Material Activity Concentrations and Exempt Consignment Activity Limits for Radionuclides
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                                           Activity concentration  Activity concentration    Activity limit for      Activity limit for
      Symbol of radionuclide          Element and atomic     for exempt material     for exempt material     exempt consignment      exempt consignment
                                            number                 (Bq/g)                  (Ci/g)                   (Bq)                    (Ci)
--------------------------------------------------------------------------------------------------------------------------------------------------------
Ac-225............................  Actinium (89)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Ac-227............................  .....................  1.0 x 10-1              2.7 x 10-12             1.0 x 103               2.7 x 10-8
Ac-228............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ag-105............................  Silver (47)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ag-108m (b).......................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ag-110m...........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ag-111............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Al-26.............................  Aluminum (13)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Am-241............................  Americium (95).......  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Am-242m (b).......................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Am-243 (b)........................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Ar-37.............................  Argon (18)...........  1.0 x 10\6\             2.7 x 10-5              1.0 x 10\8\             2.7 x 10-3
Ar-39.............................  .....................  1.0 x 10\7\             2.7 x 10-4              1.0 x 10\4\             2.7 x 10-7
Ar-41.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\9\             2.7 x 10-2
As-72.............................  Arsenic (33).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
As-73.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
As-74.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
As-76.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
As-77.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5

[[Page 388]]

 
At-211............................  Astatine (85)........  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Au-193............................  Gold (79)............  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Au-194............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Au-195............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Au-198............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Au-199............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ba-131............................  Barium (56)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ba-133............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ba-133m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ba-140 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Be-7..............................  Beryllium (4)........  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Be-10.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Bi-205............................  Bismuth (83).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Bi-206............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Bi-207............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Bi-210............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Bi-210m...........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Bi-212 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Bk-247............................  Berkelium (97).......  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Bk-249............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Br-76.............................  Bromine (35).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Br-77.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Br-82.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
C-11..............................  Carbon (6)...........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
C-14..............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Ca-41.............................  Calcium (20).........  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\7\             2.7 x 10-4
Ca-45.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Ca-47.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Cd-109............................  Cadmium (48).........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Cd-113m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Cd-115............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Cd-115m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Ce-139............................  Cerium (58)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ce-141............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Ce-143............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ce-144 (b)........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Cf-248............................  Californium (98).....  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cf-249............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Cf-250............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cf-251............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Cf-252............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cf-253............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Cf-254............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Cl-36.............................  Chlorine (17)........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Cl-38.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Cm-240............................  Curium (96)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Cm-241............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Cm-242............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Cm-243............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Cm-244............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cm-245............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Cm-246............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Cm-247............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Cm-248............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Co-55.............................  Cobalt (27)..........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Co-56.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Co-57.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Co-58.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Co-58m............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Co-60.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Cr-51.............................  Chromium (24)........  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Cs-129............................  Cesium (55)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Cs-131............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Cs-132............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Cs-134............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cs-134m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
Cs-135............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Cs-136............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6

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Cs-137 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Cu-64.............................  Copper (29)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Cu-67.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Dy-159............................  Dysprosium (66)......  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Dy-165............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Dy-166............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Er-169............................  Erbium (68)..........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Er-171............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Eu-147............................  Europium (63)........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Eu-148............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Eu-149............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Eu-150 (short lived)..............  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Eu-150 (long lived)...............  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Eu-152............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Eu-152m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Eu-154............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Eu-155............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Eu-156............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
F-18..............................  Fluorine (9).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Fe-52.............................  Iron (26)............  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Fe-55.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Fe-59.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Fe-60.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Ga-67.............................  Gallium (31).........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ga-68.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Ga-72.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Gd-146............................  Gadolinium (64)......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Gd-148............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Gd-153............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Gd-159............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Ge-68.............................  Germanium (32).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Ge-71.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\8\             2.7 x 10-3
Ge-77.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Hf-172............................  Hafnium (72).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Hf-175............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Hf-181............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Hf-182............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Hg-194............................  Mercury (80).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Hg-195m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Hg-197............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Hg-197m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Hg-203............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Ho-166............................  Holmium (67).........  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
Ho-166m...........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
I-123.............................  Iodine (53)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
I-124.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
I-125.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
I-126.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
I-129.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
I-131.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
I-132.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
I-133.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
I-134.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
I-135.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
In-111............................  Indium (49)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
In-113m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
In-114m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
In-115m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ir-189............................  Iridium (77).........  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Ir-190............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ir-192............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Ir-194............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
K-40..............................  Potassium (19).......  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
K-42..............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
K-43..............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Kr-79.............................  Krypton (36).........  1.0 x 10\3\             2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6

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Kr-81.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Kr-85.............................  .....................  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\4\             2.7 x 10-7
Kr-85m............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\10\            2.7 x 10-1
Kr-87.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\9\             2.7 x 10-2
La-137............................  Lanthanum (57).......  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
La-140............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Lu-172............................  Lutetium (71)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Lu-173............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Lu-174............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Lu-174m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Lu-177............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Mg-28.............................  Magnesium (12).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Mn-52.............................  Manganese (25).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Mn-53.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\9\             2.7 x 10-2
Mn-54.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Mn-56.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Mo-93.............................  Molybdenum (42)......  1.0 x 103               2.7 x 10-8              1.0 x 10\8\             2.7 x 10-3
Mo-99.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
N-13..............................  Nitrogen (7).........  1.0 x 102               2.7 x 10-9              1.0 x 10\9\             2.7 x 10-2
Na-22.............................  Sodium (11)..........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Na-24.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Nb-93m............................  Niobium (41).........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Nb-94.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Nb-95.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Nb-97.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Nd-147............................  Neodymium (60).......  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Nd-149............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ni-59.............................  Nickel (28)..........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\8\             2.7 x 10-3
Ni-63.............................  .....................  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\8\             2.7 x 10-3
Ni-65.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Np-235............................  Neptunium (93).......  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Np-236 (short-lived)..............  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Np-236 (long-lived)...............  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Np-237 (b)........................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Np-239............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Os-185............................  Osmium (76)..........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Os-191............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Os-191m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Os-193............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Os-194............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
P-32..............................  Phosphorus (15)......  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
P-33..............................  .....................  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\8\             2.7 x 10-3
Pa-230............................  Protactinium (91)....  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Pa-231............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Pa-233............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Pb-201............................  Lead (82)............  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Pb-202............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Pb-203............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Pb-205............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Pb-210 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Pb-212 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Pd-103............................  Palladium (46).......  1.0 x 103               2.7 x 10-8              1.0 x 10\8\             2.7 x 10-3
Pd-107............................  .....................  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\8\             2.7 x 10-3
Pd-109............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Pm-143............................  Promethium (61)......  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Pm-144............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Pm-145............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Pm-147............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Pm-148m...........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Pm-149............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Pm-151............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Po-210............................  Polonium (84)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Pr-142............................  Praseodymium (59)....  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Pr-143............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Pt-188............................  Platinum (78)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Pt-191............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5

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Pt-193............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Pt-193m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Pt-195m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Pt-197............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Pt-197m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Pu-236............................  Plutonium (94).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Pu-237............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Pu-238............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Pu-239............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Pu-240............................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Pu-241............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Pu-242............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Pu-244............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Ra-223 (b)........................  Radium (88)..........  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Ra-224 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Ra-225............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Ra-226 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Ra-228 (b)........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Rb-81.............................  Rubidium (37)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Rb-83.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Rb-84.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Rb-86.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Rb-87.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Rb(nat)...........................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Re-184............................  Rhenium (75).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Re-184m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Re-186............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Re-187............................  .....................  1.0 x 10\6\             2.7 x 10-5              1.0 x 10\9\             2.7 x 10-2
Re-188............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Re-189............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Re(nat)...........................  .....................  1.0 x 10\6\             2.7 x 10-5              1.0 x 10\9\             2.7 x 10-2
Rh-99.............................  Rhodium (45).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Rh-101............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Rh-102............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Rh-102m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Rh-103m...........................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\8\             2.7 x 10-3
Rh-105............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Rn-222 (b)........................  Radon (86)...........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\8\             2.7 x 10-3
Ru-97.............................  Ruthenium (44).......  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Ru-103............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Ru-105............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ru-106 (b)........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
S-35..............................  Sulphur (16).........  1.0 x 10\5\             2.7 x 10-6              1.0 x 10\8\             2.7 x 10-3
Sb-122............................  Antimony (51)........  1.0 x 102               2.7 x 10-9              1.0 x 10\4\             2.7 x 10-7
Sb-124............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Sb-125............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Sb-126............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Sc-44.............................  Scandium (21)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Sc-46.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Sc-47.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Sc-48.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Se-75.............................  Selenium (34)........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Se-79.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Si-31.............................  Silicon (14).........  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Si-32.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Sm-145............................  Samarium (62)........  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Sm-147............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Sm-151............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\8\             2.7 x 10-3
Sm-153............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Sn-113............................  Tin (50).............  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Sn-117m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Sn-119m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Sn-121m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Sn-123............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Sn-125............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Sn-126............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Sr-82.............................  Strontium (38).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Sr-85.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5

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Sr-85m............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Sr-87m............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Sr-89.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Sr-90 (b).........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\4\             2.7 x 10-7
Sr-91.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Sr-92.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
T(H-3)............................  Tritium (1)..........  1.0 x 10\6\             2.7 x 10-5              1.0 x 10\9\             2.7 x 10-2
Ta-178 (long-lived)...............  Tantalum (73)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Ta-179............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Ta-182............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Tb-157............................  Terbium (65).........  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Tb-158............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tb-160............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tc-95m............................  Technetium (43)......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tc-96.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tc-96m............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Tc-97.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\8\             2.7 x 10-3
Tc-97m............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Tc-98.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tc-99.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
Tc-99m............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Te-121............................  Tellurium (52).......  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Te-121m...........................  .....................  1.0 x 10\2\             2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Te-123m...........................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Te-125m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Te-127............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Te-127m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Te-129............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Te-129m...........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Te-131m...........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Te-132............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Th-227............................  Thorium (90).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Th-228 (b)........................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Th-229 (b)........................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Th-230............................  .....................  1.0                     2.7 x 10-11             1.0 x 10\4\             2.7 x 10-7
Th-231............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Th-232............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
Th-234 (b)........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
Th (nat) (b)......................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
Ti-44.............................  Titanium (22)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
Tl-200............................  Thallium (81)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Tl-201............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Tl-202............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Tl-204............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\4\             2.7 x 10-7
Tm-167............................  Thulium (69).........  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Tm-170............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Tm-171............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\8\             2.7 x 10-3
U-230 (fast lung absorption)        Uranium (92).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
 (b),(d).
U-230 (medium lung absorption) (e)  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-230 (slow lung absorption) (f)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-232 (fast lung absorption)        .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
 (b),(d).
U-232 (medium lung absorption) (e)  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-232 (slow lung absorption) (f)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-233 (fast lung absorption) (d)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7

[[Page 393]]

 
U-233 (medium lung absorption) (e)  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
U-233 (slow lung absorption) (f)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
U-234 (fast lung absorption) (d)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-234 (medium lung absorption) (e)  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
U-234 (slow lung absorption) (f)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
U-235 (all lung absorption types)   .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
 (b),(d),(e),(f).
U-236 (fast lung absorption) (d)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-236 (medium lung absorption) (e)  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
U-236 (slow lung absorption) (f)..  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
U-238 (all lung absorption types)   .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\4\             2.7 x 10-7
 (b),(d),(e),(f).
U (nat) (b).......................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
U (enriched to 20% or less)(g)....  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
U (dep)...........................  .....................  1.0                     2.7 x 10-11             1.0 x 103               2.7 x 10-8
V-48..............................  Vanadium (23)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
V-49..............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
W-178.............................  Tungsten (74)........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
W-181.............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
W-185.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\7\             2.7 x 10-4
W-187.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
W-188.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Xe-122............................  Xenon (54)...........  1.0 x 102               2.7 x 10-9              1.0 x 10\9\             2.7 x 10-2
Xe-123............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\9\             2.7 x 10-2
Xe-127............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
Xe-131m...........................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\4\             2.7 x 10-7
Xe-133............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\4\             2.7 x 10-7
Xe-135............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\10\            2.7 x 10-1
Y-87..............................  Yttrium (39).........  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Y-88..............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Y-90..............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\5\             2.7 x 10-6
Y-91..............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\6\             2.7 x 10-5
Y-91m.............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Y-92..............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Y-93..............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\5\             2.7 x 10-6
Yb-169............................  Ytterbium (70).......  1.0 x 102               2.7 x 10-9              1.0 x 10\7\             2.7 x 10-4
Yb-175............................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Zn-65.............................  Zinc (30)............  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Zn-69.............................  .....................  1.0 x 10\4\             2.7 x 10-7              1.0 x 10\6\             2.7 x 10-5
Zn-69m............................  .....................  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Zr-88.............................  Zirconium (40).......  1.0 x 102               2.7 x 10-9              1.0 x 10\6\             2.7 x 10-5
Zr-93 (b).........................  .....................  1.0 x 103               2.7 x 10-8              1.0 x 10\7\             2.7 x 10-4
Zr-95.............................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\6\             2.7 x 10-5
Zr-97 (b).........................  .....................  1.0 x 10\1\             2.7 x 10-10             1.0 x 10\5\             2.7 x 10-6
--------------------------------------------------------------------------------------------------------------------------------------------------------
\a\ [Reserved]
\b\ Parent nuclides and their progeny included in secular equilibrium are listed as follows:


[[Page 394]]


Sr-90                    Y-90
Zr-93                    Nb-93m
Zr-97                    Nb-97
Ru-106                   Rh-106
Ag-108m                  Ag-108
Cs-137                   Ba-137m
Ce-144                   Pr-144
Ba-140                   La-140
Bi-212                   Tl-208 (0.36), Po-212 (0.64)
Pb-210                   Bi-210, Po-210
Pb-212                   Bi-212, Tl-208 (0.36), Po-212 (0.64)
Rn-222                   Po-218, Pb-214, Bi-214, Po-214
Ra-223                   Rn-219, Po-215, Pb-211, Bi-211, Tl-207
Ra-224                   Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36),
                          Po-212 (0.64)
Ra-226                   Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210,
                          Bi-210, Po-210
Ra-228                   Ac-228
Th-228                   Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208
                          (0.36), Po-212(0.64)
Th-229                   Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213,
                          Pb-209
Th-nat                   Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216,
                          Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Th-234                   Pa-234m
U-230                    Th-226, Ra-222, Rn-218, Po-214
U-232                    Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212,
                          Tl-208 (0.36), Po-212 (0.64)
U-235                    Th-231
U-238                    Th-234, Pa-234m
U-nat                    Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222,
                          Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-
                          210, Po-210
Np-237                   Pa-233
Am-242m                  Am-242
Am-243                   Np-239
 
\c\ [Reserved]
\d\ These values apply only to compounds of uranium that take the
  chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident
  conditions of transport.
\e\ These values apply only to compounds of uranium that take the
  chemical form of UO3, UF4, UCl4 and hexavalent compounds in both
  normal and accident conditions of transport.
\f\ These values apply to all compounds of uranium other than those
  specified in notes (d) and (e) of this table.
\g\ These values apply to unirradiated uranium only.


                                                         Table A-3--General Values for A1 and A2
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                           A1                        A2                 Activity          Activity      Activity limits  Activity limits
                                ---------------------------------------------------   concentration     concentration      for exempt       for exempt
            Contents                                                                   for exempt        for exempt       consignments     consignments
                                   (TBq)        (Ci)       (TBq)         (Ci)        material (Bq/g)   material (Ci/g)        (Bq)             (Ci)
--------------------------------------------------------------------------------------------------------------------------------------------------------
Only beta or gamma emitting      1 x 10-1   2.7 x 10\0\  2 x 10-2   5.4 x 10-1      1 x 10\1\         2.7 x 10-10       1 x 10\4\        2.7 x 10-7
 radionuclides are known to be
 present.
Alpha emitting nuclides, but no  2 x 10-    5.4 x 10\0\  9 x 10-    2.4 x 10-\3\    1 x 10-\1\        2.7 x 10-\12\     1 x 10\3\        2.7 x 10-\8\
 neutron emitters, are known to   \1\                     \5\
 be present (a).

[[Page 395]]

 
Neutron emitting nuclides are    1 x 10-    2.7 x 10-    9 x 10-    2.4 x 10-\3\    1 x 10-\1\        2.7 x 10-\12\     1 x 10\3\        2.7 x 10-\8\
 known to be present or no        \3\        \2\          \5\
 relevant data are available.
--------------------------------------------------------------------------------------------------------------------------------------------------------
\a\ If beta or gamma emitting nuclides are known to be present, the A1 value of 0.1 TBq (2.7 Ci) should be used.


           Table A-4--Activity-mass Relationships for Uranium
------------------------------------------------------------------------
                                             Specific Activity
Uranium Enrichment \1\ wt % U-235 --------------------------------------
             present                      TBq/g               Ci/g
------------------------------------------------------------------------
0.45.............................  1.8 x 10-8          5.0 x 10-7
0.72.............................  2.6 x 10-8          7.1 x 10-7
1................................  2.8 x 10-8          7.6 x 10-7
1.5..............................  3.7 x 10-8          1.0 x 10-6
5................................  1.0 x 10-7          2.7 x 10-6
10...............................  1.8 x 10-7          4.8 x 10-6
20...............................  3.7 x 10-7          1.0 x 10-5
35...............................  7.4 x 10-7          2.0 x 10-5
50...............................  9.3 x 10-7          2.5 x 10-5
90...............................  2.2 x 10-6          5.8 x 10-5
93...............................  2.6 x 10-6          7.0 x 10-5
95...............................  3.4 x 10-6          9.1 x 10-5
------------------------------------------------------------------------
\1\ The figures for uranium include representative values for the
  activity of the uranium-234 that is concentrated during the enrichment
  process.


[69 FR 3800, Jan. 26, 2004; 69 FR 58039, Sept. 29, 2004, as amended at 
77 FR 39908, July 6, 2012; 80 FR 34014, June 12, 2015]



PART 72_LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT
NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED 
GREATER THAN CLASS C WASTE--Table of Contents



                      Subpart A_General Provisions

Sec.
72.1 Purpose.
72.2 Scope.
72.3 Definitions.
72.4 Communications.
72.5 Interpretations.
72.6 License required; types of licenses.
72.7 Specific exemptions.
72.8 Denial of licensing by Agreement States.
72.9 Information collection requirements: OMB approval.
72.10 Employee protection.
72.11 Completeness and accuracy of information.
72.12 Deliberate misconduct.
72.13 Applicability.

            Subpart B_License Application, Form, and Contents

72.16 Filing of application for specific license.
72.18 Elimination of repetition.
72.20 Public inspection of application.
72.22 Contents of application: General and financial information.
72.24 Contents of application: Technical information.
72.26 Contents of application: Technical specifications.
72.28 Contents of application: Applicant's technical qualifications.
72.30 Financial assurance and recordkeeping for decommissioning.
72.32 Emergency Plan.
72.34 Environmental report.

              Subpart C_Issuance and Conditions of License

72.40 Issuance of license.
72.42 Duration of license; renewal.
72.44 License conditions.
72.46 Public hearings.
72.48 Changes, tests, and experiments.
72.50 Transfer of license.
72.52 Creditor regulations.
72.54 Expiration and termination of licenses and decommissioning of 
          sites and separate buildings or outdoor areas.
72.56 Application for amendment of license.
72.58 Issuance of amendment.
72.60 Modification, revocation, and suspension of license.
72.62 Backfitting.

        Subpart D_Records, Reports, Inspections, and Enforcement

72.70 Safety analysis report updating.

[[Page 396]]

72.72 Material balance, inventory, and records requirements for stored 
          materials.
72.74 Reports of accidental criticality or loss of special nuclear 
          material.
72.75 Reporting requirements for specific events and conditions.
72.76 Material status reports.
72.78 Nuclear material transaction reports.
72.79 Facility information and verification.
72.80 Other records and reports.
72.82 Inspections and tests.
72.84 Violations.
72.86 Criminal penalties.

                   Subpart E_Siting Evaluation Factors

72.90 General considerations.
72.92 Design basis external natural events.
72.94 Design basis external man-induced events.
72.96 Siting limitations.
72.98 Identifying regions around an ISFSI or MRS site.
72.100 Defining potential effects of the ISFSI or MRS on the region.
72.102 Geological and seismological characteristics for applications 
          before October 16, 2003 and applications for other than dry 
          cask modes of storage.
72.103 Geological and seismological characteristics for applications for 
          dry cask modes of storage on or after October 16, 2003.
72.104 Criteria for radioactive materials in effluents and direct 
          radiation from an ISFSI or MRS.
72.106 Controlled area of an ISFSI or MRS.
72.108 Spent fuel, high-level radioactive waste, or reactor-related 
          greater than Class C waste transportation.

                    Subpart F_General Design Criteria

72.120 General considerations.
72.122 Overall requirements.
72.124 Criteria for nuclear criticality safety.
72.126 Criteria for radiological protection.
72.128 Criteria for spent fuel, high-level radioactive waste, reactor-
          related greater than Class C waste, and other radioactive 
          waste storage and handling.
72.130 Criteria for decommissioning.

                       Subpart G_Quality Assurance

72.140 Quality assurance requirements.
72.142 Quality assurance organization.
72.144 Quality assurance program.
72.146 Design control.
72.148 Procurement document control.
72.150 Instructions, procedures, and drawings.
72.152 Document control.
72.154 Control of purchased material, equipment, and services.
72.156 Identification and control of materials, parts, and components.
72.158 Control of special processes.
72.160 Licensee and certificate holder inspection.
72.162 Test control.
72.164 Control of measuring and test equipment.
72.166 Handling, storage, and shipping control.
72.168 Inspection, test, and operating status.
72.170 Nonconforming materials, parts, or components.
72.172 Corrective action.
72.174 Quality assurance records.
72.176 Audits.

                      Subpart H_Physical Protection

72.180 Physical protection plan.
72.182 Design for physical protection.
72.184 Safeguards contingency plan.
72.186 Change to physical security and safeguards contingency plans.

            Subpart I_Training and Certification of Personnel

72.190 Operator requirements.
72.192 Operator training and certification program.
72.194 Physical requirements.

 Subpart J_Provision of MRS Information to State Governments and Indian 
                                 Tribes

72.200 Provision of MRS information.
72.202 Participation in license reviews.
72.204 Notice to States.
72.206 Representation.

  Subpart K_General License for Storage of Spent Fuel at Power Reactor 
                                  Sites

72.210 General license issued.
72.212 Conditions of general license issued under Sec. 72.210.
72.214 List of approved spent fuel storage casks.
72.216 [Reserved]
72.218 Termination of licenses.
72.220 Violations.

             Subpart L_Approval of Spent Fuel Storage Casks

72.230 Procedures for spent fuel storage cask submittals.
72.232 Inspection and tests.
72.234 Conditions of approval.
72.236 Specific requirements for spent fuel storage cask approval and 
          fabrication.
72.238 Issuance of an NRC Certificate of Compliance.
72.240 Conditions for spent fuel storage cask renewal.
72.242 Recordkeeping and reports.
72.244 Application for amendment of a certificate of compliance.

[[Page 397]]

72.246 Issuance of amendment to a certificate of compliance.
72.248 Safety analysis report updating.

    Authority: Atomic Energy Act of 1954, secs. 51, 53, 57, 62, 63, 65, 
69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2210e, 2232, 2233, 
2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy Reorganization Act of 
1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); 
National Environmental Policy Act of 1969 (42 U.S.C. 4332); Nuclear 
Waste Policy Act of 1982, secs. 117(a), 132, 133, 134, 135, 137, 141, 
145(g), 148, 218(a) (42 U.S.C. 10137(a), 10152, 10153, 10154, 10155, 
10157, 10161, 10165(g), 10168, 10198(a)); 44 U.S.C. 3504 note.

    Source: 53 FR 31658, Aug. 19, 1988, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 72 appear at 80 FR 
74981, Dec. 1, 2015, and at 81 FR 86910, Dec. 2, 2016.



                      Subpart A_General Provisions



Sec. 72.1  Purpose.

    The regulations in this part establish requirements, procedures, and 
criteria for the issuance of licenses to receive, transfer, and possess 
power reactor spent fuel, power reactor-related Greater than Class C 
(GTCC) waste, and other radioactive materials associated with spent fuel 
storage in an independent spent fuel storage installation (ISFSI) and 
the terms and conditions under which the Commission will issue these 
licenses. The regulations in this part also establish requirements, 
procedures, and criteria for the issuance of licenses to the Department 
of Energy (DOE) to receive, transfer, package, and possess power reactor 
spent fuel, high-level radioactive waste, power reactor-related GTCC 
waste, and other radioactive materials associated with the storage of 
these materials in a monitored retrievable storage installation (MRS). 
The term Monitored Retrievable Storage Installation or MRS, as defined 
in Sec. 72.3, is derived from the Nuclear Waste Policy Act (NWPA) and 
includes any installation that meets this definition. The regulations in 
this part also establish requirements, procedures, and criteria for the 
issuance of Certificates of Compliance approving spent fuel storage cask 
designs.

[66 FR 51838, Oct. 11, 2001]



Sec. 72.2  Scope.

    (a) Except as provided in Sec. 72.6(b), licenses issued under this 
part are limited to the receipt, transfer, packaging, and possession of:
    (1) Power reactor spent fuel to be stored in a complex that is 
designed and constructed specifically for storage of power reactor spent 
fuel aged for at least one year, other radioactive materials associated 
with spent fuel storage, and power reactor-related GTCC waste in a solid 
form in an independent spent fuel storage installation (ISFSI); or
    (2) Power reactor spent fuel to be stored in a monitored retrievable 
storage installation (MRS) owned by DOE that is designed and constructed 
specifically for the storage of spent fuel aged for at least one year, 
high-level radioactive waste that is in a solid form, other radioactive 
materials associated with storage of these materials, and power reactor-
related GTCC waste that is in a solid form.
    (b) The regulations in this part pertaining to an independent spent 
fuel storage installation (ISFSI) and a spent fuel storage cask apply to 
all persons in the United States, including persons in Agreement States. 
The regulations in this part pertaining to a monitored retrievable 
storage installation (MRS) apply only to DOE.
    (c) The requirements of this regulation are applicable, as 
appropriate, to both wet and dry modes of storage of--
    (1) Spent fuel and solid reactor-related GTCC waste in an 
independent spent fuel storage installation (ISFSI); and
    (2) Spent fuel, solid high-level radioactive waste, and solid 
reactor-related GTCC waste in a monitored retrievable storage 
installation (MRS).
    (d) Licenses covering the storage of spent fuel in an existing spent 
fuel storage installation shall be issued in accordance with the 
requirements of this part as stated in Sec. 72.40, as applicable.
    (e) This part also gives notice to all persons who knowingly provide 
to any licensee, certificate holder, applicant for a license or 
certificate, contractor, or subcontractor, components, equipment, 
materials, or other goods or services, that relate to a licensee's,

[[Page 398]]

certificate holder's, or applicant's activities subject to this part, 
that they may be individually subject to NRC enforcement action for 
violation of Sec. 72.12.
    (f) Certificates of Compliance approving spent fuel storage cask 
designs shall be issued in accordance with the requirements of subpart L 
of this part.

[53 FR 31658, Aug. 19, 1988, as amended at 56 FR 40692, Aug. 15, 1991; 
63 FR 1900, Jan. 13, 1998; 64 FR 33183, June 22, 1999; 64 FR 56121, Oct. 
15, 1999; 66 FR 51838, Oct. 11, 2001]



Sec. 72.3  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954 (68 Stat. 919) including any 
amendments thereto.
    Affected Indian Tribe means any Indian Tribe--
    (1) Within whose reservation boundaries a monitored retrievable 
storage facility is proposed to be located;
    (2) Whose federally defined possessory or usage rights to other 
lands outside of the reservation's boundaries arising out of 
congressionally ratified treaties may be substantially and adversely 
affected by the locating of such a facility: Provided, That the 
Secretary of the Interior finds, upon the petition of the appropriate 
governmental officials of the Tribe, that such effects are both 
substantial and adverse to the Tribe.
    Affected unit of local government means any unit of local government 
with jurisdiction over the site where an MRS is proposed to be located.
    AMP, for the purposes of this part, means a program for addressing 
aging effects that may include prevention, mitigation, condition 
monitoring, and performance monitoring.
    As low as is reasonably achievable (ALARA) means as low as is 
reasonably achievable taking into account the state of technology, and 
the economics of improvement in relation to--
    (1) Benefits to the public health and safety,
    (2) Other societal and socioeconomic considerations, and
    (3) The utilization of atomic energy in the public interest.
    Atomic energy means all forms of energy released in the course of 
nuclear fission or nuclear transformation.
    Byproduct material means--
    (1) Any radioactive material (except special nuclear material) 
yielded in, or made radioactive by, exposure to the radiation incident 
to the process of producing or using special nuclear material;
    (2)(i) Any discrete source of radium-226 that is produced, 
extracted, or converted after extraction, before, on, or after August 8, 
2005, for use for a commercial, medical, or research activity; or
    (ii) Any material that--
    (A) Has been made radioactive by use of a particle accelerator; and
    (B) Is produced, extracted, or converted after extraction, before, 
on, or after August 8, 2005, for use for a commercial, medical, or 
research activity; and
    (3) Any discrete source of naturally occurring radioactive material, 
other than source material, that--
    (i) The Commission, in consultation with the Administrator of the 
Environmental Protection Agency, the Secretary of Energy, the Secretary 
of Homeland Security, and the head of any other appropriate Federal 
agency, determines would pose a threat similar to the threat posed by a 
discrete source of radium-226 to the public health and safety or the 
common defense and security; and
    (ii) Before, on, or after August 8, 2005, is extracted or converted 
after extraction for use in a commercial, medical, or research activity.
    Certificate holder means a person who has been issued a Certificate 
of Compliance by the Commission for a spent fuel storage cask design.
    Certificate of Compliance or CoC means the certificate issued by the 
Commission that approves the design of a spent fuel storage cask in 
accordance with the provisions of subpart L of this part.
    Commencement of construction means any clearing of land, excavation, 
or other substantial action that would adversely affect the natural 
environment of a site, but does not mean:
    (1) Changes desirable for the temporary use of the land for public 
recreational uses, necessary borings or excavations to determine 
subsurface materials and foundation conditions, or other preconstruction 
monitoring to

[[Page 399]]

establish background information related to the suitability of the site 
or to the protection of environmental values;
    (2) Construction of environmental monitoring facilities;
    (3) Procurement or manufacture of components of the installation; or
    (4) Construction of means of access to the site as may be necessary 
to accomplish the objectives of paragraphs (1) and (2) of this 
definition.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Confinement systems means those systems, including ventilation, that 
act as barriers between areas containing radioactive substances and the 
environment.
    Controlled area means that area immediately surrounding an ISFSI or 
MRS for which the licensee exercises authority over its use and within 
which ISFSI or MRS operations are performed.
    Decommission means to remove a facility or site safely from service 
and reduce residual radioactivity to a level that permits--
    (1) Release of the property for unrestricted use and termination of 
the license; or
    (2) Release of the property under restricted conditions and 
termination of the license.
    Design bases means that information that identifies the specific 
functions to be performed by a structure, system, or component of a 
facility or of a spent fuel storage cask and the specific values or 
ranges of values chosen for controlling parameters as reference bounds 
for design. These values may be restraints derived from generally 
accepted state-of-the-art practices for achieving functional goals or 
requirements derived from analysis (based on calculation or experiments) 
of the effects of a postulated event under which a structure, system, or 
component must meet its functional goals. The values for controlling 
parameters for external events include--
    (1) Estimates of severe natural events to be used for deriving 
design bases that will be based on consideration of historical data on 
the associated parameters, physical data, or analysis of upper limits of 
the physical processes involved; and
    (2) Estimates of severe external man-induced events to be used for 
deriving design bases that will be based on analysis of human activity 
in the region, taking into account the site characteristics and the 
risks associated with the event.
    Design capacity means the quantity of spent fuel, high-level 
radioactive waste, or reactor-related GTCC waste, the maximum burn up of 
the spent fuel in MWD/MTU, the terabequerel (curie) content of the 
waste, and the total heat generation in Watts (btu/hour) that the 
storage installation is designed to accommodate.
    DOE means the U.S. Department of Energy or its duly authorized 
representatives.
    Floodplain means the lowland and relatively flat areas adjoining 
inland and coastal waters including floodprone areas of offshore 
islands. Areas subject to a one percent or greater chance of flooding in 
any given year are included.
    Greater than Class C waste or GTCC waste means low-level radioactive 
waste that exceeds the concentration limits of radionuclides established 
for Class C waste in Sec. 61.55 of this chapter.
    High-level radioactive waste or HLW means (1) the highly radioacive 
material resulting from the reprocessing of spent nuclear fuel, 
including liquid waste produced directly in reprocessing and any solid 
material derived from such liquid waste that contains fission products 
in sufficient concentrations; and (2) other highly radioactive material 
that the Commission, consistent with existing law, determines by rule 
requires permanent isolation.
    Historical data means a compilation of the available published and 
unpublished information concerning a particular type of event.
    Independent spent fuel storage installation or ISFSI means a complex 
designed and constructed for the interim storage of spent nuclear fuel, 
solid reactor-related GTCC waste, and other radioactive materials 
associated with spent fuel and reactor-related GTCC waste storage. An 
ISFSI which is located on the site of another facility licensed under 
this part or a facility licensed under part 50 of this chapter and which

[[Page 400]]

shares common utilities and services with that facility or is physically 
connected with that other facility may still be considered independent.
    Indian Tribe means an Indian Tribe as defined in the Indian Self 
Determination and Education Assistance Act (Pub. L. 93-638).
    Monitored Retrievable Storage Installation or MRS means a complex 
designed, constructed, and operated by DOE for the receipt, transfer, 
handling, packaging, possession, safeguarding, and storage of spent 
nuclear fuel aged for at least one year, solidified high-level 
radioactive waste resulting from civilian nuclear activities, and solid 
reactor-related GTCC waste, pending shipment to a HLW repository or 
other disposal.
    NEPA means the National Environmental Policy Act of 1969 including 
any amendments thereto.
    NWPA means the Nuclear Waste Policy Act of 1982 including any 
amendments thereto.
    Person means--
    (1) Any individual, corporation, partnership, firm, association, 
trust, estate, public or private institution, group, Government agency 
other than the Commission or the Department of Energy (DOE), except that 
the DOE shall be considered a person within the meaning of the 
regulations in this part to the extent that its facilities and 
activities are subject to the licensing and related regulatory authority 
of the Commission pursuant to section 202 of the Energy Reorganization 
Act of 1974, as amended (88 Stat. 1244), and Sections 131, 132, 133, 
135, 137, and 141 of the Nuclear Waste Policy Act of 1982 (96 Stat. 
2229, 2230, 2232, 2241);
    (2) Any State, any political subdivision of a State, or any 
political entity within a State;
    (3) Any foreign government or nation, or any political subdivision 
of any such government or nation, or other entity; and
    (4) Any legal successor, representative, agent, or agency of the 
foregoing.
    Population means the people that may be affected by the change in 
environmental conditions due to the construction, operation, or 
decommissioning of an ISFSI or MRS.
    Principal activities, as used in this part, means activities 
authorized by the license which are essential to achieving the 
purpose(s) for which the license was issued or amended, excluding 
activities incidental to decontamination or decommissioning.
    Reconciliation means the process of evaluating and comparing 
licensee reports required under this part to the projected material 
balances generated by the Nuclear Materials Management and Safeguards 
System. This process is considered complete when the licensee resolves 
any differences between the reported and projected balances, including 
those listed for foreign obligated materials.
    Region means the geographical area surrounding and including the 
site, which is large enough to contain all the features related to a 
phenomenon or to a particular event that could potentially impact the 
safe or environmentally sound construction, operation, or 
decommissioning of an independent spent fuel storage or monitored 
retrievable storage installation.
    Reservation means--
    (1) Any Indian reservation or dependent Indian community referred to 
in clause (a) or (b) of section 1151 of title 18, United States Code; or
    (2) Any land selected by an Alaska Native village or regional 
corporation under the provisions of the Alaska Native Claims Settlement 
Act (43 U.S.C. 1601 et seq.).
    Site means the real property on which the ISFSI or MRS is located.
    Source material means--
    (1) Uranium or thorium, or any combination thereof, in any physical 
or chemical form or
    (2) Ores that contain by weight one-twentieth of one percent (0.05%) 
or more of:
    (i) Uranium,
    (ii) Thorium, or
    (iii) Any combination thereof.

Source material does not include special nuclear material.
    Special nuclear material means--
    (1) Plutonium, uranium-233, uranium enriched in the isotope 233 or 
in the isotope 235, and any other material which the Commission, 
pursuant to the

[[Page 401]]

provisions of section 51 of the Act, determines to be special nuclear 
material, but does not include source material; or
    (2) Any material artificially enriched by any of the foregoing but 
does not include source material.
    Spent fuel storage cask or cask means all the components and systems 
associated with the container in which spent fuel or other radioactive 
materials associated with spent fuel are stored in an ISFSI.
    Spent nuclear fuel or Spent fuel means fuel that has been withdrawn 
from a nuclear reactor following irradiation, has undergone at least one 
year's decay since being used as a source of energy in a power reactor, 
and has not been chemically separated into its constituent elements by 
reprocessing. Spent fuel includes the special nuclear material, 
byproduct material, source material, and other radioactive materials 
associated with fuel assemblies.
    Structures, systems, and components important to safety means those 
features of the ISFSI, MRS, and spent fuel storage cask whose functions 
are--
    (1) To maintain the conditions required to store spent fuel, high-
level radioactive waste, or reactor-related GTCC waste safely;
    (2) To prevent damage to the spent fuel, the high-level radioactive 
waste, or reactor-related GTCC waste container during handling and 
storage; or
    (3) To provide reasonable assurance that spent fuel, high-level 
radioactive waste, or reactor-related GTCC waste can be received, 
handled, packaged, stored, and retrieved without undue risk to the 
health and safety of the public.
    Term certified by the cask's Certificate of Compliance, for the 
purposes of this part, means, for an initial CoC, the period of time 
commencing with the CoC effective date and ending with the CoC 
expiration date, and for a renewed CoC, the period of time commencing 
with the most recent CoC renewal date and ending with the CoC expiration 
date.
    TLAAs, for the purposes of this part, means those licensee or 
certificate holder calculations and analyses that:
    (1) Involve structures, systems, and components important to safety 
within the scope of the license renewal, as delineated in subpart F of 
this part, or within the scope of the spent fuel storage certificate 
renewal, as delineated in subpart L of this part, respectively;
    (2) Consider the effects of aging;
    (3) Involve time-limited assumptions defined by the current 
operating term, for example, 40 years;
    (4) Were determined to be relevant by the licensee or certificate 
holder in making a safety determination;
    (5) Involve conclusions or provide the basis for conclusions related 
to the capability of structures, systems, and components to perform 
their intended safety functions; and
    (6) Are contained or incorporated by reference in the design bases.

[53 FR 31658, Aug. 19, 1988, as amended at 59 FR 36038, July 15, 1994; 
62 FR 39092, July 21, 1997; 64 FR 53614, Oct. 4, 1999; 64 FR 56121, Oct. 
15, 1999; 66 FR 51839, Oct. 11, 2001; 72 FR 55933, Oct. 1, 2007; 73 FR 
32462, June 9, 2008; 76 FR 8889, Feb. 16, 2011]



Sec. 72.4  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk, 
Director, Division of Spent Fuel Management, Office of Nuclear Material 
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001; by hand delivery to the NRC's offices at One White Flint 
North, 11555 Rockville Pike, Rockville, Maryland between 7:30 a.m. and 
4:15 p.m. eastern time; or, where practicable, by electronic submission, 
for example, via Electronic Information Exchange, or CD-ROM. Electronic 
submissions must be made in a manner that enables the NRC to receive, 
read, authenticate, distribute, and archive the submission, and process 
and retrieve it a single page at a time. Detailed guidance on making 
electronic submissions can be obtained by visiting the NRC's Web site at 
http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic

[[Page 402]]

signatures, and the treatment of nonpublic information. If the 
submission deadline date falls on a Saturday, or Sunday, or a Federal 
holiday, the next Federal working day becomes the official due date.

[68 FR 58818, Oct. 10, 2003, as amended at 74 FR 62684, Dec. 1, 2009; 75 
FR 73945, Nov. 30, 2010; 79 FR 75741, Dec. 19, 2014; 80 FR 74981, Dec. 
1, 2015]



Sec. 72.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by an 
officer or employee of the Commission, other than a written 
interpretation by the General Counsel, will be recognized to be binding 
upon the Commission.



Sec. 72.6  License required; types of licenses.

    (a) Licenses for the receipt, handling, storage, and transfer of 
spent fuel or high-level radioactive waste are of two types: general and 
specific. Licenses for the receipt, handling, storage, and transfer of 
reactor-related GTCC are specific licenses. Any general license provided 
in this part is effective without the filing of an application with the 
Commission or the issuance of a licensing document to a particular 
person. A specific license is issued to a named person upon application 
filed pursuant to regulations in this part.
    (b) A general license is hereby issued to receive title to and own 
spent fuel, high-level radioactive waste, or reactor-related GTCC waste 
without regard to quantity. Notwithstanding any other provision of this 
chapter, a general licensee under this paragraph is not authorized to 
acquire, deliver, receive, possess, use, or transfer spent fuel, high-
level radioactive waste, or reactor-related GTCC waste except as 
authorized in a specific license.
    (c) Except as authorized in a specific license and in a general 
license under subpart K of this part issued by the Commission in 
accordance with the regulations in this part, no person may acquire, 
receive, or possess--
    (1) Spent fuel for the purpose of storage in an ISFSI; or
    (2) Spent fuel, high-level radioactive waste, or radioactive 
material associated with high-level radioactive waste for the purpose of 
storage in an MRS.

[66 FR 51839, Oct. 11, 2001]



Sec. 72.7  Specific exemptions.

    The Commission may, upon application by any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
will not endanger life or property or the common defense and security 
and are otherwise in the public interest.



Sec. 72.8  Denial of licensing by Agreement States.

    Agreement States may not issue licenses covering the storage of 
spent fuel and reactor-related GTCC waste in an ISFSI or the storage of 
spent fuel, high-level radioactive waste, and reactor-related GTCC waste 
in an MRS.

[66 FR 51839, Oct. 11, 2001]



Sec. 72.9  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). OMB has approved the 
information collection requirements contained in this part under control 
number 3150-0132.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 72.7, 72.11, 72.16, 72.22 through 72.34, 
72.42, 72.44, 72.48 through 72.56, 72.62, 72.70, through 72.80, 72.90, 
72.92, 72.94, 72.98, 72.100, 72.102, 72.103, 72.104, 72.108, 72.120, 
72.126, 72.140 through 72.176, 72.180 through 72.186, 72.192, 72.206, 
72.212, 72.218, 72.230, 72.232, 72.234, 72.236, 72.240, 72.242, 72.244, 
72.248.
    (c) In Sec. 72.79, Form N-71 and associated forms are approved 
under control number 3150-0056, and DOC/NRC Forms AP-1, AP-A, and 
associated forms are approved under control number 0694-0135.

[64 FR 56122, Oct. 15, 1999, as amended at 67 FR 67101, Nov. 4, 2002; 68 
FR 54149, Sept. 16, 2003; 73 FR 78607, Dec. 23, 2008; 77 FR 39909, July 
6, 2012]

[[Page 403]]



Sec. 72.10  Employee protection.

    (a) Discrimination by a Commission licensee, certificate holder, an 
applicant for a Commission license or a CoC, or a contractor or 
subcontractor of any of these, against an employee for engaging in 
certain protected activities, is prohibited. Discrimination includes 
discharge and other actions that relate to compensation, terms, 
conditions, or privileges of employment. The protected activities are 
established in section 211 of the Energy Reorganization Act of 1974, as 
amended, and in general are related to the administration or enforcement 
of a requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) introductory text of this section or possible violations of 
requirements imposed under either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) introductory text or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) introductory 
text.
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, certificate holder, applicant for a Commission 
license or a CoC, or a contractor or subcontractor of any of these may 
be grounds for:
    (1) Denial, revocation, or suspension of the license or the CoC.
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant.
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee, certificate holder, and applicant for a 
license or CoC must prominently post the revision of NRC Form 3, 
``Notice to Employees,'' referenced in 10 CFR 19.11(c). This form must 
be posted at locations sufficient to permit employees protected by this 
section to observe a copy on the way to or from their place of work. The 
premises must be posted not later than 30 days after an application is 
docketed and remain posted while the application is pending before the 
Commission,

[[Page 404]]

during the term of the license or CoC, and for 30 days following license 
or CoC termination.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in Appendix D to Part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[58 FR 52414, Oct. 8, 1993, as amended at 60 FR 24552, May 9, 1995; 61 
FR 6766, Feb. 22, 1996; 64 FR 56122, Oct. 15, 1999; 68 FR 58819, Oct. 
10, 2003; 72 FR 63975, Nov. 14, 2007; 73 FR 30460, May 28, 2008; 79 FR 
66606, Nov. 10, 2014]



Sec. 72.11  Completeness and accuracy of information.

    (a) Information provided to the Commission by a licensee, 
certificate holder, or an applicant for a license or CoC; or information 
required by statute or by the Commission's regulations, orders, license 
or CoC conditions, to be maintained by the licensee or certificate 
holder, must be complete and accurate in all material respects.
    (b) Each licensee, certificate holder, or applicant for a license or 
CoC must notify the Commission of information identified by the 
licensee, certificate holder, or applicant for a license or CoC as 
having, for the regulated activity, a significant implication for public 
health and safety or common defense and security. A licensee, 
certificate holder, or an applicant for a license or CoC violates this 
paragraph only if the licensee, certificate holder, or applicant for a 
license or CoC fails to notify the Commission of information that the 
licensee, certificate holder, or applicant for a license or CoC has 
identified as having a significant implication for public health and 
safety or common defense and security. Notification must be provided to 
the Administrator of the appropriate Regional Office within two working 
days of identifying the information. This requirement is not applicable 
to information which is already required to be provided to the 
Commission by other reporting or updating requirements.

[64 FR 56122, Oct. 15, 1999]



Sec. 72.12  Deliberate misconduct.

    (a) Any licensee, certificate holder, applicant for a license or 
certificate, employee of a licensee, certificate holder, or applicant 
for a license or certificate; or any contractor (including a supplier or 
consultant) or subcontractor, employee of a contractor or subcontractor 
of any licensee, certificate holder, or applicant for a license or 
certificate who knowingly provides to any licensee, certificate holder, 
applicant for a license or certificate, contractor, or subcontractor, 
any components, materials, or other goods or services that relate to a 
licensee's, certificate holder's, or applicant's activities subject to 
this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee, certificate holder or applicant to 
be in violation of any rule, regulation, or order; or any term, 
condition, or limitation of any license or certificate issued by the 
Commission; or
    (2) Deliberately submit to the NRC, a licensee, a certificate 
holder, an applicant for a license or certificate, or a licensee's, 
applicant's, or certificate holder's contractor or subcontractor, 
information that the person submitting the information knows to be 
incomplete or inaccurate in some respect material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.

[[Page 405]]

    (c) For the purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee, certificate holder or applicant for a 
license or certificate to be in violation of any rule, regulation, or 
order; or any term, condition, or limitation, of any license or 
certificate issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
certificate holder, applicant, contractor, or subcontractor.

[63 FR 1900, Jan. 13, 1998]



Sec. 72.13  Applicability.

    (a) This section identifies those sections, under this part, that 
apply to the activities associated with a specific license, a general 
license, or a certificate of compliance.
    (b) The following sections apply to activities associated with a 
specific license: Sec. Sec. 72.1; 72.2(a) through (e); 72.3 through 
72.13(b); 72.16 through 72.34; 72.40 through 72.62; 72.70 through 72.86; 
72.90 through 72.108; 72.120 through 72.130; 72.140 through 72.176; 
72.180 through 72.186; 72.190 through 72.194; and 72.200 through 72.206.
    (c) The following sections apply to activities associated with a 
general license: 72.1; 72.2(a)(1), (b), (c), and (e); 72.3 through 
72.6(c)(1); 72.7 through 72.13(a) and (c); 72.30(b), (c), (d), (e) and 
(f); 72.32(c) and (d); 72.44(b) and (f); 72.48; 72.50(a); 72.52(a), (b), 
(d), and (e); 72.60; 72.62; 72.72 through 72.80(f); 72.82 through 72.86; 
72.104; 72.106; 72.122; 72.124; 72.126; 72.140 through 72.176; 72.190; 
72.194; 72.210 through 72.220, and 72.240(a).
    (d) The following sections apply to activities associated with a 
certificate of compliance: Sec. Sec. 72.1; 72.2(e) and (f); 72.3; 72.4; 
72.5; 72.7; 72.9 through 72.13(a) and (d); 72.48; 72.84(a); 72.86; 
72.124; 72.140 through 72.176; 72.214; and 72.230 through 72.248.

[65 FR 50616, Aug. 21, 2000, as amended at 76 FR 35573, June 17, 2011]



            Subpart B_License Application, Form, and Contents



Sec. 72.16  Filing of application for specific license.

    (a) Place of filing. Each application for a license, or amendment 
thereof, under this part should be filed with the Director of the NRC's 
Division of Spent Fuel Management, Office of Nuclear Material Safety and 
Safeguards in accordance with Sec. 72.4.
    (b) Oath or affirmation. Each application for a license or license 
amendment (including amendments to such applications), except for those 
filed by DOE, must be executed in an original signed by the applicant or 
duly authorized officer thereof under oath or affirmation. Each 
application for a license or license amendment (including amendments to 
such applications) filed by DOE must be signed by the Secretary of 
Energy or the Secretary's authorized representative.
    (c) Copies of application on paper or CD-ROM. If the application is 
on paper, it must be the signed original. The applicant shall maintain 
the capability to generate additional copies for distribution in 
accordance with instruction from the Director or the Director's 
designee.
    (d) Fees. The application, amendment, and renewal fees applicable to 
a license covering an ISFSI are those shown in Sec. 170.31 of this 
chapter.
    (e) Notice of docketing. Upon receipt of an application for a 
license or license amendment under this part, the Director, Office of 
Nuclear Material Safety and Safeguards or the Director's designee will 
assign a docket number to the application, notify the applicant of the 
docket number, instruct the applicant to distribute copies retained by 
the applicant in accordance with paragraph (c) of this section, and 
cause a notice of docketing to be published in the Federal Register. The 
notice of docketing shall identify the site of the ISFSI or the MRS by 
locality and State and may include a notice of hearing or a notice of 
proposed action and opportunity for hearing as provided by

[[Page 406]]

Sec. 72.46 of this part. In the case of an application for a license or 
an amendment to a license for an MRS, the Director, Office of Nuclear 
Material Safety and Safeguards, or the Director's designee, in 
accordance with Sec. 72.200 of this part, shall send a copy of the 
notice of docketing to the Governor and legislature of any State in 
which an MRS is or may be located, to the Chief Executive of the local 
municipality, to the Governors of any contiguous States and to the 
governing body of any affected Indian Tribe.

[53 FR 31658, Aug. 19, 1988, as amended at 53 FR 43421, Oct. 27, 1988; 
66 FR 51839, Oct. 11, 2001; 67 FR 3586, Jan. 25, 2002; 68 FR 58819, Oct. 
10, 2003; 75 FR 73945, Nov. 30, 2010; 79 FR 75741, Dec. 19, 2014]



Sec. 72.18  Elimination of repetition.

    In any application under this part, the applicant may incorporate by 
reference information contained in previous applications, statements, or 
reports filed with the Commission: Provided, That such references are 
clear and specific.



Sec. 72.20  Public inspection of application.

    Applications and documents submitted to the Commission in connection 
with applications may be made available for public inspection in 
accordance with provisions of the regulations contained in parts 2 and 9 
of this chapter.



Sec. 72.22  Contents of application: General and financial information.

    Each application must state:
    (a) Full name of applicant;
    (b) Address of applicant;
    (c) Description of business or occupation of applicant;
    (d) If applicant is:
    (1) An individual: Citizenship and age;
    (2) A partnership: Name, citizenship, and address of each partner 
and the principal location at which the partnership does business;
    (3) A corporation or an unincorporated association:
    (i) The State in which it is incorporated or organized and the 
principal location at which it does business; and
    (ii) The names, addresses, and citizenship of its directors and 
principal officers;
    (4) Acting as an agent or representative of another person in filing 
the application: The identification of the principal and the information 
required under this paragraph with respect to such principal.
    (5) The Department of Energy:
    (i) The identification of the DOE organization responsible for the 
construction and operation of the ISFSI or MRS, including a description 
of any delegations of authority and assignments of responsibilities.
    (ii) For each application for a license for an MRS, the provisions 
of the public law authorizing the construction and operation of the MRS.
    (e) Except for DOE, information sufficient to demonstrate to the 
Commission the financial qualifications of the applicant to carry out, 
in accordance with the regulations in this chapter, the activities for 
which the license is sought. The information must state the place at 
which the activity is to be performed, the general plan for carrying out 
the activity, and the period of time for which the license is requested. 
The information must show that the applicant either possesses the 
necessary funds, or that the applicant has reasonable assurance of 
obtaining the necessary; funds or that by a combination of the two, the 
applicant will have the necessary funds available to cover the 
following:
    (1) Estimated construction costs;
    (2) Estimated operating costs over the planned life of the ISFSI; 
and
    (3) Estimated decommissioning costs, and the necessary financial 
arrangements to provide reasonable assurance before licensing, that 
decommissioning will be carried out after the removal of spent fuel, 
high-level radioactive waste, and/or reactor-related GTCC waste from 
storage.
    (f) Each applicant for a license under this part to receive, 
transfer, and possess power reactor spent fuel, power reactor-related 
Greater than Class C (GTCC) waste, and other radioactive materials 
associated with spent fuel storage in an independent spent fuel storage 
installation (ISFSI) shall protect Safeguards Information against

[[Page 407]]

unauthorized disclosure in accordance with the requirements in Sec. 
73.21 and the requirements of Sec. 73.22 or Sec. 73.23, as applicable.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51839, Oct. 11, 2001; 
73 FR 63573, Oct. 24, 2008]



Sec. 72.24  Contents of application: Technical information.

    Each application for a license under this part must include a Safety 
Analysis Report describing the proposed ISFSI or MRS for the receipt, 
handling, packaging, and storage of spent fuel, high-level radioactive 
waste, and/or reactor-related GTCC waste as appropriate, including how 
the ISFSI or MRS will be operated. The minimum information to be 
included in this report must consist of the following:
    (a) A description and safety assessment of the site on which the 
ISFSI or MRS is to be located, with appropriate attention to the design 
bases for external events. Such assessment must contain an analysis and 
evaluation of the major structures, systems, and components of the ISFSI 
or MRS that bear on the suitability of the site when the ISFSI or MRS is 
operated at its design capacity. If the proposed ISFSI or MRS is to be 
located on the site of a nuclear power plant or other licensed facility, 
the potential interactions between the ISFSI or MRS and such other 
facility--including shared common utilities and services--must be 
evaluated.
    (b) A description and discussion of the ISFSI or MRS structures with 
special attention to design and operating characteristics, unusual or 
novel design features, and principal safety considerations.
    (c) The design of the ISFSI or MRS in sufficient detail to support 
the findings in Sec. 72.40 for the term requested in the application, 
including:
    (1) The design criteria for the ISFSI or MRS pursuant to subpart F 
of this part, with identification and justification for any additions to 
or departures from the general design criteria;
    (2) the design bases and the relation of the design bases to the 
design criteria;
    (3) Information relative to materials of construction, general 
arrangement, dimensions of principal structures, and descriptions of all 
structures, systems, and components important to safety, in sufficient 
detail to support a finding that the ISFSI or MRS will satisfy the 
design bases with an adequate margin for safety; and
    (4) Applicable codes and standards.
    (d) An analysis and evaluation of the design and performance of 
structures, systems, and components important to safety, with the 
objective of assessing the impact on public health and safety resulting 
from operation of the ISFSI or MRS and including determination of:
    (1) The margins of safety during normal operations and expected 
operational occurrences during the life of the ISFSI or MRS; and
    (2) The adequacy of structures, systems, and components provided for 
the prevention of accidents and the mitigation of the consequences of 
accidents, including natural and manmade phenomena and events.
    (e) The means for controlling and limiting occupational radiation 
exposures within the limits given in part 20 of this chapter, and for 
meeting the objective of maintaining exposures as low as is reasonably 
achievable.
    (f) The features of ISFSI or MRS design and operating modes to 
reduce to the extent practicable radioactive waste volumes generated at 
the installation.
    (g) An identification and justification for the selection of those 
subjects that will be probable license conditions and technical 
specifications. These subjects must cover the design, construction, 
preoperational testing, operation, and decommissioning of the ISFSI or 
MRS.
    (h) A plan for the conduct of operations, including the planned 
managerial and administrative controls system, and the applicant's 
organization, and program for training of personnel pursuant to subpart 
I.
    (i) If the proposed ISFSI or MRS incorporates structures, systems, 
or components important to safety whose functional adequacy or 
reliability have not been demonstrated by prior use for that purpose or 
cannot be demonstrated by reference to performance data in related 
applications or to widely accepted engineering principles, an

[[Page 408]]

identification of these structures, systems, or components along with a 
schedule showing how safety questions will be resolved prior to the 
initial receipt of spent fuel, high-level radioactive waste, and/or 
reactor-related GTCC waste as appropriate for storage at the ISFSI or 
MRS.
    (j) The technical qualifications of the applicant to engage in the 
proposed activities, as required by Sec. 72.28.
    (k) A description of the applicant's plans for coping with 
emergencies, as required by Sec. 72.32.
    (l) A description of the equipment to be installed to maintain 
control over radioactive materials in gaseous and liquid effluents 
produced during normal operations and expected operational occurrences. 
The description must identify the design objectives and the means to be 
used for keeping levels of radioactive material in effluents to the 
environment as low as is reasonably achievable and within the exposure 
limits stated in Sec. 72.104. The description must include:
    (1) An estimate of the quantity of each of the principal 
radionuclides expected to be released annually to the environment in 
liquid and gaseous effluents produced during normal ISFSI or MRS 
operations;
    (2) A description of the equipment and processes used in radioactive 
waste systems; and
    (3) A general description of the provisions for packaging, storage, 
and disposal of solid wastes containing radioactive materials resulting 
from treatment of gaseous and liquid effluents and from other sources.
    (m) An analysis of the potential dose equivalent or committed dose 
equivalent to an individual outside the controlled area from accidents 
or natural phenomena events that result in the release of radioactive 
material to the environment or direct radiation from the ISFSI or MRS. 
The calculations of individual dose equivalent or committed dose 
equivalent must be performed for direct exposure, inhalation, and 
ingestion occurring as a result of the postulated design basis event.
    (n) A description of the quality assurance program that satisfies 
the requirements of subpart G to be applied to the design, fabrication, 
construction, testing, operation, modification, and decommissioning of 
the structures, systems, and components of the ISFSI or MRS important to 
safety. The description must identify the structures, systems, and 
components important to safety. The program must also apply to 
managerial and administrative controls used to ensure safe operation of 
the ISFSI or MRS.
    (o) A description of the detailed security measures for physical 
protection, including design features and the plans required by subpart 
H. For an application from DOE for an ISFSI or MRS, DOE will provide a 
description of the physical protection plan for protection against 
radiological sabotage as required by subpart H.
    (p) A description of the program covering preoperational testing and 
initial operations.
    (q) A description of the decommissioning plan required under Sec. 
72.30.

[53 FR 31658, Aug. 19, 1988, as amended at 63 FR 26961, May 15, 1998; 64 
FR 53615, Oct. 4, 1999; 66 FR 51839, Oct. 11, 2001; 76 FR 8890, Feb. 16, 
2011]



Sec. 72.26  Contents of application: Technical specifications.

    Each application under this part shall include proposed technical 
specifications in accordance with the requirements of Sec. 72.44 and a 
summary statement of the bases and justifications for these technical 
specifications.



Sec. 72.28  Contents of application: Applicant's technical
qualifications.

    Each application under this part must include:
    (a) The technical qualifications, including training and experience, 
of the applicant to engage in the proposed activities;
    (b) A description of the personnel training program required under 
subpart I;
    (c) A description of the applicant's operating organization, 
delegations of responsibility and authority and the minimum skills and 
experience qualifications relevant to the various levels of 
responsibility and authority; and
    (d) A commitment by the applicant to have and maintain an adequate 
complement of trained and certified installation personnel prior to the 
receipt of

[[Page 409]]

spent fuel, high-level radioactive waste, and/or reactor-related GTCC 
waste as appropriate for storage.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51840, Oct. 11, 2001]



Sec. 72.30  Financial assurance and recordkeeping for decommissioning.

    (a) Each application under this part must include a proposed 
decommissioning plan that contains sufficient information on proposed 
practices and procedures for the decontamination of the site and 
facilities and for disposal of residual radioactive materials after all 
spent fuel, high-level radioactive waste, and reactor-related GTCC waste 
have been removed, in order to provide reasonable assurance that the 
decontamination and decommissioning of the ISFSI or MRS at the end of 
its useful life will provide adequate protection to the health and 
safety of the public. This plan must identify and discuss those design 
features of the ISFSI or MRS that facilitate its decontamination and 
decommissioning at the end of its useful life.
    (b) Each holder of, or applicant for, a license under this part must 
submit for NRC review and approval a decommissioning funding plan that 
must contain:
    (1) Information on how reasonable assurance will be provided that 
funds will be available to decommission the ISFSI or MRS.
    (2) A detailed cost estimate for decommissioning, in an amount 
reflecting:
    (i) The cost of an independent contractor to perform all 
decommissioning activities;
    (ii) An adequate contingency factor; and
    (iii) The cost of meeting the Sec. 20.1402 of this chapter criteria 
for unrestricted use, provided that, if the applicant or licensee can 
demonstrate its ability to meet the provisions of Sec. 20.1403 of this 
chapter, the cost estimate may be based on meeting the Sec. 20.1403 
criteria.
    (3) Identification of and justification for using the key 
assumptions contained in the DCE.
    (4) A description of the method of assuring funds for 
decommissioning from paragraph (e) of this section, including means for 
adjusting cost estimates and associated funding levels periodically over 
the life of the facility.
    (5) The volume of onsite subsurface material containing residual 
radioactivity that will require remediation to meet the criteria for 
license termination.
    (6) A certification that financial assurance for decommissioning has 
been provided in the amount of the cost estimate for decommissioning.
    (c) At the time of license renewal and at intervals not to exceed 3 
years, the decommissioning funding plan must be resubmitted with 
adjustments as necessary to account for changes in costs and the extent 
of contamination. If the amount of financial assurance will be adjusted 
downward, this can not be done until the updated decommissioning funding 
plan is approved. The decommissioning funding plan must update the 
information submitted with the original or prior approved plan and must 
specifically consider the effect of the following events on 
decommissioning costs:
    (1) Spills of radioactive material producing additional residual 
radioactivity in onsite subsurface material.
    (2) Facility modifications.
    (3) Changes in authorized possession limits.
    (4) Actual remediation costs that exceed the previous cost estimate.
    (d) If, in surveys made under 10 CFR 20.1501(a), residual 
radioactivity in soils or groundwater is detected at levels that would 
require such radioactivity to be reduced to a level permitting release 
of the property for unrestricted use under the decommissioning 
requirements in part 20 of this chapter, the licensee must submit a new 
or revised decommissioning funding plan within one year of when the 
survey is completed.
    (e) The financial instrument must include the licensee's name, 
license number, and docket number; and the name, address, and other 
contact information of the issuer, and, if a trust is used, the trustee. 
When any of the foregoing information changes, the licensee must, within 
30 days, submit financial instruments reflecting such changes. Financial 
assurance for decommissioning must be provided by one or more of the 
following methods:

[[Page 410]]

    (1) Prepayment. Prepayment is the deposit before the start of 
operation into an account segregated from licensee assets and outside 
the licensee's administrative control of cash or liquid assets such that 
the amount of funds would be sufficient to pay decommissioning costs. 
Prepayment must be made into a trust account, and the trustee and the 
trust must be acceptable to the Commission.
    (2) A surety method, insurance, or other guarantee method. These 
methods guarantee that decommissioning costs will be paid. A surety 
method may be in the form of a surety bond, or letter of credit. A 
parent company guarantee of funds for decommissioning costs based on a 
financial test may be used if the guarantee and test are as contained in 
Appendix A to part 30 of this chapter. For commercial corporations that 
issue bonds, a guarantee of funds by the applicant or licensee for 
decommissioning costs based on a financial test may be used if the 
guarantee and test are as contained in Appendix C to part 30 of this 
chapter. For commercial companies that do not issue bonds, a guarantee 
of funds by the applicant or licensee for decommissioning costs may be 
used if the guarantee and test are as contained in Appendix D to part 30 
of this chapter. Except for an external sinking fund, a parent company 
guarantee or a guarantee by the applicant or licensee may not be used in 
combination with other financial methods to satisfy the requirements of 
this section. A guarantee by the applicant or licensee may not be used 
in any situation where the applicant or licensee has a parent company 
holding majority control of the voting stock of the company. Any surety 
method or insurance used to provide financial assurance for 
decommissioning must contain the following conditions:
    (i) The surety method or insurance must be open-ended or, if written 
for a specified term, such as five years, must be renewed automatically 
unless 90 days or more prior to the renewal date, the issuer notifies 
the Commission, the beneficiary, and the licensee of its intention not 
to renew. The surety method or insurance must also provide that the full 
face amount be paid to the beneficiary automatically prior to the 
expiration without proof of forfeiture if the licensee fails to provide 
a replacement acceptable to the Commission withing 30 days after receipt 
of notification or cancellation.
    (ii) The surety method or insurance must be payable to a trust 
established for decommissioning costs. The trustee and trust must be 
acceptable to the Commission. An acceptable trustee includes an 
appropriate State or Federal government agency or an entity which has 
the authority to act as a trustee and whose trust operations are 
regulated and examined by a Federal or State agency.
    (iii) The surety or insurance must remain in effect until the 
Commission has terminated the license.
    (3) An external sinking fund in which deposits are made at least 
annually, coupled with a surety method, insurance, or other guarantee 
method, the value of which may decrease by the amount being accumulated 
in the sinking fund. An external sinking fund is a fund established and 
maintained by setting aside funds periodically in an account segregated 
from licensee assets and outside the licensee's administrative control 
in which the total amount of funds would be sufficient to pay 
decommissioning costs at the time termination of operation is expected. 
An external sinking fund must be in the form of a trust. If the other 
guarantee method is used, no surety or insurance may be combined with 
the external sinking fund. The surety, insurance, or other guarantee 
provisions must be as stated in paragraph (e)(2) of this section.
    (4) In the case of Federal, State, or local government licensees, a 
statement of intent containing a cost estimate for decommissioning, and 
indicating that funds for decommissioning will be obtained when 
necessary.
    (5) In the case of licensees who are issued a power reactor license 
under part 50 of this chapter or ISFSI licensees who are an electric 
utility, as defined in part 50 of this chapter, with a specific license 
issued under this part, the methods of 10 CFR 50.75(b), (e), and (h), as 
applicable. In the event that funds remaining to be placed into the

[[Page 411]]

licensee's ISFSI decommissioning external sinking fund are no longer 
approved for recovery in rates by a competent rate making authority, the 
licensee must make changes to provide financial assurance using one or 
more of the methods stated in paragraphs (1) through (4) of this 
section.
    (6) When a governmental entity is assuming ownership of a site, an 
arrangement that is deemed acceptable by such governmental entity.
    (f) Each person licensed under this part shall keep records of 
information important to the decommissioning of a facility in an 
identified location until the site is released for unrestricted use. If 
records important to the decommissioning of a facility are kept for 
other purposes, reference to these records and their locations may be 
used. Information the Commission considers important to decommissioning 
consists of--
    (1) Records of spills or other unusual occurrences involving the 
spread of contamination in and around the facility, equipment, or site. 
These records may be limited to instances when contamination remains 
after any cleanup procedures or when there is reasonable likelihood that 
contaminants may have spread to inaccessible areas as in the case of 
possible seepage into porous materials such as concrete. These records 
must include any known information on identification of involved 
nuclides, quantities, forms, and concentrations.
    (2) As-built drawings and modifications of structures and equipment 
in restricted areas where radioactive materials are used and/or stored, 
and of locations of possible inaccessible contamination such as buried 
pipes which may be subject to contamination. If required drawings are 
referenced, each relevant document need not be indexed individually. If 
drawings are not available, the licensee shall substitute appropriate 
records of available information concerning these areas and locations.
    (3) A list contained in a single document and updated no less than 
every 2 years of the following:
    (i) All areas designated and formerly designated as restricted areas 
as defined under 10 CFR 20.1003; and
    (ii) All areas outside of restricted areas that require 
documentation under Sec. 72.30(f)(1).
    (4) Records of the cost estimate performed for the decommissioning 
funding plan and records of the funding method used for assuring funds 
are available for decommissioning.
    (g) In providing financial assurance under this section, each 
licensee must use the financial assurance funds only for decommissioning 
activities and each licensee must monitor the balance of funds held to 
account for market variations. The licensee must replenish the funds, 
and report such actions to the NRC, as follows:
    (1) If, at the end of a calendar year, the fund balance is below the 
amount necessary to cover the cost of decommissioning, but is not below 
75 percent of the cost, the licensee must increase the balance to cover 
the cost, and must do so within 30 days after the end of the calendar 
year.
    (2) If, at any time, the fund balance falls below 75 percent of the 
amount necessary to cover the cost of decommissioning, the licensee must 
increase the balance to cover the cost, and must do so within 30 days of 
the occurrence.
    (3) Within 30 days of taking the actions required by paragraph 
(g)(1) or (g)(2) of this section, the licensee must provide a written 
report of such actions to the Director, Office of Nuclear Material 
Safety and Safeguards, and state the new balance of the fund.

[53 FR 31658, Aug. 19, 1988, as amended at 55 FR 29191, July 18, 1990; 
58 FR 39635, July 26, 1993; 58 FR 67662, Dec. 22, 1993; 58 FR 68732, 
Dec. 29, 1993; 59 FR 1618, Jan. 12, 1994; 61 FR 24675, May 16, 1996; 62 
FR 39092, July 21, 1997; 63 FR 29544, June 1, 1998; 66 FR 51840, Oct. 
11, 2001; 67 FR 78351, Dec. 24, 2002; 76 FR 35573, June 17, 2011; 79 FR 
75741 Dec. 19, 2014]



Sec. 72.32  Emergency Plan.

    (a) Each application for an ISFSI that is licensed under this part 
which is: Not located on the site of a nuclear power reactor, or not 
located within the exclusion area as defined in 10 CFR part 100 of a 
nuclear power reactor, or located on the site of a nuclear power reactor 
which does not have an operating license, or located on the site of

[[Page 412]]

a nuclear power reactor that is not authorized to operate must be 
accompanied by an Emergency Plan that includes the following 
information:
    (1) Facility description. A brief description of the licensee's 
facility and area near the site.
    (2) Types of accidents. An identification of each type of 
radioactive materials accident.
    (3) Classification of accidents. A classification system for 
classifying accidents as ``alerts.''
    (4) Detection of accidents. Identification of the means of detecting 
an accident condition.
    (5) Mitigation of consequences. A brief description of the means of 
mitigating the consequences of each type of accident, including those 
provided to protect workers onsite, and a description of the program for 
maintaining the equipment.
    (6) Assessment of releases. A brief description of the methods and 
equipment to assess releases of radioactive materials.
    (7) Responsibilities. A brief description of the responsibilities of 
licensee personnel should an accident occur, including identification of 
personnel responsible for promptly notifying offsite response 
organizations and the NRC; also responsibilities for developing, 
maintaining, and updating the plan.
    (8) Notification and coordination. A commitment to and a brief 
description of the means to promptly notify offsite response 
organizations and request offsite assistance, including medical 
assistance for the treatment of contaminated injured onsite workers when 
appropriate. A control point must be established. The notification and 
coordination must be planned so that unavailability of some personnel, 
parts of the facility, and some equipment will not prevent the 
notification and coordination. The licensee shall also commit to notify 
the NRC operations center immediately after notifications of the 
appropriate offsite response organizations and not later than one hour 
after the licensee declares an emergency. \10\
---------------------------------------------------------------------------

    \10\ These reporting requirements do not supersede or release 
licensees of complying with the requirements under the Emergency 
Planning and Community Right-to-Know Act of 1986, Title III, Pub. L. 99-
499 or other State or Federal reporting requirements.
---------------------------------------------------------------------------

    (9) Information to be communicated. A brief description of the types 
of information on facility status; radioactive releases; and recommended 
protective actions, if necessary, to be given to offsite response 
organizations and to the NRC.
    (10) Training. A brief description of the training the licensee will 
provide workers on how to respond to an emergency and any special 
instructions and orientation tours the licensee would offer to fire, 
police, medical and other emergency personnel.
    (11) Safe condition. A brief description of the means of restoring 
the facility to a safe condition after an accident.
    (12) Exercises. (i) Provisions for conducting semiannual 
communications checks with offsite response organizations and biennial 
onsite exercises to test response to simulated emergencies. 
Radiological/Health Physics, Medical, and Fire drills shall be conducted 
annually. Semiannual communications checks with offsite response 
organizations must include the check and update of all necessary 
telephone numbers. The licensee shall invite offsite response 
organizations to participate in the biennial exercise.
    (ii) Participation of offsite response organizations in biennial 
exercises, although recommended, is not required. Exercises must use 
scenarios not known to most exercise participants. The licensee shall 
critique each exercise using individuals not having direct 
implementation responsibility for conducting the exercise. Critiques of 
exercises must evaluate the appropriateness of the plan, emergency 
procedures, facilities, equipment, training of personnel, and overall 
effectiveness of the response. Deficiencies found by the critiques must 
be corrected.
    (13) Hazardous chemicals. A certification that the applicant has met 
its responsibilities under the Emergency Planning and Community Right-
to-Know Act of 1986, Title III, Pub. L. 99-499, with respect to 
hazardous materials at the facility.
    (14) Comments on Plan. The licensee shall allow the offsite response 
organizations expected to respond in case of

[[Page 413]]

an accident 60 days to comment on the initial submittal of the 
licensee's emergency plan before submitting it to NRC. Subsequent plan 
changes need not have the offsite comment period unless the plan changes 
affect the offsite response organizations. The licensee shall provide 
any comments received within the 60 days to the NRC with the emergency 
plan.
    (15) Offsite assistance. The applicant's emergency plans shall 
include a brief description of the arrangements made for requesting and 
effectively using offsite assistance on site and provisions that exist 
for using other organizations capable of augmenting the planned onsite 
response.
    (16) Arrangements made for providing information to the public.
    (b) Each application for an MRS that is licensed under this part and 
each application for an ISFSI that is licensed under this part and that 
may process and/or repackage spent fuel, must be accompanied by an 
Emergency Plan that includes the following information:
    (1) Facility description. A brief description of the licensee 
facility and area near the site.
    (2) Types of accidents. An identification of each type of 
radioactive materials accident.
    (3) Classification of accidents. A classification system for 
classifying accidents as ``alerts'' or ``site area emergencies.''
    (4) Detection of accidents. Identification of the means of detecting 
an accident condition.
    (5) Mitigation of consequences. A brief description of the means of 
mitigating the consequences of each type of accident, including those 
provided to protect workers on site, and a description of the program 
for maintaining the equipment.
    (6) Assessment of releases. A brief description of the methods and 
equipment to assess releases of radioactive materials.
    (7) Responsibilities. A brief description of the responsibilities of 
licensee personnel should an accident occur, including identification of 
personnel responsible for promptly notifying offsite response 
organizations and the NRC; also responsibilities for developing, 
maintaining, and updating the plan.
    (8) Notification and coordination. A commitment to and a brief 
description of the means to promptly notify offsite response 
organizations and request offsite assistance, including medical 
assistance for the treatment of contaminated injured onsite workers when 
appropriate. A control point must be established. The notification and 
coordination must be planned so that unavailability of some personnel, 
parts of the facility, and some equipment will not prevent the 
notification and coordination. The licensee shall also commit to notify 
the NRC operations center immediately after notifications of the 
appropriate offsite response organizations and not later than one hour 
after the licensee declares an emergency. \11\
---------------------------------------------------------------------------

    \11\ These reporting requirements do not supersede or release 
licensees of complying with the requirements under the Emergency 
Planning and Community Right-to-Know Act of 1986, Title III, Pub. L. 99-
499 or other State or Federal reporting requirements.
---------------------------------------------------------------------------

    (9) Information to be communicated. A brief description of the types 
of information on facility status; radioactive releases; and recommended 
protective actions, if necessary, to be given to offsite response 
organizations and to the NRC.
    (10) Training. A brief description of the training the licensee will 
provide workers on how to respond to an emergency and any special 
instructions and orientation tours the licensee would offer to fire, 
police, medical and other emergency personnel.
    (11) Safe condition. A brief description of the means of restoring 
the facility to a safe condition after an accident.
    (12) Exercises. (i) Provisions for conducting quarterly 
communications checks with offsite response organizations and biennial 
onsite exercises to test response to simulated emergencies. 
Radiological/Health Physics, Medical, and Fire Drills shall be held 
semiannually. Quarterly communications checks with offsite response 
organizations must include the check and update of all necessary 
telephone numbers. The licensee shall invite offsite response 
organizations to participate in the biennial exercises.

[[Page 414]]

    (ii) Participation of offsite response organizations in the biennial 
exercises, although recommended, is not required. Exercises must use 
scenarios not known to most exercise participants. The licensee shall 
critique each exercise using individuals not having direct 
implementation responsibility for conducting the exercise. Critiques of 
exercises must evaluate the appropriateness of the plan, emergency 
procedures, facilities, equipment, training of personnel, and overall 
effectiveness of the response. Deficiencies found by the critiques must 
be corrected.
    (13) Hazardous chemicals. A certification that the applicant has met 
its responsibilities under the Emergency Planning and Community Right-
to-Know Act of 1986, Title III, Pub. L. 99-499, with respect to 
hazardous materials at the facility.
    (14) Comments on Plan. The licensee shall allow the offsite response 
organizations expected to respond in case of an accident 60 days to 
comment on the initial submittal of the licensee's emergency plan before 
submitting it to NRC. Subsequent plan changes need not have the offsite 
comment period unless the plan changes affect the offsite response 
organizations. The licensee shall provide any comments received within 
the 60 days to the NRC with the emergency plan.
    (15) Offsite assistance. The applicant's emergency plans shall 
include the following:
    (i) A brief description of the arrangements made for requesting and 
effectively using offsite assistance on site and provisions that exist 
for using other organizations capable of augmenting the planned onsite 
response.
    (ii) Provisions that exist for prompt communications among principal 
response organizations to offsite emergency personnel who would be 
responding onsite.
    (iii) Adequate emergency facilities and equipment to support the 
emergency response onsite are provided and maintained.
    (iv) Adequate methods, systems, and equipment for assessing and 
monitoring actual or potential consequences of a radiological emergency 
condition are available.
    (v) Arrangements are made for medical services for contaminated and 
injured onsite individuals.
    (vi) Radiological Emergency Response Training has been made 
available to those offsite who may be called to assist in an emergency 
onsite.
    (16) Arrangements made for providing information to the public.
    (c) For an ISFSI that is:
    (1) located on the site, or
    (2) located within the exclusion area as defined in 10 CFR part 100, 
of a nuclear power reactor licensed for operation by the Commission, the 
emergency plan required by 10 CFR 50.47 shall be deemed to satisfy the 
requirements of this section.
    (d) A licensee with a license issued under this part may take 
reasonable action that departs from a license condition or a technical 
specification (contained in a license issued under this part) in an 
emergency when this action is immediately needed to protect the public 
health and safety and no action consistent with license conditions and 
technical specifications that can provide adequate or equivalent 
protection is immediately apparent.

[60 FR 32441, June 22, 1995]



Sec. 72.34  Environmental report.

    Each application for an ISFSI or MRS license under this part must be 
accompanied by an Environmental Report which meets the requirements of 
subpart A of part 51 of this chapter.



              Subpart C_Issuance and Conditions of License



Sec. 72.40  Issuance of license.

    (a) Except as provided in paragraph (c) of this section, the 
Commission will issue a license under this part upon a determination 
that the application for a license meets the standards and requirements 
of the Act and the regulations of the Commission, and upon finding that:
    (1) The applicant's proposed ISFSI or MRS design complies with 
subpart F;
    (2) The proposed site complies with the criteria in subpart E;
    (3) If on the site of a nuclear power plant or other licensed 
activity or facility, the proposed ISFSI would not

[[Page 415]]

pose an undue risk to the safe operation of such nuclear power plant or 
other licensed activity or facility;
    (4) The applicant is qualified by reason of training and experience 
to conduct the operation covered by the regulations in this part;
    (5) The applicant's proposed operating procedures to protect health 
and to minimize danger to life or property are adequate;
    (6) Except for DOE, the applicant for an ISFSI or MRS is financially 
qualified to engage in the proposed activities in accordance with the 
regulations in this part;
    (7) The applicant's quality assurance plan complies with subpart G;
    (8) The applicant's physical protection provisions comply with 
subpart H. DOE has complied with the safeguards and physical security 
provisions identified in Sec. 72.24(o);
    (9) The applicant's personnel training program complies with subpart 
I;
    (10) Except for DOE, the applicant's decommissioning plan and its 
financing pursuant to Sec. 72.30 provide reasonable assurance that the 
decontamination and decommissioning of the ISFSI or MRS at the end of 
its useful life will provide adequate protection to the health and 
safety of the public;
    (11) The applicant's emergency plan complies with Sec. 72.32;
    (12) The applicable provisions of part 170 of this chapter have been 
satisfied;
    (13) There is reasonable assurance that: (i) The activities 
authorized by the license can be conducted without endangering the 
health and safety of the public and (ii) these activities will be 
conducted in compliance with the applicable regulations of this chapter; 
and
    (14) The issuance of the license will not be inimical to the common 
defense and security.
    (b) A license to store spent fuel and reactor-related GTCC waste in 
the proposed ISFSI or to store spent fuel, high-level radioactive waste, 
and reactor-related GTCC waste in the proposed MRS may be denied if 
construction on the proposed facility begins before a finding approving 
issuance of the proposed license with any appropriate conditions to 
protect environmental values. Grounds for denial may be the commencement 
of construction prior to a finding by the Director, Office of Nuclear 
Materials Safety and Safeguards or designee or a finding after a public 
hearing by the presiding officer, Atomic Safety and Licensing Board, or 
the Commission acting as a collegial body, as appropriate, that the 
action called for is the issuance of the proposed license with any 
appropriate conditions to protect environmental values. This finding is 
to be made on the basis of information filed and evaluations made 
pursuant to subpart A of part 51 of this chapter or in the case of an 
MRS on the basis of evaluations made pursuant to sections 141(c) and (d) 
or 148(a) and (c) of NWPA (96 Stat. 2242, 2243, 42 U.S.C. 10161(c), (d); 
101 Stat. 1330-235, 1330-236, 42 U.S.C. 10168(a), (c)), as appropriate, 
and after weighing the environmental, economic, technical and other 
benefits against environmental costs and considering available 
alternatives.
    (c) For facilities that have been covered under previous licensing 
actions including the issuance of a construction permit under part 50 of 
this chapter, a reevaluation of the site is not required except where 
new information is discovered which could alter the original site 
evaluation findings. In this case, the site evaluation factors involved 
will be reevaluated.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51840, Oct. 11, 2001]



Sec. 72.42  Duration of license; renewal.

    (a) Each license issued under this part must be for a fixed period 
of time to be specified in the license. The license term for an ISFSI 
must not exceed 40 years from the date of issuance. The license term for 
an MRS must not exceed 40 years from the date of issuance. Licenses for 
either type of installation may be renewed by the Commission at the 
expiration of the license term upon application by the licensee for a 
period not to exceed 40 years and under the requirements of this rule. 
Application for ISFSI license renewals must include the following:
    (1) TLAAs that demonstrate that structures, systems, and components 
important to safety will continue to perform their intended function for 
the

[[Page 416]]

requested period of extended operation; and
    (2) A description of the AMP for management of issues associated 
with aging that could adversely affect structures, systems, and 
components important to safety.
    (b) Applications for renewal of a license should be filed in 
accordance with the applicable provisions of subpart B of this part at 
least 2 years before the expiration of the existing license. The 
application must also include design bases information as documented in 
the most recently updated FSAR as required by Sec. 72.70. Information 
contained in previous applications, statements, or reports filed with 
the Commission under the license may be incorporated by reference 
provided that these references are clear and specific.
    (c) In any case in which a licensee, not less than two years prior 
to expiration of its existing license, has filed an application in 
proper form for renewal of a license, the existing license shall not 
expire until a final decision concerning the application for renewal has 
been made by the Commission.

[53 FR 31658, Aug. 19, 1988, as amended at 76 FR 8890, Feb. 16, 2011]



Sec. 72.44  License conditions.

    (a) Each license issued under this part shall include license 
conditions. The license conditions may be derived from the analyses and 
evaluations included in the Safety Analysis Report and amendments 
thereto submitted pursuant to Sec. 72.24. License conditions pertain to 
design, construction and operation. The Commission may also include 
additional license conditions as it finds appropriate.
    (b) Each license issued under this part shall be subject to the 
following conditions, even if they are not explicitly stated therein;
    (1) Neither the license nor any right thereunder shall be 
transferred, assigned, or disposed of in any manner, either voluntarily 
or involuntarily, directly or indirectly, through transfer of control of 
the license to any person, unless the Commission shall, after securing 
full information, find that the transfer is in accordance with the 
provisions of the Atomic Energy Act of 1954, as amended, and give its 
consent in writing.
    (2) The license shall be subject to revocation, suspension, 
modification, or amendment in accordance with the procedures provided by 
the Atomic Energy Act of 1954, as amended, and Commission regulations.
    (3) Upon request of the Commission, the licensee shall, at any time 
before expiration of the license, submit written statements, signed 
under oath or affirmation if appropriate, to enable the Commission to 
determine whether or not the license should be modified, suspended, or 
revoked.
    (4) The licensee shall have an NRC-approved program in effect that 
covers the training and certification of personnel that meets the 
requirements of subpart I before the licensee may receive spent fuel 
and/or reactor-related GTCC waste for storage at an ISFSI or the receipt 
of spent fuel, high-level radioactive waste, and/or reactor-related GTCC 
waste for storage at an MRS.
    (5) The license shall permit the operation of the equipment and 
controls that are important to safety of the ISFSI or the MRS only by 
personnel whom the licensee has certified as being adequately trained to 
perform such operations, or by uncertified personnel who are under the 
direct visual supervision of a certified individual.
    (6)(i) Each licensee shall notify the appropriate NRC Regional 
Administrator, in writing, immediately following the filing of a 
voluntary or involuntary petition for bankruptcy under any Chapter of 
Title II (Bankruptcy) of the United States Code by or against:
    (A) The licensee;
    (B) An entity (as that term is defined in 11 U.S.C. 101(14)) 
controlling the licensee or listing the license or licensee as property 
of the estate; or
    (C) An affiliate (as that term is defined in 11 U.S.C. 101(2)) of 
the licensee.
    (ii) This notification must indicate:
    (A) The bankruptcy court in which the petition for bankruptcy was 
filed; and
    (B) The date of the filing of the petition.

[[Page 417]]

    (c) Each license issued under this part must include technical 
specifications. Technical specifications must include requirements in 
the following categories:
    (1) Functional and operating limits and monitoring instruments and 
limiting control settings. (i) Functional and operating limits for an 
ISFSI or MRS are limits on fuel or waste handling and storage conditions 
that are found to be necessary to protect the integrity of the stored 
fuel or waste container, to protect employees against occupational 
exposures and to guard against the uncontrolled release of radioactive 
materials; and
    (ii) Monitoring instruments and limiting control settings for an 
ISFSI or MRS are those related to fuel or waste handling and storage 
conditions having significant safety functions.
    (2) Limiting conditions. Limiting conditions are the lowest 
functional capability or performance levels of equipment required for 
safe operation.
    (3) Surveillance requirements. Surveillance requirements include:
    (i) Inspection and monitoring of spent fuel, high-level radioactive 
waste, or reactor-related GTCC waste in storage;
    (ii) Inspection, test and calibration activities to ensure that the 
necessary integrity of required systems and components is maintained;
    (iii) Confirmation that operation of the ISFSI or MRS is within the 
required functional and operating limits; and
    (iv) Confirmation that the limiting conditions required for safe 
storage are met.
    (4) Design features. Design features include items that would have a 
significant effect on safety if altered or modified, such as materials 
of construction and geometric arrangements.
    (5) Administrative controls. Administrative controls include the 
organization and management procedures, recordkeeping, review and audit, 
and reporting requirements necessary to assure that the operations 
involved in the storage of spent fuel and reactor-related GTCC waste in 
an ISFSI and the storage of spent fuel, high-level radioactive waste, 
and reactor-related GTCC waste in an MRS are performed in a safe manner.
    (d) Each license authorizing the receipt, handling, and storage of 
spent fuel, high-level radioactive waste, and/or reactor-related GTCC 
waste under this part must include technical specifications that, in 
addition to stating the limits on the release of radioactive materials 
for compliance with limits of part 20 of this chapter and the ``as low 
as is reasonably achievable'' objectives for effluents, require that:
    (1) Operating procedures for control of effluents be established and 
followed, and equipment in the radioactive waste treatment systems be 
maintained and used, to meet the requirements of Sec. 72.104;
    (2) An environmental monitoring program be established to ensure 
compliance with the technical specifications for effluents; and
    (3) An annual report be submitted to the Commission in accordance 
with Sec. 72.4, specifying the quantity of each of the principal 
radionuclides released to the environment in liquid and in gaseous 
effluents during the previous 12 months of operation and such other 
information as may be required by the Commission to estimate maximum 
potential radiation dose commitment to the public resulting from 
effluent releases. On the basis of this report and any additional 
information that the Commission may obtain from the licensee or others, 
the Commission may from time to time require the licensee to take such 
action as the Commission deems appropriate. The report must be submitted 
within 60 days after the end of the 12-month monitoring period.
    (e) The licensee shall make no change that would decrease the 
effectiveness of the physical security plan prepared pursuant to Sec. 
72.180 without the prior approval of the Commission. A licensee desiring 
to make such a change shall submit an application for an amendment to 
the license pursuant to Sec. 72.56. A licensee may make changes to the 
physical security plan without prior Commission approval, provided that 
such changes do not decrease the effectiveness of the plan. The licensee 
shall furnish to the Commission a report containing a description of 
each change within two months after the

[[Page 418]]

change is made, and shall maintain records of changes to the plan made 
without prior Commission approval for a period of 3 years from the date 
of the change.
    (f) A licensee shall follow and maintain in effect an emergency plan 
that is approved by the Commission. The licensee may make changes to the 
approved plan without Commission approval only if such changes do not 
decrease the effectiveness of the plan. Within six months after any 
change is made, the licensee shall submit, in accordance with Sec. 
72.4, a report containing a description of any changes made in the plan 
addressed to Director, Division of Spent Fuel Management, Office of 
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory 
Commission, with a copy to the appropriate NRC Regional Office shown in 
appendix D to part 20 of this chapter. Proposed changes that decrease 
the effectiveness of the approved emergency plan must not be implemented 
unless the licensee has received prior approval of such changes from the 
Commission.
    (g) A license issued to DOE under this part for an MRS authorized by 
section 142(b) of NWPA (101 Stat. 1330-232, 42 U.S.C. 10162(b)) must 
include the following conditions:
    (1) Construction of the MRS may not begin until the Commission has 
authorized the construction of a repository under section 114(d) of NWPA 
(96 Stat. 2215, as amended by 101 Stat. 1330-230, 42 U.S.C. 10134 (d)) 
and part 60 or 63 of this chapter;
    (2) Construction of the MRS or acceptance of spent nuclear fuel, 
high-level radioactive waste, and/or reactor-related GTCC waste at the 
MRS is prohibited during such time as the repository license is revoked 
by the Commission or construction of the repository ceases.
    (3) The quantity of spent nuclear fuel or high-level radioactive 
waste at the site of the MRS at any one time may not exceed 10,000 
metric tons of heavy metal until a repository authorized under NWPA and 
part 60 or 63 of this chapter first accepts spent nuclear fuel or 
solidified high-level radioactive waste; and
    (4) The quantity of spent nuclear fuel or high-level radioactive 
waste at the site of the MRS at any one time may not exceed 15,000 
metric tons of heavy metal.
    (h) Each licensee shall protect Safeguards Information against 
unauthorized disclosure in accordance with the requirements of Sec. 
73.21 and the requirements of Sec. 73.22 or Sec. 73.23, as applicable.

[53 FR 31658, Aug. 19, 1988, as amended at 64 FR 33183, June 22, 1999; 
66 FR 51840, Oct. 11, 2001; 66 FR 55815, Nov. 2, 2001; 67 FR 3586, Jan. 
25, 2002; 68 FR 58819, Oct. 10, 2003; 73 FR 63573, Oct. 24, 2008; 75 FR 
73945, Nov. 30, 2010; 79 FR 75741, Dec. 19, 2014]



Sec. 72.46  Public hearings.

    (a) In connection with each application for a license under this 
part, the Commission shall issue or cause to be issued a notice of 
proposed action and opportunity for hearing in accordance with Sec. 
2.105 or Sec. 2.1107 of this chapter, as appropriate, or, if the 
Commission finds that a hearing is required in the public interest, a 
notice of hearing in accordance with Sec. 2.104 of this chapter.
    (b)(1) In connection with each application for an amendment to a 
license under this part, the Commission shall, except as provided in 
paragraph (b)(2) of this section, issue or cause to be issued a notice 
of proposed action and opportunity for hearing in accordance with Sec. 
2.105 or Sec. 2.1107 of this chapter, as appropriate, or, if the 
Commission finds that a hearing is required in the public interest, a 
notice of hearing in accordance with Sec. 2.104 of this chapter.
    (2) The Director, Office of Nuclear Material Safety and Safeguards, 
or the Director's designee may dispense with a notice of proposed action 
and opportunity for hearing or a notice of hearing and take immediate 
action on an amendment to a license issued under this part upon a 
determination that the amendment does not present a genuine issue as to 
whether the health and safety of the public will be significantly 
affected. After taking the action, the Director or the Director's 
designee shall promptly publish a notice in the Federal Register of the 
action taken and of the right of interested persons to request a hearing 
on whether the action should be rescinded or modified. If the action 
taken amends

[[Page 419]]

an MRS license, the Director or the Director's designee shall also 
inform the appropriate State and local officials.
    (c) The notice of proposed action and opportunity for hearing or the 
notice of hearing may be included in the notice of docketing required to 
be published by Sec. 72.16 of this part.
    (d) If no request for a hearing or petition for leave to intervene 
is filed within the time prescribed in the notice of proposed action and 
opportunity for hearing, the Director, Office of Nuclear Material Safety 
and Safeguards or the Director's designee may take the proposed action, 
and thereafter shall promptly inform the appropriate State and local 
officials and publish a notice in the Federal Register of the action 
taken. In accordance with Sec. 2.764(c) of this chapter, the Director, 
Office of Nuclear Material Safety and Safeguards shall not issue an 
initial license for the construction and operation of an ISFSI located 
at a site other than a reactor site or an MRS until expressly authorized 
to do so by the Commission.
    (e) If an application for (or an amendment to) a specific license 
issued under this part incorporates by reference information on the 
design of a spent fuel storage cask for which NRC approval pursuant to 
subpart L of this part has been issued or is being sought, the scope of 
any public hearing held to consider the application will not include any 
cask design issues.

[53 FR 31658, Aug. 19, 1988, as amended at 60 FR 20886, Apr. 28, 1995; 
65 FR 50617, Aug. 21, 2000]



Sec. 72.48  Changes, tests, and experiments.

    (a) Definitions for the purposes of this section:
    (1) Change means a modification or addition to, or removal from, the 
facility or spent fuel storage cask design or procedures that affects a 
design function, method of performing or controlling the function, or an 
evaluation that demonstrates that intended functions will be 
accomplished.
    (2) Departure from a method of evaluation described in the FSAR (as 
updated) used in establishing the design bases or in the safety analyses 
means:
    (i) Changing any of the elements of the method described in the FSAR 
(as updated) unless the results of the analysis are conservative or 
essentially the same; or
    (ii) Changing from a method described in the FSAR to another method 
unless that method has been approved by NRC for the intended 
application.
    (3) Facility means either an independent spent fuel storage 
installation (ISFSI) or a Monitored Retrievable Storage facility (MRS).
    (4) The facility or spent fuel storage cask design as described in 
the Final Safety Analysis Report (FSAR) (as updated) means:
    (i) The structures, systems, and components (SSC) that are described 
in the FSAR (as updated),
    (ii) The design and performance requirements for such SSCs described 
in the FSAR (as updated), and
    (iii) The evaluations or methods of evaluation included in the FSAR 
(as updated) for such SSCs which demonstrate that their intended 
function(s) will be accomplished.
    (5) Final Safety Analysis Report (as updated) means:
    (i) For specific licensees, the Safety Analysis Report for a 
facility submitted and updated in accordance with Sec. 72.70;
    (ii) For general licensees, the Safety Analysis Report for a spent 
fuel storage cask design, as amended and supplemented; and
    (iii) For certificate holders, the Safety Analysis Report for a 
spent fuel storage cask design submitted and updated in accordance with 
Sec. 72.248.
    (6) Procedures as described in the Final Safety Analysis Report (as 
updated) means those procedures that contain information described in 
the FSAR (as updated) such as how SSCs are operated and controlled 
(including assumed operator actions and response times).
    (7) Tests or experiments not described in the Final Safety Analysis 
Report (as updated) means any activity where any SSC is utilized or 
controlled in a manner which is either:
    (i) Outside the reference bounds of the design bases as described in 
the FSAR (as updated) or
    (ii) Inconsistent with the analyses or descriptions in the FSAR (as 
updated).
    (b) This section applies to:

[[Page 420]]

    (1) Each holder of a general or specific license issued under this 
part, and
    (2) Each holder of a Certificate of Compliance (CoC) issued under 
this part.
    (c)(1) A licensee or certificate holder may make changes in the 
facility or spent fuel storage cask design as described in the FSAR (as 
updated), make changes in the procedures as described in the FSAR (as 
updated), and conduct tests or experiments not described in the FSAR (as 
updated), without obtaining either:
    (i) A license amendment pursuant to Sec. 72.56 (for specific 
licensees) or
    (ii) A CoC amendment submitted by the certificate holder pursuant to 
Sec. 72.244 (for general licensees and certificate holders) if:
    (A) A change to the technical specifications incorporated in the 
specific license is not required; or
    (B) A change in the terms, conditions, or specifications 
incorporated in the CoC is not required; and
    (C) The change, test, or experiment does not meet any of the 
criteria in paragraph (c)(2) of this section.
    (2) A specific licensee shall obtain a license amendment pursuant to 
Sec. 72.56, a certificate holder shall obtain a CoC amendment pursuant 
to Sec. 72.244, and a general licensee shall request that the 
certificate holder obtain a CoC amendment pursuant to Sec. 72.244, 
prior to implementing a proposed change, test, or experiment if the 
change, test, or experiment would:
    (i) Result in more than a minimal increase in the frequency of 
occurrence of an accident previously evaluated in the FSAR (as updated);
    (ii) Result in more than a minimal increase in the likelihood of 
occurrence of a malfunction of a system, structure, or component (SSC) 
important to safety previously evaluated in the FSAR (as updated);
    (iii) Result in more than a minimal increase in the consequences of 
an accident previously evaluated in the FSAR (as updated);
    (iv) Result in more than a minimal increase in the consequences of a 
malfunction of an SSC important to safety previously evaluated in the 
FSAR (as updated);
    (v) Create a possibility for an accident of a different type than 
any previously evaluated in the FSAR (as updated);
    (vi) Create a possibility for a malfunction of an SSC important to 
safety with a different result than any previously evaluated in the FSAR 
(as updated);
    (vii) Result in a design basis limit for a fission product barrier 
as described in the FSAR (as updated) being exceeded or altered; or
    (viii) Result in a departure from a method of evaluation described 
in the FSAR (as updated) used in establishing the design bases or in the 
safety analyses.
    (3) In implementing this paragraph, the FSAR (as updated) is 
considered to include FSAR changes resulting from evaluations performed 
pursuant to this section and analyses performed pursuant to Sec. 72.56 
or Sec. 72.244 since the last update of the FSAR pursuant to Sec. 
72.70, or Sec. 72.248 of this part.
    (4) The provisions in this section do not apply to changes to the 
facility or procedures when the applicable regulations establish more 
specific criteria for accomplishing such changes.
    (d)(1) The licensee and certificate holder shall maintain records of 
changes in the facility or spent fuel storage cask design, of changes in 
procedures, and of tests and experiments made pursuant to paragraph (c) 
of this section. These records must include a written evaluation which 
provides the bases for the determination that the change, test, or 
experiment does not require a license or CoC amendment pursuant to 
paragraph (c)(2) of this section.
    (2) The licensee and certificate holder shall submit, as specified 
in Sec. 72.4, a report containing a brief description of any changes, 
tests, and experiments, including a summary of the evaluation of each. A 
report shall be submitted at intervals not to exceed 24 months.
    (3) The records of changes in the facility or spent fuel storage 
cask design shall be maintained until:
    (i) Spent fuel is no longer stored in the facility or the spent fuel 
storage cask design is no longer being used, or

[[Page 421]]

    (ii) The Commission terminates the license or CoC issued pursuant to 
this part.
    (4) The records of changes in procedures and of tests and 
experiments shall be maintained for a period of 5 years.
    (5) The holder of a spent fuel storage cask design CoC, who 
permanently ceases operation, shall provide the records of changes to 
the new certificate holder or to the Commission, as appropriate, in 
accordance with Sec. 72.234(d)(3).
    (6)(i) A general licensee shall provide a copy of the record for any 
changes to a spent fuel storage cask design to the applicable 
certificate holder within 60 days of implementing the change.
    (ii) A specific licensee using a spent fuel storage cask design, 
approved pursuant to subpart L of this part, shall provide a copy of the 
record for any changes to a spent fuel storage cask design to the 
applicable certificate holder within 60 days of implementing the change.
    (iii) A certificate holder shall provide a copy of the record for 
any changes to a spent fuel storage cask design to any general or 
specific licensee using the cask design within 60 days of implementing 
the change.

[64 FR 53615, Oct. 4, 1999, as amended at 66 FR 11527, Feb. 26, 2001]



Sec. 72.50  Transfer of license.

    (a) No license or any part included in a license issued under this 
part for an ISFSI or MRS shall be transferred, assigned, or in any 
manner disposed of, either voluntarily or involuntarily, directly or 
indirectly, through transfer of control of the license to any person, 
unless the Commission gives its consent in writing.
    (b)(1) An application for transfer of a license must include as much 
of the information described in Sec. Sec. 72.22 and 72.28 with respect 
to the identity and the technical and financial qualifications of the 
proposed transferee as would be required by those sections if the 
application were for an initial license. The application must also 
include a statement of the purposes for which the transfer of the 
license is requested and the nature of the transaction necessitating or 
making desirable the transfer of the license.
    (2) The Commission may require any person who submits an application 
for the transfer of a license pursuant to the provisions of this section 
to file a written consent from the existing licensee, or a certified 
copy of an order or judgment of a court of competent jurisdiction, 
attesting to the person's right--subject to the licensing requirements 
of the Act and these regulations--to possession of the radioactive 
materials and the storage installation involved.
    (3) The application shall describe the financial assurance that will 
be provided for the decommissioning of the facility under Sec. 72.30.
    (c) After appropriate notice to interested persons, including the 
existing licensee, and observance of such procedures as may be required 
by the Act or regulations or orders of the Commission, the Commission 
will approve an application for the transfer of a license, if the 
Commission determines that:
    (1) The proposed transferee is qualified to be the holder of the 
license; and
    (2) Transfer of the license is consistent with applicable provisions 
of the law, and the regulations and orders issued by the Commission.

[53 FR 31658, Aug. 19, 1988, as amended at 76 FR 35574, June 17, 2011]



Sec. 72.52  Creditor regulations.

    (a) This section does not apply to an ISFSI or MRS constructed and 
operated by DOE.
    (b) Pursuant to section 184 of the Act, the Commission consents, 
without individual application, to the creation of any mortgage, pledge, 
or other lien on special nuclear material contained in spent fuel not 
owned by the United States that is the subject of a license or on any 
interest in special nuclear material in spent fuel; Provided:
    (1) That the rights of any creditor so secured may be exercised only 
in compliance with and subject to the same requirements and restrictions 
as would apply to the licensee pursuant to the provisions of the 
license, the Atomic Energy Act of 1954, as amended, and regulations 
issued by the Commission pursuant to said Act; and

[[Page 422]]

    (2) That no creditor so secured may take possession of the spent 
fuel and/or reactor-related GTCC waste under the provisions of this 
section before--
    (i) The Commission issues a license authorizing possession; or
    (ii) The license is transferred.
    (c) Any creditor so secured may apply for transfer of the license 
covering spent fuel and/or reactor-related GTCC waste by filing an 
application for transfer of the license under Sec. 72.50(b). The 
Commission will act upon the application under Sec. 72.50(c).
    (d) Nothing contained in this regulation shall be deemed to affect 
the means of acquiring, or the priority of, any tax lien or other lien 
provided by law.
    (e) As used in this section, ``creditor'' includes, without implied 
limitation--
    (1) The trustee under any mortgage, pledge, or lien on spent fuel 
and/or reactor-related GTCC waste in storage made to secure any 
creditor;
    (2) Any trustee or receiver of spent fuel and/or reactor-related 
GTCC waste appointed by a court of competent jurisdiction in any action 
brought for the benefit of any creditor secured by a mortgage, pledge, 
or lien;
    (3) Any purchaser of the spent fuel and/or reactor-related GTCC 
waste at the sale thereof upon foreclosure of the mortgage, pledge, or 
lien or upon exercise of any power of sale contained therein; or
    (4) Any assignee of any such purchaser.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51840, Oct. 11, 2001]



Sec. 72.54  Expiration and termination of licenses and decommissioning
of sites and separate buildings or outdoor areas.

    (a) Each specific license expires at the end of the day on the 
expiration date stated in the license except when a licensee has filed 
an application for renewal pursuant to Sec. 72.42 not less than 24 
months before the expiration of the existing license. If an application 
for renewal has been filed at least 24 months prior to the expiration 
date stated in the existing license, the existing license expires at the 
end of the day on which the Commission makes a final determination to 
deny the renewal application or, if the determination states an 
expiration date, the expiration date stated in the determination.
    (b) Each specific license revoked by the Commission expires at the 
end of the day on the date of the Commission's final determination to 
revoke the license or on the expiration date stated in the determination 
or as otherwise provided by Commission Order.
    (c) Each specific license continues in effect, beyond the expiration 
date if necessary, with respect to possession of licensed material until 
the Commission notifies the licensee in writing that the license is 
terminated. During this time, the licensee shall--
    (1) Limit actions involving spent fuel, reactor-related GTCC waste, 
or other licensed material to those related to decommissioning; and
    (2) Continue to control entry to restricted areas until they are 
suitable for release in accordance with NRC requirements.
    (d) As required by Sec. 72.42(b), or within 60 days of the 
occurrence of any of the following, consistent with the administrative 
directions in Sec. 72.4, each licensee shall notify the NRC in writing, 
and submit within 12 months of this notification, a final 
decommissioning plan and begin decommissioning upon approval of the plan 
if--
    (1) The licensee has decided to permanently cease principal 
activities, as defined in this part, at the entire site or any separate 
building or outdoor area that contains residual radioactivity such that 
the building or outdoor area is unsuitable for release in accordance 
with NRC requirements; or
    (2) No principal activities under the license have been conducted 
for a period of 24 months; or
    (3) No principal activities have been conducted for a period of 24 
months in any separate building or outdoor area that contains residual 
radioactivity such that the building or outdoor area is unsuitable for 
release in accordance with NRC requirements.
    (e) Coincident with the notification required by paragraph (d) of 
this section, the licensee shall maintain in effect all decommissioning 
financial assurances established by the licensee pursuant to Sec. 72.30 
in conjunction with

[[Page 423]]

a license issuance or renewal or as required by this section. The amount 
of the financial assurance must be increased, or may be decreased, as 
appropriate, to cover the detailed cost estimate for decommissioning 
established pursuant to paragraph (g)(5) of this section.
    (1) Any licensee who has not provided financial assurance to cover 
the detailed cost estimate submitted with the decommissioning plan shall 
do so when this rule becomes effective November 24, 1995.
    (2) Following approval of the decommissioning plan, a licensee may 
reduce the amount of the financial assurance as decommissioning proceeds 
and radiological contamination is reduced at the site with the approval 
of the Commission.
    (f)(1) The Commission may grant a request to delay or postpone 
initiation of the decommissioning process if the Commission determines 
that this relief is not detrimental to the public health and safety and 
is otherwise in the public interest. The request must be submitted no 
later than 30 days before notification pursuant to paragraph (d) of this 
section. The schedule for decommissioning set forth in paragraph (d) of 
this section may not commence until the Commission has made a 
determination on the request.
    (2) The Commission may approve an alternate schedule for submittal 
of the final decommissioning plan required pursuant to paragraph (d) of 
this section if the Commission determines that the alternate schedule is 
necessary to the effective conduct of decommissioning operations and 
presents no undue risk from radiation to the public health and safety, 
and is otherwise to the public interest.
    (g) The proposed final decommissioning plan must include--
    (1) A description of the current conditions of the site or separate 
building or outdoor area sufficient to evaluate the acceptability of the 
plan;
    (2) The choice of the alternative for decommissioning with a 
description of the activities involved;
    (3) A description of controls and limits on procedures and equipment 
to protect occupational and public health and safety;
    (4) A description of the planned final radiation survey; and
    (5) An updated detailed cost estimate for the chosen alternative for 
decommissioning, comparison of that estimate with present funds set 
aside for decommissioning, and plan for assuring the availability of 
adequate funds for completion of decommissioning including means for 
adjusting cost estimates and associated funding levels over any storage 
or surveillance period; and
    (6) A description of technical specifications and quality assurance 
provisions in place during decommissioning.
    (h) For final decommissioning plans in which the major dismantlement 
activities are delayed by first placing the ISFSI or MRS in storage, 
planning for these delayed activities may be less detailed. Updated 
detailed plans must be submitted and approved prior to the start of 
these activities.
    (i) If the final decommissioning plan demonstrates that the 
decommissioning will be completed as soon as practicable, performed in 
accordance with the regulations in this chapter, and will not be 
inimical to the common defense and security or to the health and safety 
of the public, and after notice to interested persons, the Commission 
will approve the plan subject to any appropriate conditions and 
limitations and issue an order authorizing decommissioning.
    (j)(1) Except as provided in paragraph (k) of this section, each 
licensee shall complete decommissioning of the site or separate building 
or outdoor area as soon as practicable but no later than 24 months 
following approval of the final decommissioning plan by the Commission.
    (2) Except as provided in paragraph (k) of this section, when 
decommissioning involves the entire site, each licensee shall request 
license termination as soon as practicable but no later than 24 months 
following approval of the final decommissioning plan by the Commission.
    (k) The Commission may approve a request for an alternate schedule 
for completion of decommissioning of the site or separate building or 
outdoor area, and license termination if appropriate, if the Commission 
determines

[[Page 424]]

that the alternate schedule is warranted by consideration of the 
following:
    (1) Whether it is technically feasible to complete decommissioning 
within the allotted 24-month period;
    (2) Whether sufficient waste disposal capacity is available to allow 
completion of decommissioning within the allotted 24-month period;
    (3) Whether a significant volume reduction in wastes requiring 
disposal will be achieved by allowing short-lived radionuclides to 
decay;
    (4) Whether a significant reduction in radiation exposure to workers 
can be achieved by allowing short-lived radionuclides to decay; and
    (5) Other site-specific factors that the Commission may consider 
appropriate on a case-by-case basis, such as regulatory requirements of 
other government agencies, lawsuits, groundwater treatment activities, 
monitored natural groundwater restoration, actions that could result in 
more environmental harm than deferred cleanup, and other factors beyond 
the control of the licensee.
    (l) As the final step in decommissioning, the licensee shall--
    (1) Certify the disposition of all licensed material, including 
accumulated wastes, by submitting a completed NRC Form 314 or equivalent 
information; and
    (2) Conduct a radiation survey of the premises where the licensed 
activities were conducted and submit a report of the results of this 
survey, unless the licensee demonstrates in some other manner that the 
premises are suitable for release in accordance with the criteria for 
decommissioning in 10 CFR part 20, subpart E. The licensee shall, as 
appropriate--
    (i) Report levels of gamma radiation in units of millisieverts 
(microroentgen) per hour at one meter from surfaces, and report levels 
of radioactivity, including alpha and beta, in units of megabecquerels 
(disintegrations per minute or microcuries) per 100 square centimeters 
removable and fixed for surfaces, megabecquerels (microcuries) per 
milliliter for water, and becquerels (picocuries) per gram for solids 
such as soils or concrete; and
    (ii) Specify the survey instrument(s) used and certify that each 
instrument is properly calibrated and tested.
    (m) Specific licenses, including expired licenses, will be 
terminated by written notice to the licensee when the Commission 
determines that--
    (1) The decommissioning has been performed in accordance with the 
approved final decommissioning plan and the order authorizing 
decommissioning; and
    (2)(i) A radiation survey has been performed which demonstrates that 
the premises are suitable for release in accordance with the criteria 
for decommissioning in 10 CFR part 20, subpart E; or
    (ii) Other information submitted by the licensee is sufficient to 
demonstrate that the premises are suitable for release in accordance 
with the criteria for decommissioning in 10 CFR part 20, subpart E.
    (3) Records required by Sec. 72.80(e) have been received.

[59 FR 36038, July 15, 1994, as amended at 60 FR 38240, July 26, 1995; 
61 FR 24675, May 16, 1996; 61 FR 29638, June 12, 1996; 62 FR 39092, July 
21, 1997; 62 FR 59276, Nov. 3, 1997; 66 FR 51840, Oct. 11, 2001]



Sec. 72.56  Application for amendment of license.

    Whenever a holder of a specific license desires to amend the license 
(including a change to the license conditions), an application for an 
amendment shall be filed with the Commission fully describing the 
changes desired and the reasons for such changes, and following as far 
as applicable the form prescribed for original applications.

[64 FR 53616, Oct. 4, 1999]



Sec. 72.58  Issuance of amendment.

    In determining whether an amendment to a license will be issued to 
the applicant, the Commission will be guided by the considerations that 
govern the issuance of initial licenses.



Sec. 72.60  Modification, revocation, and suspension of license.

    (a) The terms and conditions of all licenses are subject to 
amendment, revision, or modification by reason of amendments to the 
Atomic Energy Act

[[Page 425]]

of 1954, as amended, or by reason or rules, regulations, or orders 
issued in accordance with the Act or any amendments thereto.
    (b) Any license may be modified, revoked, or suspended in whole or 
in part for any of the following:
    (1) Any material false statement in the application or in any 
statement of fact required under section 182 of the Act;
    (2) Conditions revealed by the application or statement of fact or 
any report, record, inspection or other means which would warrant the 
Commission to refuse to grant a license on an original application;
    (3) Failure to operate an ISFSI or MRS in accordance with the terms 
of the license;
    (4) Violation of, or failure to observe, any of the terms and 
conditions of the Act, or of any applicable regulation, license, or 
order of the Commission.
    (c) Upon revocation of a license, the Commission may immediately 
cause the retaking of possession of all special nuclear material 
contained in spent fuel and/or reactor-related GTCC waste held by the 
licensee. In cases found by the Commission to be of extreme importance 
to the national defense and security or to the health and safety of the 
public, the Commission may cause the taking of possession of any special 
nuclear material contained in spent fuel and/or reactor-related GTCC 
waste held by the licensee before following any of the procedures 
provided under sections 551-558 of title 5 of the United States Code.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51841, Oct. 11, 2001]



Sec. 72.62  Backfitting.

    (a) As used in this section, backfitting means the addition, 
elimination, or modification, after the license has been issued, of:
    (1) Structures, systems, or components of an ISFSI or MRS, or
    (2) Procedures or organization required to operate an ISFSI or MRS.
    (b) The Commission will require backfitting of an ISFSI or MRS if it 
finds that such action is necessary to assure adequate protection to 
occupational or public health and safety, or to bring the ISFSI or MRS 
into compliance with a license or the rules or orders of the Commission, 
or into conformance with written commitments by a licensee.
    (c) The Commission may require the backfitting of an ISFSI or MRS if 
it finds:
    (1) That there is a substantial increase in the overall protection 
of the occupational or public health and safety to be derived from the 
backfit, and
    (2) That the direct and indirect costs of implementation for that 
ISFSI or MRS are justified in view of this increased protection.
    (d) The Commission may at any time require a holder of a license to 
submit such information concerning the backfitting or the proposed 
backfitting of an ISFSI or MRS as it deems appropriate.



        Subpart D_Records, Reports, Inspections, and Enforcement



Sec. 72.70  Safety analysis report updating.

    (a) Each specific licensee for an ISFSI or MRS shall update 
periodically, as provided in paragraphs (b) and (c) of this section, the 
final safety analysis report (FSAR) to assure that the information 
included in the report contains the latest information developed.
    (1) Each licensee shall submit an original FSAR to the Commission, 
in accordance with Sec. 72.4, within 90 days after issuance of the 
license.
    (2) The original FSAR shall be based on the safety analysis report 
submitted with the application and reflect any changes and applicant 
commitments developed during the license approval and/or hearing 
process.
    (b) Each update shall contain all the changes necessary to reflect 
information and analyses submitted to the Commission by the licensee or 
prepared by the licensee pursuant to Commission requirement since the 
submission of the original FSAR or, as appropriate, the last update to 
the FSAR under this section. The update shall include the effects \1\ 
of:
---------------------------------------------------------------------------

    \1\ Effects of changes includes appropriate revisions of 
descriptions in the FSAR such that the FSAR (as updated) is complete and 
accurate.

---------------------------------------------------------------------------

[[Page 426]]

    (1) All changes made in the ISFSI or MRS or procedures as described 
in the FSAR;
    (2) All safety analyses and evaluations performed by the licensee 
either in support of approved license amendments, or in support of 
conclusions that changes did not require a license amendment in 
accordance with Sec. 72.48;
    (3) All final analyses and evaluations of the design and performance 
of structures, systems, and components that are important to safety 
taking into account any pertinent information developed during final 
design, construction, and preoperational testing; and
    (4) All analyses of new safety issues performed by or on behalf of 
the licensee at Commission request. The information shall be 
appropriately located within the updated FSAR.
    (c)(1) The update of the FSAR must be filed in accordance with Sec. 
72.4. If the update is filed on paper, it should be filed on a page-
replacement basis; if filed electronically, it should be filed on a full 
replacement basis. See Guidance for Electronic Submissions to the 
Commission at http://www.nrc.gov/site-help/e-submittals.html.
    (2) A paper update filed on a page-replacement basis must include a 
list that identifies the current pages of the FSAR following page 
replacement. If the update is filed electronically on a full replacement 
basis, it must include a list of changed pages.
    (3) Each replacement page shall include both a change indicator for 
the area changed, e.g., a bold line vertically drawn in the margin 
adjacent to the portion actually changed, and a page change 
identification (date of change or change number or both);
    (4) The update shall include:
    (i) A certification by a duly authorized officer of the licensee 
that either the information accurately presents changes made since the 
previous submittal, or that no such changes were made; and
    (ii) An identification of changes made under the provisions of Sec. 
72.48, but not previously submitted to the Commission;
    (5) The update shall reflect all changes implemented up to a maximum 
of 6 months prior to the date of filing; and
    (6) Updates shall be filed every 24 months from the date of issuance 
of the license.
    (d) The updated FSAR shall be retained by the licensee until the 
Commission terminates the license.

[64 FR 53616, Oct. 4, 1999, as amended at 68 FR 58819, Oct. 10, 2003; 74 
FR 62684, Dec. 1, 2009]



Sec. 72.72  Material balance, inventory, and records requirements 
for stored materials.

    (a) Each licensee shall keep records showing the receipt, inventory 
(including location), disposal, acquisition, and transfer of all special 
nuclear material with quantities as specified in Sec. 74.13(a) of this 
chapter and for source material as specified in Sec. 40.64 of this 
chapter. The records must include as a minimum the name of shipper of 
the material to the ISFSI or MRS, the estimated quantity of radioactive 
material per item (including special nuclear material in spent fuel and 
reactor-related GTCC waste), item identification and seal number, 
storage location, onsite movements of each fuel assembly or storage 
canister, and ultimate disposal. These records for spent fuel and 
reactor-related GTCC waste at an ISFSI or for spent fuel, high-level 
radioactive waste, and reactor-related GTCC waste at an MRS must be 
retained for as long as the material is stored and for a period of 5 
years after the material is disposed of or transferred out of the ISFSI 
or MRS.
    (b) Each licensee shall conduct a physical inventory of all spent 
fuel, high-level radioactive waste, and reactor-related GTCC waste 
containing special nuclear material meeting the requirements in 
paragraph (a) of this section at intervals not to exceed 12 months 
unless otherwise directed by the Commission. The licensee shall retain a 
copy of the current inventory as a record until the Commission 
terminates the license.
    (c) Each licensee shall establish, maintain, and follow written 
material control and accounting procedures that are sufficient to enable 
the licensee to

[[Page 427]]

account for material in storage. The licensee shall retain a copy of the 
current material control and accounting procedures until the Commission 
terminates the license.
    (d) Records of spent fuel, high-level radioactive waste, and 
reactor-related GTCC waste containing special nuclear material meeting 
the requirements in paragraph (a) of this section must be kept in 
duplicate. The duplicate set of records must be kept at a separate 
location sufficiently remote from the original records that a single 
event would not destroy both sets of records. Records of spent fuel or 
reactor-related GTCC waste containing special nuclear material 
transferred out of an ISFSI or of spent fuel, high-level radioactive 
waste, or reactor-related GTCC waste containing special nuclear material 
transferred out of an MRS must be preserved for a period of five years 
after the date of transfer.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51841, Oct. 11, 2001; 
73 FR 32462, June 9, 2008]



Sec. 72.74  Reports of accidental criticality or loss of special
nuclear material.

    (a) Each licensee shall notify the NRC Operations Center \1\ within 
one hour of discovery of accidental criticality or any loss of special 
nuclear material.
---------------------------------------------------------------------------

    \1\ Commercial telephone number of the NRC Operations Center is 
(301) 816-5100.
---------------------------------------------------------------------------

    (b) This notification must be made to the NRC Operations Center via 
the Emergency Notification System if the licensee is party to that 
system. If the Emergency Notification System is inoperative or 
unavailable, the licensee shall make the required notification via 
commercial telephonic service or any other dedicated telephonic system 
or any other method that will ensure that a report is received by the 
NRC Operations Center within one hour. The exemption of Sec. 
73.22(f)(3) of this chapter applies to all telephonic reports required 
by this section.
    (c) Reports required under Sec. 73.71 of this chapter need not be 
duplicated under the requirements of this section.

[53 FR 31658, Aug. 19, 1988, as amended at 59 FR 14087, Mar. 25, 1994, 
81 FR 86910, Dec. 2, 2016]



Sec. 72.75  Reporting requirements for specific events and conditions.

    (a) Emergency notifications: Each licensee shall notify the NRC 
Headquarters Operations Center upon the declaration of an emergency as 
specified in the licensee's approved emergency plan addressed in Sec. 
72.32. The licensee shall notify the NRC immediately after notification 
of the appropriate State or local agencies, but not later than one hour 
after the time the licensee declares an emergency.
    (b) Non-emergency notifications: Four-hour reports. Each licensee 
shall notify the NRC as soon as possible but not later than four hours 
after the discovery of any of the following events or conditions 
involving spent fuel, HLW, or reactor-related GTCC waste:
    (1) An action taken in an emergency that departs from a condition or 
a technical specification contained in a license or certificate of 
compliance issued under this part when the action is immediately needed 
to protect the public health and safety, and no action consistent with 
license or certificate of compliance conditions or technical 
specifications that can provide adequate or equivalent protection is 
immediately apparent.
    (2) Any event or situation related to the health and safety of the 
public or onsite personnel, or protection of the environment, for which 
a news release is planned or notification to other Government agencies 
has been or will be made. Such an event may include an onsite fatality 
or inadvertent release of radioactively contaminated materials.
    (c) Non-emergency notifications: Eight-hour reports. Each licensee 
shall notify the NRC as soon as possible but not later than eight hours 
after the discovery of any of the following events or conditions 
involving spent fuel, HLW, or reactor-related GTCC waste:
    (1) A defect in any spent fuel, HLW, or reactor-related GTCC waste 
storage structure, system, or component that is important to safety.
    (2) A significant reduction in the effectiveness of any spent fuel, 
HLW, or reactor-related GTCC waste storage confinement system during 
use.
    (3) Any event requiring the transport of a radioactively 
contaminated person

[[Page 428]]

to an offsite medical facility for treatment.
    (d) Non-emergency notifications: 24-hour reports. Each licensee 
shall notify the NRC within 24 hours after the discovery of any of the 
following events involving spent fuel, HLW, or reactor-related GTCC 
waste:
    (1) An event in which important to safety equipment is disabled or 
fails to function as designed when:
    (i) The equipment is required by regulation, license condition, or 
certificate of compliance to be available and operable to prevent 
releases that could exceed regulatory limits, to prevent exposures to 
radiation or radioactive materials that could exceed regulatory limits, 
or to mitigate the consequences of an accident; and
    (ii) No redundant equipment was available and operable to perform 
the required safety function.
    (2) For notifications made under this paragraph, the licensee may 
delay the notification to the NRC if the end of the 24-hour period 
occurs outside of the NRC's normal working day (i.e., 7:30 a.m. to 5:00 
p.m. Eastern time), on a weekend, or a Federal holiday. In these cases, 
the licensee shall notify the NRC before 8:00 a.m. Eastern time on the 
next working day.
    (e) Initial notification: Reports made by licensees in response to 
the requirements of this section must be made as follows:
    (1) Licensees shall make reports required by paragraphs (a), (b), 
(c), or (d) of this section by telephone to the NRC Headquarters 
Operations Center. \2\
---------------------------------------------------------------------------

    \2\ The commercial telephone number of the NRC Headquarters 
Operations Center is (301) 816-5100. Those licensees with an available 
Emergency Notification System (ENS) shall use the ENS to notify the NRC 
Headquarters Operations Center.
---------------------------------------------------------------------------

    (2) When making a report under paragraphs (a), (b), (c), or (d) of 
this section, the licensee shall identify:
    (i) The Emergency Class declared; or
    (ii) Paragraph (b), ``four-hour reports,'' paragraph (c), ``eight-
hour reports,'' or paragraph (d), ``24-hour reports,'' as the paragraph 
of this section requiring notification of the non-emergency event.
    (3) To the extent that the information is available at the time of 
notification, the information provided in these reports must include:
    (i) The caller's name and call back telephone number;
    (ii) A description of the event, including date and time;
    (iii) The exact location of the event;
    (iv) The quantities and chemical and physical forms of the spent 
fuel, HLW, or reactor-related GTCC waste involved in the event; and
    (v) Any personnel radiation exposure data.
    (f) Follow-up notification: With respect to the telephone 
notifications made under paragraphs (a), (b), (c) or (d) of this 
section, in addition to making the required initial notification, each 
licensee shall during the course of the event:
    (1) Immediately report any further degradation in the level of 
safety of the ISFSI or MRS or other worsening conditions, including 
those that require the declaration of any of the Emergency Classes, if 
such a declaration has not been previously made; or any change from one 
Emergency Class to another; or a termination of the Emergency Class.
    (2) Immediately report the results of ensuing evaluations or 
assessments of ISFSI or MRS conditions; the effectiveness of response or 
protective measures taken; and information related to ISFSI or MRS 
behavior that is not understood.
    (3) Maintain an open, continuous communication channel with the NRC 
Headquarters Operations Center upon request by the NRC.
    (g) Preparation and submission of written reports. Each licensee who 
makes an initial notification required by paragraphs (b)(1), (c)(1), 
(c)(2), or (d)(1) of this section shall also submit a written follow-up 
report to the Commission within 60 days of the initial notification. 
Written reports prepared pursuant to other regulations may be submitted 
to fulfill this requirement if the reports contain all the necessary 
information and the appropriate distribution is made. These written 
reports must be of sufficient quality to permit legible reproduction and 
optical scanning and must be submitted to the NRC in accordance with 
Sec. 72.4. These

[[Page 429]]

reports must include the following information:
    (1) A brief abstract describing the major occurrences during the 
event, including all component or system failures that contributed to 
the event and significant corrective action taken or planned to prevent 
recurrence;
    (2) A clear, specific, narrative description of the event that 
occurred so that knowledgeable readers conversant with the design of an 
ISFSI or MRS, but not familiar with the details of a particular 
facility, can understand the complete event. The narrative description 
must include the following specific information as appropriate for the 
particular event:
    (i) The ISFSI or MRS operating conditions before the event;
    (ii) The status of structures, components, or systems that were 
inoperable at the start of the event and that contributed to the event;
    (iii) The dates and approximate times of occurrences;
    (iv) The cause of each component or system failure or personnel 
error, if known;
    (v) The failure mode, mechanism, and effect of each failed 
component, if known;
    (vi) A list of systems or secondary functions that were also 
affected for failures of components with multiple functions;
    (vii) For wet spent fuel storage systems only, after the failure 
that rendered a train of a safety system inoperable, an estimate of the 
elapsed time from the discovery of the failure until the train was 
returned to service;
    (viii) The method of discovery of each component or system failure 
or procedural error;
    (ix) For each human performance related root cause, the licensee 
shall discuss the cause(s) and circumstances;
    (x) For wet spent fuel storage systems only, any automatically and 
manually initiated safety system responses;
    (xi) The manufacturer and model number (or other identification) of 
each component that failed during the event; and
    (xii) The quantities and chemical and physical forms of the spent 
fuel, HLW, or reactor-related GTCC waste involved in the event;
    (3) An assessment of the safety consequences and implications of the 
event. This assessment must include the availability of other systems or 
components that could have performed the same function as the components 
and systems that failed during the event;
    (4) A description of any corrective actions planned as a result of 
the event, including those to reduce the probability of similar events 
occurring in the future;
    (5) Reference to any previous similar events at the same facility 
that are known to the licensee;
    (6) The name and telephone number of a person within the licensee's 
organization who is knowledgeable about the event and can provide 
additional information concerning the event and the facility's 
characteristics; and
    (7) The extent of exposure of individuals to radiation or to 
radioactive materials without identification of individuals by name.
    (h) Supplemental information: The Commission may require the 
licensee to submit specific additional information beyond that required 
by paragraph (g) of this section if the Commission finds that 
supplemental material is necessary for complete understanding of an 
unusually complex or significant event. These requests for supplemental 
information will be made in writing, and the licensee shall submit, as 
specified in Sec. 72.4, the requested information as a supplement to 
the initial written report.
    (i) Applicability: The requirements of this section apply to:
    (1)(i) Licensees issued a specific license under Sec. 72.40; and
    (ii) Licensees issued a general license under Sec. 72.210, after 
the licensee has placed spent fuel on the ISFSI storage pad (if the 
ISFSI is located inside the collocated protected area, for a reactor 
licensed under part 50 of this chapter) or after the licensee has 
transferred spent fuel waste outside the reactor licensee's protected 
area to the ISFSI storage pad (if the ISFSI is located outside the 
collocated protected area, for a reactor licensed under part 50 of this 
chapter).

[[Page 430]]

    (2) Those non-emergency events specified in paragraphs (b), (c), and 
(d) of this section that occurred within 3 years of the date of 
discovery.

[68 FR 33615, June 5, 2003]



Sec. 72.76  Material status reports.

    (a) Except as provided in paragraph (b) of this section, each 
licensee shall complete in computer-readable format and submit to the 
Commission a Material Balance Report and a Physical Inventory Listing 
Report as specified in the instructions in NUREG/BR-0007 and NMMSS 
Report D-24 ``Personal Computer Data Input for NRC Licensees.'' Copies 
of these instructions may be obtained either by writing to the U.S. 
Nuclear Regulatory Commission, Division of Fuel Cycle Safety Safeguards, 
and Environmental Review, Washington, DC 20555-0001, or by e-mail to 
[email protected]. These reports, as specified by Sec. 74.13 or 
40.64 of this chapter, provide information concerning the special 
nuclear material and/or source material possessed, received, 
transferred, disposed of, or lost by the licensee. Each report must be 
submitted within 60 days of the beginning of the physical inventory 
required by Sec. 72.72(b). The Commission may, when good cause is 
shown, permit a licensee to submit Material Balance Reports and Physical 
Inventory Listing Reports at other times. Each licensee required to 
report material balance and inventory information as described in this 
part, shall resolve any discrepancies identified during the report 
review and reconciliation process within 30 calendar days of 
notification of a discrepancy identified by NRC. The Commission's copy 
of this report must be submitted to the address specified in the 
instructions. These prescribed, computer-readable forms replace the DOE/
NRC Forms 742 and 742C previously submitted in paper form.
    (b) Any licensee who is required to submit routine material status 
reports pursuant to Sec. 75.35 of this chapter (pertaining to 
implementation of the US/IAEA Safeguards Agreement) shall prepare and 
submit such reports only as provided in that section instead of as 
provided in paragraph (a) of this section.

[53 FR 31658, Aug. 19, 1988, as amended at 59 FR 35620, July 13, 1994; 
66 FR 51841, Oct. 11, 2001; 67 FR 78143, Dec. 23, 2002; 68 FR 58819, 
Oct. 10, 2003; 73 FR 32462, June 9, 2008; 79 FR 75741, Dec. 19, 2014]



Sec. 72.78  Nuclear material transaction reports.

    (a) Except as provided in paragraph (b) of this section, whenever 
the licensee transfers or receives or adjusts the inventory, in any 
manner, of special nuclear material as specified by Sec. 74.15 and/or 
source material as specified by Sec. 40.64 of this chapter, the 
licensee shall complete in computer-readable format a Nuclear Material 
Transaction Report as specified in the instructions in NUREG/BR-0006 and 
NMMSS Report D-24, ``Personal Computer Data Input for NRC Licensees.'' 
Copies of these instructions may be obtained either by writing to the 
U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety, 
Safeguards, and Environmental Review, Washington, DC 20555-0001, or by 
e-mail to [email protected]. Each licensee who transfers the material 
shall submit a Nuclear Material Transaction Report in computer-readable 
format as specified in the instructions no later than the close of 
business the next working day. Each licensee who receives the material 
shall submit a Nuclear Material Transaction Report in computer-readable 
format in accordance with instructions within ten (10) days after the 
material is received. Each ISFSI licensee who receives spent fuel from a 
foreign source shall complete both the supplier's and the receiver's 
portion of the Nuclear Material Transaction Report, verify the identity 
of the spent fuel, and indicate the results on the receiver's portion of 
the form. These prescribed computer-readable forms replace the DOE/NRC 
Form 741 which have been previously submitted in paper form.
    (b) Any licensee who is required to submit Nuclear Material 
Transactions Reports pursuant to Sec. 75.34 of this chapter (pertaining 
to implementation of the US/IAEA Safeguards Agreement) shall prepare and 
submit the reports only as provided in that section instead

[[Page 431]]

of as provided in paragraph (a) of this section.

[59 FR 35621, July 13, 1994, as amended at 66 FR 51841, Oct. 11, 2001; 
68 FR 58819, Oct. 10, 2003; 73 FR 32463, June 9, 2008; 79 FR 75741, Dec. 
19, 2014]



Sec. 72.79  Facility information and verification.

    (a) In response to a written request by the Commission, each 
applicant for a certificate of compliance or license and each recipient 
of a certificate of compliance or specific or general license shall 
submit facility information, as described in Sec. 75.10 of this 
chapter, on Form N-71 and associated forms and site information on DOC/
NRC Form AP-A and associated forms;
    (b) Shall submit location information described in Sec. 75.11 of 
this chapter on DOC/NRC Form AP-1 and associated forms; and
    (c) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA) and take other action as necessary to implement the 
US/IAEA Safeguards Agreement, as described in part 75 of this chapter.

[73 FR 78607, Dec. 23, 2008]



Sec. 72.80  Other records and reports.

    (a) Each licensee shall maintain any records and make any reports 
that may be required by the conditions of the license or by the rules, 
regulations, and orders of the Commission in effectuating the purposes 
of the Act.
    (b) Each licensee shall furnish a copy of its annual financial 
report, including the certified financial statements, to the Commission. 
However, licensees who submit a Form 10-Q with the Securities and 
Exchange Commission or a Form 1 with the Federal Energy Regulatory 
Commission, need not submit the annual financial report or a certified 
financial statement under this paragraph.
    (c) Records that are required by the regulations in this part or by 
the license conditions must be maintained for the period specified by 
the appropriate regulation or license condition. If a retention period 
is not otherwise specified, the above records must be maintained until 
the Commission terminates the license.
    (d) Any record that must be maintained pursuant to this part may be 
either the original or a reproduced copy by any state of the art method 
provided that any reproduced copy is duly authenticated by authorized 
personnel and is capable of producing a clear and legible copy after 
storage for the period specified by Commission regulations.
    (e) Before license termination, the licensee shall forward records 
required by Sec. 20.2103(b)(4), of this chapter, and Sec. 72.30(f) to 
the appropriate NRC Regional Office.
    (f) If licensed activities are transferred or assigned in accordance 
with Sec. 72.44(b)(1), the licensee shall transfer the records required 
by Sec. 20.2103(b)(4), of this chapter, and Sec. 72.30(f) to the new 
licensee and the new licensee will be responsible for maintaining these 
records until the license is terminated.
    (g) Each specific licensee shall notify the Commission, in 
accordance with Sec. 72.4, of its readiness to begin operation at least 
90 days prior to the first storage of spent fuel, high-level waste, or 
reactor-related GTCC waste in an ISFSI or an MRS.

[53 FR 31658, Aug. 19, 1988, as amended at 61 FR 24675, May 16, 1996; 64 
FR 53616, Oct. 4, 1999; 66 FR 51841, Oct. 11, 2001; 71 FR 29247, May 22, 
2006; 76 FR 35574, June 17, 2011]



Sec. 72.82  Inspections and tests.

    (a) Each licensee under this part shall permit duly authorized 
representatives of the Commission to inspect its records, premises, and 
activities and of spent fuel, high-level radioactive waste, or reactor-
related GTCC waste in its possession related to the specific license as 
may be necessary to meet the objectives of the Act, including section 
105 of the Act.
    (b) Each licensee under this part shall make available to the 
Commission for inspection, upon reasonable notice, records kept by the 
licensee pertaining to its receipt, possession, packaging, or transfer 
of spent fuel, high-level radioactive waste, or reactor-related GTCC 
waste.
    (c)(1) Each licensee under this part shall upon request by the 
Director, Office of Nuclear Material Safety and Safeguards or the 
appropriate NRC Regional Administrator provide rent-free

[[Page 432]]

office space for the exclusive use of the Commission inspection 
personnel. Heat, air conditioning, light, electrical outlets and 
janitorial services shall be furnished by each licensee. The office 
shall be convenient to and have full access to the installation and 
shall provide the inspector both visual and acoustic privacy.
    (2) For a site with a single storage installation the space provided 
shall be adequate to accommodate a full-time inspector, a part-time 
secretary, and transient NRC personnel and will be generally 
commensurate with other office facilities at the site. A space of 250 
sq. ft., either within the site's office complex or in an office 
trailer, or other onsite space, is suggested as a guide. For sites 
containing multiple facilities, additional space may be requested to 
accommodate additional full-time inspectors. The office space that is 
provided shall be subject to the approval of the Director, Office of 
Nuclear Material Safety and Safeguards or the appropriate NRC Regional 
Administrator. All furniture, supplies and Commission equipment will be 
furnished by the Commission.
    (3) Each licensee under this part shall afford any NRC resident 
inspector assigned to that site, or other NRC inspectors identified by 
the Regional Administrator as likely to inspect the installation, 
immediate unfettered access, equivalent to access provided regular plant 
employees, following proper identification and compliance with 
applicable access control measures for security, radiological 
protection, and personal safety.
    (d) Each licensee shall perform, or permit the Commission to 
perform, such tests as the Commission deems appropriate or necessary for 
the administrator of the regulations in this part.

[53 FR 31658, Aug. 19, 1988, as amended at 64 FR 17512, Apr. 12, 1999; 
66 FR 51842, Oct. 11, 2001]



Sec. 72.84  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
Section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55078, Nov. 24, 1992]



Sec. 72.86  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 72 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in Part 72 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 72.1, 72.2, 72.3, 72.4, 72.5, 72.7, 72.8, 72.9, 72.13, 72.16, 
72.18, 72.20, 72.22, 72.24, 72.26, 72.28, 72.32, 72.34, 72.40, 72.46, 
72.56, 72.58, 72.60, 72.62, 72.84, 72.86, 72.90, 72.96, 72.108, 72.120, 
72.122, 72.124, 72.126, 72.128, 72.130, 72.182, 72.194, 72.200, 72.202, 
72.204, 72.206, 72.210, 72.214, 72.220, 72.230, 72.238, and 72.240.

[57 FR 55078, Nov. 24, 1992, as amended at 59 FR 36040, July 13, 1994; 
64 FR 53616, Oct. 4, 1999; 64 FR 56122, Oct. 15, 1999; 65 FR 50617, Aug. 
21, 2000]

[[Page 433]]



                   Subpart E_Siting Evaluation Factors



Sec. 72.90  General considerations.

    (a) Site characteristics that may directly affect the safety or 
environmental impact of the ISFSI or MRS must be investigated and 
assessed.
    (b) Proposed sites for the ISFSI or MRS must be examined with 
respect to the frequency and the severity of external natural and man-
induced events that could affect the safe operation of the ISFSI or MRS.
    (c) Design basis external events must be determined for each 
combination of proposed site and proposed ISFSI or MRS design.
    (d) Proposed sites with design basis external events for which 
adequate protection cannot be provided through ISFSI or MRS design shall 
be deemed unsuitable for the location of the ISFSI or MRS.
    (e) Pursuant to subpart A of part 51 of this chapter for each 
proposed site for an ISFSI and pursuant to sections 141 or 148 of NWPA, 
as appropriate (96 Stat. 2241, 101 Stat. 1330-235, 42 U.S.C. 10161, 
10168) for each proposed site for an MRS, the potential for radiological 
and other environmental impacts on the region must be evaluated with due 
consideration of the characteristics of the population, including its 
distribution, and of the regional environs, including its historical and 
esthetic values.
    (f) The facility must be sited so as to avoid to the extent possible 
the long-term and short-term adverse impacts associated with the 
occupancy and modification of floodplains.



Sec. 72.92  Design basis external natural events.

    (a) Natural phenomena that may exist or that can occur in the region 
of a proposed site must be identified and assessed according to their 
potential effects on the safe operation of the ISFSI or MRS. The 
important natural phenomena that affect the ISFSI or MRS design must be 
identified.
    (b) Records of the occurrence and severity of those important 
natural phenomena must be collected for the region and evaluated for 
reliability, accuracy, and completeness. The applicant shall retain 
these records until the license is issued.
    (c) Appropriate methods must be adopted for evaluating the design 
basis external natural events based on the characteristics of the region 
and the current state of knowledge about such events.



Sec. 72.94  Design basis external man-induced events.

    (a) The region must be examined for both past and present man-made 
facilities and activities that might endanger the proposed ISFSI or MRS. 
The important potential man-induced events that affect the ISFSI or MRS 
design must be identified.
    (b) Information concerning the potential occurrence and severity of 
such events must be collected and evaluated for reliability, accuracy, 
and completeness.
    (c) Appropriate methods must be adopted for evaluating the design 
basis external man-induced events, based on the current state of 
knowledge about such events.



Sec. 72.96  Siting limitations.

    (a) An ISFSI which is owned and operated by DOE must not be located 
at any site within which there is a candidate site for a HLW repository. 
This limitation shall apply until such time as DOE decides that such 
candidate site is no longer a candidate site under consideration for 
development as a HLW repository.
    (b) An MRS must not be sited in any State in which there is located 
any site approved for site characterization for a HLW repository. This 
limitation shall apply until such time as DOE decides that the candidate 
site is no longer a candidate site under consideration for development 
as a repository. This limitation shall continue to apply to any site 
selected for construction as a repository.
    (c) If an MRS is located, or is planned to be located, within 50 
miles of the first HLW repository, any Commission decision approving the 
first HLW repository application must limit the quantity of spent fuel 
or high-level radioactive waste that may be stored.

[[Page 434]]

This limitation shall prohibit the storage of a quantity of spent fuel 
containing in excess of 70,000 metric tons of heavy metal, or a quantity 
of solidified high-level radioactive waste resulting from the 
reprocessing of such a quantity of spent fuel, in both the repository 
and the MRS until such time as a second repository is in operation.
    (d) An MRS authorized by section 142(b) of NWPA (101 Stat. 1330-232, 
42 U.S.C. 10162(b)) may not be constructed in the State of Nevada. The 
quantity of spent nuclear fuel or high-level radioactive waste that may 
be stored at an MRS authorized by section 142(b) of NWPA shall be 
subject to the limitations in Sec. 72.44(g) of this part instead of the 
limitations in paragraph (c) of this section.



Sec. 72.98  Identifying regions around an ISFSI or MRS site.

    (a) The regional extent of external phenomena, man-made or natural, 
that are used as a basis for the design of the ISFSI or MRS must be 
identified.
    (b) The potential regional impact due to the construction, operation 
or decommissioning of the ISFSI or MRS must be identified. The extent of 
regional impacts must be determined on the basis of potential measurable 
effects on the population or the environment from ISFSI or MRS 
activities.
    (c) Those regions identified pursuant to paragraphs (a) and (b) of 
this section must be investigated as appropriate with respect to:
    (1) The present and future character and the distribution of 
population,
    (2) Consideration of present and projected future uses of land and 
water within the region, and
    (3) Any special characteristics that may influence the potential 
consequences of a release of radioactive material during the operational 
lifetime of the ISFSI or MRS.



Sec. 72.100  Defining potential effects of the ISFSI or MRS on the
region.

    (a) The proposed site must be evaluated with respect to the effects 
on populations in the region resulting from the release of radioactive 
materials under normal and accident conditions during operation and 
decommissioning of the ISFSI or MRS; in this evaluation both usual and 
unusual regional and site characteristics shall be taken into account.
    (b) Each site must be evaluated with respect to the effects on the 
regional environment resulting from construction, operation, and 
decommissioning for the ISFSI or MRS; in this evaluation both usual and 
unusual regional and site characteristics must be taken into account.



Sec. 72.102  Geological and seismological characteristics for 
applications before October 16, 2003 and applications for other 
than dry cask modes of storage.

    (a)(1) East of the Rocky Mountain Front (east of approximately 
104[deg] west longitude), except in areas of known seismic activity 
including but not limited to the regions around New Madrid, MO, 
Charleston, SC, and Attica, NY, sites will be acceptable if the results 
from onsite foundation and geological investigation, literature review, 
and regional geological reconnaissance show no unstable geological 
characteristics, soil stability problems, or potential for vibratory 
ground motion at the site in excess of an appropriate response spectrum 
anchored at 0.2 g.
    (2) For those sites that have been evaluated under paragraph (a)(1) 
of this section that are east of the Rocky Mountain Front, and that are 
not in areas of known seismic activity, a standardized design earthquake 
(DE) described by an appropriate response spectrum anchored at 0.25 g 
may be used. Alternatively, a site-specific DE may be determined by 
using the criteria and level of investigations required by appendix A of 
part 100 of this chapter.
    (b) West of the Rocky Mountain Front (west of approximately 104[deg] 
west longitude), and in other areas of known potential seismic activity, 
seismicity will be evaluated by the techniques of appendix A of part 100 
of this chapter. Sites that lie within the range of strong near-field 
ground motion from historical earthquakes on large capable faults should 
be avoided.
    (c) Sites other than bedrock sites must be evaluated for their 
liquefaction potential or other soil instability due to vibratory ground 
motion.

[[Page 435]]

    (d) Site-specific investigations and laboratory analyses must show 
that soil conditions are adequate for the proposed foundation loading.
    (e) In an evaluation of alternative sites, those which require a 
minimum of engineered provisions to correct site deficiencies are 
preferred. Sites with unstable geologic characteristics should be 
avoided.
    (f) The design earthquake (DE) for use in the design of structures 
must be determined as follows:
    (1) For sites that have been evaluated under the criteria of 
appendix A of 10 CFR part 100, the DE must be equivalent to the safe 
shutdown earthquake (SSE) for a nuclear power plant.
    (2) Regardless of the results of the investigations anywhere in the 
continental U.S., the DE must have a value for the horizontal ground 
motion of no less than 0.10 g with the appropriate response spectrum.



Sec. 72.103  Geological and seismological characteristics for 
applications for dry cask modes of storage on or after October 16,
2003.

    (a)(1) East of the Rocky Mountain Front (east of approximately 
104[deg] west longitude), except in areas of known seismic activity 
including but not limited to the regions around New Madrid, MO; 
Charleston, SC; and Attica, NY; sites will be acceptable if the results 
from onsite foundation and geological investigation, literature review, 
and regional geological reconnaissance show no unstable geological 
characteristics, soil stability problems, or potential for vibratory 
ground motion at the site in excess of an appropriate response spectrum 
anchored at 0.2 g.
    (2) For those sites that have been evaluated under paragraph (a)(1) 
of this section that are east of the Rocky Mountain Front, and that are 
not in areas of known seismic activity, a standardized design earthquake 
ground motion (DE) described by an appropriate response spectrum 
anchored at 0.25 g may be used. Alternatively, a site-specific DE may be 
determined by using the criteria and level of investigations required by 
paragraph (f) of this section. For a site with a co-located nuclear 
power plant (NPP), the existing geological and seismological design 
criteria for the NPP may be used. If the existing design criteria for 
the NPP is used and the site has multiple NPPs, then the criteria for 
the most recent NPP must be used.
    (b) West of the Rocky Mountain Front (west of approximately 104[deg] 
west longitude), and in other areas of known potential seismic activity 
east of the Rocky Mountain Front, seismicity must be evaluated by the 
techniques presented in paragraph (f) of this section. If an ISFSI or 
MRS is located on an NPP site, the existing geological and seismological 
design criteria for the NPP may be used. If the existing design criteria 
for the NPP is used and the site has multiple NPPs, then the criteria 
for the most recent NPP must be used.
    (c) Sites other than bedrock sites must be evaluated for their 
liquefaction potential or other soil instability due to vibratory ground 
motion.
    (d) Site-specific investigations and laboratory analyses must show 
that soil conditions are adequate for the proposed foundation loading.
    (e) In an evaluation of alternative sites, those which require a 
minimum of engineered provisions to correct site deficiencies are 
preferred. Sites with unstable geologic characteristics should be 
avoided.
    (f) Except as provided in paragraphs (a)(2) and (b) of this section, 
the DE for use in the design of structures, systems, and components must 
be determined as follows:
    (1) Geological, seismological, and engineering characteristics. The 
geological, seismological, and engineering characteristics of a site and 
its environs must be investigated in sufficient scope and detail to 
permit an adequate evaluation of the proposed site, to provide 
sufficient information to support evaluations performed to arrive at 
estimates of the DE, and to permit adequate engineering solutions to 
actual or potential geologic and seismic effects at the proposed site. 
The size of the region to be investigated and the type of data pertinent 
to the investigations must be determined based on the nature of the 
region surrounding the proposed site. Data on the vibratory ground 
motion, tectonic surface deformation, nontectonic deformation,

[[Page 436]]

earthquake recurrence rates, fault geometry and slip rates, site 
foundation material, and seismically induced floods and water waves must 
be obtained by reviewing pertinent literature and carrying out field 
investigations. However, each applicant shall investigate all geologic 
and seismic factors (for example, volcanic activity) that may affect the 
design and operation of the proposed ISFSI or MRS facility irrespective 
of whether these factors are explicitly included in this section.
    (2) Geologic and seismic siting factors. The geologic and seismic 
siting factors considered for design must include a determination of the 
DE for the site, the potential for surface tectonic and nontectonic 
deformations, the design bases for seismically induced floods and water 
waves, and other design conditions as stated in paragraph (f)(2)(iv) of 
this section.
    (i) Determination of the Design Earthquake Ground Motion (DE). The 
DE for the site is characterized by both horizontal and vertical free-
field ground motion response spectra at the free ground surface. In view 
of the limited data available on vibratory ground motions for strong 
earthquakes, it usually will be appropriate that the design response 
spectra be smoothed spectra. The DE for the site is determined 
considering the results of the investigations required by paragraph 
(f)(1) of this section. Uncertainties are inherent in these estimates 
and must be addressed through an appropriate analysis, such as a 
probabilistic seismic hazard analysis (PSHA) or suitable sensitivity 
analyses.
    (ii) Determination of the potential for surface tectonic and 
nontectonic deformations. Sufficient geological, seismological, and 
geophysical data must be provided to clearly establish if there is a 
potential for surface deformation.
    (iii) Determination of design bases for seismically induced floods 
and water waves. The size of seismically induced floods and water waves 
that could affect a site from either locally or distantly generated 
seismic activity must be determined.
    (iv) Determination of siting factors for other design conditions. 
Siting factors for other design conditions that must be evaluated 
include soil and rock stability, liquefaction potential, and natural and 
artificial slope stability. Each applicant shall evaluate all siting 
factors and potential causes of failure, such as, the physical 
properties of the materials underlying the site, ground disruption, and 
the effects of vibratory ground motion that may affect the design and 
operation of the proposed ISFSI or MRS.
    (3) Regardless of the results of the investigations anywhere in the 
continental U.S., the DE must have a value for the horizontal ground 
motion of no less than 0.10 g with the appropriate response spectrum.

[68 FR 54159, Sept. 16, 2003]



Sec. 72.104  Criteria for radioactive materials in effluents and
direct radiation from an ISFSI or MRS.

    (a) During normal operations and anticipated occurrences, the annual 
dose equivalent to any real individual who is located beyond the 
controlled area must not exceed 0.25 mSv (25 mrem) to the whole body, 
0.75 mSv (75 mrem) to the thyroid and 0.25 mSv (25 mrem) to any other 
critical organ as a result of exposure to:
    (1) Planned discharges of radioactive materials, radon and its decay 
products excepted, to the general environment,
    (2) Direct radiation from ISFSI or MRS operations, and
    (3) Any other radiation from uranium fuel cycle operations within 
the region.
    (b) Operational restrictions must be established to meet as low as 
is reasonably achievable objectives for radioactive materials in 
effluents and direct radiation levels associated with ISFSI or MRS 
operations.
    (c) Operational limits must be established for radioactive materials 
in effluents and direct radiation levels associated with ISFSI or MRS 
operations to meet the limits given in paragraph (a) of this section.

[53 FR 31658, Aug. 19, 1988, as amended at 63 FR 54562, Oct. 13, 1998]



Sec. 72.106  Controlled area of an ISFSI or MRS.

    (a) For each ISFSI or MRS site, a controlled area must be 
established.

[[Page 437]]

    (b) Any individual located on or beyond the nearest boundary of the 
controlled area may not receive from any design basis accident the more 
limiting of a total effective dose equivalent of 0.05 Sv (5 rem), or the 
sum of the deep-dose equivalent and the committed dose equivalent to any 
individual organ or tissue (other than the lens of the eye) of 0.5 Sv 
(50 rem). The lens dose equivalent may not exceed 0.15 Sv (15 rem) and 
the shallow dose equivalent to skin or any extremity may not exceed 0.5 
Sv (50 rem). The minimum distance from the spent fuel, high-level 
radioactive waste, or reactor-related GTCC waste handling and storage 
facilities to the nearest boundary of the controlled area must be at 
least 100 meters.
    (c) The controlled area may be traversed by a highway, railroad or 
waterway, so long as appropriate and effective arrangements are made to 
control traffic and to protect public health and safety.

[53 FR 31658, Aug. 19, 1988, as amended at 63 FR 54562, Oct. 13, 1998; 
66 FR 51842, Oct. 11, 2001]



Sec. 72.108  Spent fuel, high-level radioactive waste, or reactor-
related greater than Class C waste transportation.

    The proposed ISFSI or MRS must be evaluated with respect to the 
potential impact on the environment of the transportation of spent fuel, 
high-level radioactive waste, or reactor-related GTCC waste within the 
region.

[66 FR 51842, Oct. 11, 2001]



                    Subpart F_General Design Criteria



Sec. 72.120  General considerations.

    (a) As required by Sec. 72.24, an application to store spent fuel 
or reactor-related GTCC waste in an ISFSI or to store spent fuel, high-
level radioactive waste, or reactor-related GTCC waste in an MRS must 
include the design criteria for the proposed storage installation. These 
design criteria establish the design, fabrication, construction, 
testing, maintenance and performance requirements for structures, 
systems, and components important to safety as defined in Sec. 72.3. 
The general design criteria identified in this subpart establish minimum 
requirements for the design criteria for an ISFSI or an MRS. Any 
omissions in these general design criteria do not relieve the applicant 
from the requirement of providing the necessary safety features in the 
design of the ISFSI or MRS.
    (b) The ISFSI must be designed to store spent fuel and/or solid 
reactor-related GTCC waste.
    (1) Reactor-related GTCC waste may not be stored in a cask that also 
contains spent fuel. This restriction does not include radioactive 
materials that are associated with fuel assemblies (e.g., control rod 
blades or assemblies, thimble plugs, burnable poison rod assemblies, or 
fuel channels);
    (2) Liquid reactor-related GTCC wastes may not be received or stored 
in an ISFSI; and
    (3) If the ISFSI is a water-pool type facility, the reactor-related 
GTCC waste must be in a durable solid form with demonstrable leach 
resistance.
    (c) The MRS must be designed to store spent fuel, solid high-level 
radioactive waste, and/or solid reactor-related GTCC waste.
    (1) Reactor-related GTCC waste may not be stored in a cask that also 
contains spent fuel. This restriction does not include radioactive 
materials associated with fuel assemblies (e.g., control rod blades or 
assemblies, thimble plugs, burnable poison rod assemblies, or fuel 
channels);
    (2) Liquid high-level radioactive wastes or liquid reactor-related 
GTCC wastes may not be received or stored in an MRS; and
    (3) If the MRS is a water-pool type facility, the high-level waste 
and reactor-related GTCC waste must be in a durable solid form with 
demonstrable leach resistance.
    (d) The ISFSI or MRS must be designed, made of materials, and 
constructed to ensure that there will be no significant chemical, 
galvanic, or other reactions between or among the storage system 
components, spent fuel, reactor-related GTCC waste, and/or high level 
waste including possible reaction with water during wet loading and 
unloading operations or during storage in a water-pool type ISFSI or 
MRS. The

[[Page 438]]

behavior of materials under irradiation and thermal conditions must be 
taken into account.
    (e) The NRC may authorize exceptions, on a case-by-case basis, to 
the restrictions in paragraphs (b) and (c) of this section regarding the 
commingling of spent fuel and reactor-related GTCC waste in the same 
cask.

[66 FR 51842, Oct. 11, 2001]



Sec. 72.122  Overall requirements.

    (a) Quality Standards. Structures, systems, and components important 
to safety must be designed, fabricated, erected, and tested to quality 
standards commensurate with the importance to safety of the function to 
be performed.
    (b) Protection against environmental conditions and natural 
phenomena. (1) Structures, systems, and components important to safety 
must be designed to accommodate the effects of, and to be compatible 
with, site characteristics and environmental conditions associated with 
normal operation, maintenance, and testing of the ISFSI or MRS and to 
withstand postulated accidents.
    (2)(i) Structures, systems, and components important to safety must 
be designed to withstand the effects of natural phenomena such as 
earthquakes, tornadoes, lightning, hurricanes, floods, tsunami, and 
seiches, without impairing their capability to perform their intended 
design functions. The design bases for these structures, systems, and 
components must reflect:
    (A) Appropriate consideration of the most severe of the natural 
phenomena reported for the site and surrounding area, with appropriate 
margins to take into account the limitations of the data and the period 
of time in which the data have accumulated, and
    (B) Appropriate combinations of the effects of normal and accident 
conditions and the effects of natural phenomena.
    (ii) The ISFSI or MRS also should be designed to prevent massive 
collapse of building structures or the dropping of heavy objects as a 
result of building structural failure on the spent fuel, high-level 
radioactive waste, or reactor-related GTCC waste or on to structures, 
systems, and components important to safety.
    (3) Capability must be provided for determining the intensity of 
natural phenomena that may occur for comparison with design bases of 
structures, systems, and components important to safety.
    (4) If the ISFSI or MRS is located over an aquifer which is a major 
water resource, measures must be taken to preclude the transport of 
radioactive materials to the environment through this potential pathway.
    (c) Protection against fires and explosions. Structures, systems, 
and components important to safety must be designed and located so that 
they can continue to perform their safety functions effectively under 
credible fire and explosion exposure conditions. Noncombustible and 
heat-resistant materials must be used wherever practical throughout the 
ISFSI or MRS, particularly in locations vital to the control of 
radioactive materials and to the maintenance of safety control 
functions. Explosion and fire detection, alarm, and suppression systems 
shall be designed and provided with sufficient capacity and capability 
to minimize the adverse effects of fires and explosions on structures, 
systems, and components important to safety. The design of the ISFSI or 
MRS must include provisions to protect against adverse effects that 
might result from either the operation or the failure of the fire 
suppression system.
    (d) Sharing of structures, systems, and components. Structures, 
systems, and components important to safety must not be shared between 
an ISFSI or MRS and other facilities unless it is shown that such 
sharing will not impair the capability of either facility to perform its 
safety functions, including the ability to return to a safe condition in 
the event of an accident.
    (e) Proximity of sites. An ISFSI or MRS located near other nuclear 
facilities must be designed and operated to ensure that the cumulative 
effects of their combined operations will not constitute an unreasonable 
risk to the health and safety of the public.
    (f) Testing and maintenance of systems and components. Systems and 
components that are important to safety

[[Page 439]]

must be designed to permit inspection, maintenance, and testing.
    (g) Emergency capability. Structures, systems, and components 
important to safety must be designed for emergencies. The design must 
provide for accessibility to the equipment of onsite and available 
offsite emergency facilities and services such as hospitals, fire and 
police departments, ambulance service, and other emergency agencies.
    (h) Confinement barriers and systems. (1) The spent fuel cladding 
must be protected during storage against degradation that leads to gross 
ruptures or the fuel must be otherwise confined such that degradation of 
the fuel during storage will not pose operational safety problems with 
respect to its removal from storage. This may be accomplished by canning 
of consolidated fuel rods or unconsolidated assemblies or other means as 
appropriate.
    (2) For underwater storage of spent fuel, high-level radioactive 
waste, or reactor-related GTCC waste in which the pool water serves as a 
shield and a confinement medium for radioactive materials, systems for 
maintaining water purity and the pool water level must be designed so 
that any abnormal operations or failure in those systems from any cause 
will not cause the water level to fall below safe limits. The design 
must preclude installations of drains, permanently connected systems, 
and other features that could, by abnormal operations or failure, cause 
a significant loss of water. Pool water level equipment must be provided 
to alarm in a continuously manned location if the water level in the 
storage pools falls below a predetermined level.
    (3) Ventilation systems and off-gas systems must be provided where 
necessary to ensure the confinement of airborne radioactive particulate 
materials during normal or off-normal conditions.
    (4) Storage confinement systems must have the capability for 
continuous monitoring in a manner such that the licensee will be able to 
determine when corrective action needs to be taken to maintain safe 
storage conditions. For dry spent fuel storage, periodic monitoring is 
sufficient provided that periodic monitoring is consistent with the dry 
spent fuel storage cask design requirements. The monitoring period must 
be based upon the spent fuel storage cask design requirements.
    (5) The high-level radioactive waste and reactor-related GTCC waste 
must be packaged in a manner that allows handling and retrievability 
without the release of radioactive materials to the environment or 
radiation exposures in excess of part 20 limits. The package must be 
designed to confine the high-level radioactive waste for the duration of 
the license.
    (i) Instrumentation and control systems. Instrumentation and control 
systems for wet spent fuel and reactor-related GTCC waste storage must 
be provided to monitor systems that are important to safety over 
anticipated ranges for normal operation and off-normal operation. Those 
instruments and control systems that must remain operational under 
accident conditions must be identified in the Safety Analysis Report. 
Instrumentation systems for dry storage casks must be provided in 
accordance with cask design requirements to monitor conditions that are 
important to safety over anticipated ranges for normal conditions and 
off-normal conditions. Systems that are required under accident 
conditions must be identified in the Safety Analysis Report.
    (j) Control room or control area. A control room or control area, if 
appropriate for the ISFSI or MRS design, must be designed to permit 
occupancy and actions to be taken to monitor the ISFSI or MRS safely 
under normal conditions, and to provide safe control of the ISFSI or MRS 
under off-normal or accident conditions.
    (k) Utility or other services. (1) Each utility service system must 
be designed to meet emergency conditions. The design of utility services 
and distribution systems that are important to safety must include 
redundant systems to the extent necessary to maintain, with adequate 
capacity, the ability to perform safety functions assuming a single 
failure.
    (2) Emergency utility services must be designed to permit testing of 
the functional operability and capacity, including the full operational 
sequence, of each system for transfer between normal and emergency 
supply sources;

[[Page 440]]

and to permit the operation of associated safety systems.
    (3) Provisions must be made so that, in the event of a loss of the 
primary electric power source or circuit, reliable and timely emergency 
power will be provided to instruments, utility service systems, the 
central security alarm station, and operating systems, in amounts 
sufficient to allow safe storage conditions to be maintained and to 
permit continued functioning of all systems essential to safe storage.
    (4) An ISFSI or MRS which is located on the site of another facility 
may share common utilities and services with such a facility and be 
physically connected with the other facility; however, the sharing of 
utilities and services or the physical connection must not 
significantly:
    (i) Increase the probability or consequences of an accident or 
malfunction of components, structures, or systems that are important to 
safety; or
    (ii) Reduce the margin of safety as defined in the basis for any 
technical specifications of either facility.
    (l) Retrievability. Storage systems must be designed to allow ready 
retrieval of spent fuel, high-level radioactive waste, and reactor-
related GTCC waste for further processing or disposal.

[53 FR 31658, Aug. 19, 1988, as amended at 64 FR 33184, June 22, 1999; 
66 FR 51842, Oct. 11, 2001]



Sec. 72.124  Criteria for nuclear criticality safety.

    (a) Design for criticality safety. Spent fuel handling, packaging, 
transfer, and storage systems must be designed to be maintained 
subcritical and to ensure that, before a nuclear criticality accident is 
possible, at least two unlikely, independent, and concurrent or 
sequential changes have occurred in the conditions essential to nuclear 
criticality safety. The design of handling, packaging, transfer, and 
storage systems must include margins of safety for the nuclear 
criticality parameters that are commensurate with the uncertainties in 
the data and methods used in calculations and demonstrate safety for the 
handling, packaging, transfer and storage conditions and in the nature 
of the immediate environment under accident conditions.
    (b) Methods of criticality control. When practicable, the design of 
an ISFSI or MRS must be based on favorable geometry, permanently fixed 
neutron absorbing materials (poisons), or both. Where solid neutron 
absorbing materials are used, the design must provide for positive means 
of verifying their continued efficacy. For dry spent fuel storage 
systems, the continued efficacy may be confirmed by a demonstration or 
analysis before use, showing that significant degradation of the neutron 
absorbing materials cannot occur over the life of the facility.
    (c) Criticality monitoring. A criticality monitoring system shall be 
maintained in each area where special nuclear material is handled, used, 
or stored which will energize clearly audible alarm signals if 
accidental criticality occurs. Underwater monitoring is not required 
when special nuclear material is handled or stored beneath water 
shielding. Monitoring of dry storage areas where special nuclear 
material is packaged in its stored configuration under a license issued 
under this subpart is not required.

[53 FR 31658, Aug. 19, 1988, as amended at 64 FR 33184, June 22, 1999]



Sec. 72.126  Criteria for radiological protection.

    (a) Exposure control. Radiation protection systems must be provided 
for all areas and operations where onsite personnel may be exposed to 
radiation or airborne radioactive materials. Structures, systems, and 
components for which operation, maintenance, and required inspections 
may involve occupational exposure must be designed, fabricated, located, 
shielded, controlled, and tested so as to control external and internal 
radiation exposures to personnel. The design must include means to:
    (1) Prevent the accumulation of radioactive material in those 
systems requiring access;
    (2) Decontaminate those systems to which access is required;
    (3) Control access to areas of potential contamination or high 
radiation within the ISFSI or MRS;

[[Page 441]]

    (4) Measure and control contamination of areas requiring access;
    (5) Minimize the time required to perform work in the vicinity of 
radioactive components; for example, by providing sufficient space for 
ease of operation and designing equipment for ease of repair and 
replacement; and
    (6) Shield personnel from radiation exposure.
    (b) Radiological alarm systems. Radiological alarm systems must be 
provided in accessible work areas as appropriate to warn operating 
personnel of radiation and airborne radioactive material concentrations 
above a given setpoint and of concentrations of radioactive material in 
effluents above control limits. Radiation alarm systems must be designed 
with provisions for calibration and testing their operability.
    (c) Effluent and direct radiation monitoring. (1) As appropriate for 
the handling and storage system, effluent systems must be provided. 
Means for measuring the amount of radionuclides in effluents during 
normal operations and under accident conditions must be provided for 
these systems. A means of measuring the flow of the diluting medium, 
either air or water, must also be provided.
    (2) Areas containing radioactive materials must be provided with 
systems for measuring the direct radiation levels in and around these 
areas.
    (d) Effluent control. The ISFSI or MRS must be designed to provide 
means to limit to levels as low as is reasonably achievable the release 
of radioactive materials in effluents during normal operations; and 
control the release of radioactive materials under accident conditions. 
Analyses must be made to show that releases to the general environment 
during normal operations and anticipated occurrences will be within the 
exposure limit given in Sec. 72.104. Analyses of design basis accidents 
must be made to show that releases to the general environment will be 
within the exposure limits given in Sec. 72.106. Systems designed to 
monitor the release of radioactive materials must have means for 
calibration and testing their operability.



Sec. 72.128  Criteria for spent fuel, high-level radioactive waste,
reactor-related greater than Class C waste, and other radioactive
waste storage and handling.

    (a) Spent fuel, high-level radioactive waste, and reactor-related 
GTCC waste storage and handling systems. Spent fuel storage, high-level 
radioactive waste storage, reactor-related GTCC waste storage and other 
systems that might contain or handle radioactive materials associated 
with spent fuel, high-level radioactive waste, or reactor-related GTCC 
waste, must be designed to ensure adequate safety under normal and 
accident conditions. These systems must be designed with--
    (1) A capability to test and monitor components important to safety,
    (2) Suitable shielding for radioactive protection under normal and 
accident conditions,
    (3) Confinement structures and systems,
    (4) A heat-removal capability having testability and reliability 
consistent with its importance to safety, and
    (5) means to minimize the quantity of radioactive wastes generated.
    (b) Waste treatment. Radioactive waste treatment facilities must be 
provided. Provisions must be made for the packing of site-generated low-
level wastes in a form suitable for storage onsite awaiting transfer to 
disposal sites.

[53 FR 31658, Aug. 19, 1988, as amended at 66 FR 51843, Oct. 11, 2001]



Sec. 72.130  Criteria for decommissioning.

    The ISFSI or MRS must be designed for decommissioning. Provisions 
must be made to facilitate decontamination of structures and equipment, 
minimize the quantity of radioactive wastes and contaminated equipment, 
and facilitate the removal of radioactive wastes and contaminated 
materials at the time the ISFSI or MRS is permanently decommissioned.



                       Subpart G_Quality Assurance

    Source: 64 FR 56122, Oct. 15, 1999, unless otherwise noted.

[[Page 442]]



Sec. 72.140  Quality assurance requirements.

    (a) Purpose. This subpart describes quality assurance requirements 
that apply to design, purchase, fabrication, handling, shipping, 
storing, cleaning, assembly, inspection, testing, operation, 
maintenance, repair, modification of structures, systems, and 
components, and decommissioning that are important to safety. As used in 
this subpart, ``quality assurance'' comprises all those planned and 
systematic actions necessary to provide adequate confidence that a 
structure, system, or component will perform satisfactorily in service. 
Quality assurance includes quality control, which comprises those 
quality assurance actions related to control of the physical 
characteristics and quality of the material or component to 
predetermined requirements. The certificate holder and applicant for a 
CoC are responsible for the quality assurance requirements as they apply 
to the design, fabrication, and testing of a spent fuel storage cask 
until possession of the spent fuel storage cask is transferred to the 
licensee. The licensee and the certificate holder are also 
simultaneously responsible for these quality assurance requirements 
through the oversight of contractors and subcontractors.
    (b) Establishment of program. Each licensee, applicant for a 
license, certificate holder, applicant for a CoC shall establish, 
maintain, and execute a quality assurance program satisfying each of the 
applicable criteria of this subpart, and satisfying any specific 
provisions which are applicable to the licensee's, applicant's for a 
license, certificate holder's, and applicant's for a CoC activities. The 
licensee, applicant for a license, certificate holder, and applicant for 
a CoC shall execute the applicable criteria in a graded approach to an 
extent that is commensurate with the quality assurance requirements' 
importance to safety. The quality assurance program must cover the 
activities identified in this subpart throughout the life of the 
activity. For licensees, this includes activities from the site 
selection through decommissioning prior to termination of the license. 
For certificate holders, this includes activities from development of 
the spent fuel storage cask design through termination of the CoC.
    (c) Approval of program. (1) Each licensee, applicant for a license, 
certificate holder, or applicant for a CoC shall file a description of 
its quality assurance program, including a discussion of which 
requirements of this subpart are applicable and how they will be 
satisfied, in accordance with Sec. 72.4.
    (2) Each licensee shall obtain Commission approval of its quality 
assurance program prior to receipt of spent fuel and/or reactor-related 
GTCC waste at the ISFSI or spent fuel, high-level radioactive waste, 
and/or reactor-related GTCC waste at the MRS. Each licensee or applicant 
for a specific license shall obtain Commission approval of its quality 
assurance program before commencing fabrication or testing of a spent 
fuel storage cask.
    (3) Each certificate holder or applicant for a CoC shall obtain 
Commission approval of its quality assurance program before commencing 
fabrication or testing of a spent fuel storage cask.
    (d) Previously-approved programs. A quality assurance program 
previously approved by the Commission as satisfying the requirements of 
Appendix B to part 50 of this chapter, subpart H to part 71 of this 
chapter, or subpart G to this part will be accepted as satisfying the 
requirements of paragraph (b) of this section, except that a licensee, 
applicant for a license, certificate holder, and applicant for a CoC who 
is using an Appendix B or subpart H quality assurance program shall also 
meet the recordkeeping requirements of Sec. 72.174. In filing the 
description of the quality assurance program required by paragraph (c) 
of this section, each licensee, applicant for a license, certificate 
holder, and applicant for a CoC shall notify the NRC, in accordance with 
Sec. 72.4, of its intent to apply its previously-approved quality 
assurance program to ISFSI activities or spent fuel storage cask 
activities. The notification shall identify the previously-approved 
quality assurance program by date of submittal to the Commission, docket 
number, and date of Commission approval.

[53 FR 31658, Aug. 19, 1988, as amended at 65 FR 50617, Aug. 21, 2000; 
66 FR 51843, Oct. 11, 2001]

[[Page 443]]



Sec. 72.142  Quality assurance organization.

    (a) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall be responsible for the establishment and 
execution of the quality assurance program. The licensee and certificate 
holder may delegate to others, such as contractors, agents, or 
consultants, the work of establishing and executing the quality 
assurance program, but the licensee and the certificate holder shall 
retain responsibility for the program. The licensee, applicant for a 
license, certificate holder, and applicant for a CoC shall clearly 
establish and delineate in writing the authority and duties of persons 
and organizations performing activities affecting the functions of 
structures, systems, and components which are important to safety. These 
activities include performing the functions associated with attaining 
quality objectives and the quality assurance functions.
    (b) The quality assurance functions are--
    (1) Assuring that an appropriate quality assurance program is 
established and effectively executed; and
    (2) Verifying, by procedures such as checking, auditing, and 
inspection, that activities affecting the functions that are important 
to safety have been correctly performed. The persons and organizations 
performing quality assurance functions shall have sufficient authority 
and organizational freedom to identify quality problems; to initiate, 
recommend, or provide solutions; and to verify implementation of 
solutions.
    (c) The persons and organizations performing quality assurance 
functions shall report to a management level that ensures that the 
required authority and organizational freedom, including sufficient 
independence from cost and schedule considerations when these 
considerations are opposed to safety considerations, are provided. 
Because of the many variables involved, such as the number of personnel, 
the type of activity being performed, and the location or locations 
where activities are performed, the organizational structure for 
executing the quality assurance program may take various forms, provided 
that the persons and organizations assigned the quality assurance 
functions have the required authority and organizational freedom. 
Irrespective of the organizational structure, the individual(s) assigned 
the responsibility for assuring effective execution of any portion of 
the quality assurance program, at any location where activities subject 
to this section are being performed, must have direct access to the 
levels of management necessary to perform this function.



Sec. 72.144  Quality assurance program.

    (a) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish, at the earliest practicable time 
consistent with the schedule for accomplishing the activities, a quality 
assurance program which complies with the requirements of this subpart. 
The licensee, applicant for a license, certificate holder, and applicant 
for a CoC shall document the quality assurance program by written 
procedures or instructions and shall carry out the program in accordance 
with these procedures throughout the period during which the ISFSI or 
MRS is licensed or the spent fuel storage cask is certified. The 
licensee, applicant for a license, certificate holder, and applicant for 
a CoC shall identify the structures, systems, and components to be 
covered by the quality assurance program, the major organizations 
participating in the program, and the designated functions of these 
organizations.
    (b) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC, through their quality assurance program(s), shall 
provide control over activities affecting the quality of the identified 
structures, systems, and components to an extent commensurate with the 
importance to safety and, as necessary, to ensure conformance with the 
approved design of each ISFSI, MRS, or spent fuel storage cask. The 
licensee, applicant for a license, certificate holder, and applicant for 
a CoC shall ensure that activities affecting quality are accomplished 
under suitably controlled conditions. Controlled conditions include the 
use of

[[Page 444]]

appropriate equipment; suitable environmental conditions for 
accomplishing the activity, such as adequate cleanliness; and assurance 
that all prerequisites for the given activity have been satisfied. The 
licensee, applicant for a license, certificate holder, and applicant for 
a CoC shall take into account the need for special controls, processes, 
test equipment, tools and skills to attain the required quality and the 
need for verification of quality by inspection and test.
    (c) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall base the requirements and procedures of their 
quality assurance program(s) on the following considerations concerning 
the complexity and proposed use of the structures, systems, or 
components:
    (1) The impact of malfunction or failure of the item on safety;
    (2) The design and fabrication complexity or uniqueness of the item;
    (3) The need for special controls and surveillance over processes 
and equipment;
    (4) The degree to which functional compliance can be demonstrated by 
inspection or test; and
    (5) The quality history and degree of standardization of the item.
    (d) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall provide for indoctrination and training of 
personnel performing activities affecting quality as necessary to ensure 
that suitable proficiency is achieved and maintained.
    (e) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall review the status and adequacy of the quality 
assurance program at established intervals. Management of other 
organizations participating in the quality assurance program must 
regularly review the status and adequacy of that part of the quality 
assurance program which they are executing.



Sec. 72.146  Design control.

    (a) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to ensure that applicable 
regulatory requirements and the design basis, as specified in the 
license or CoC application for those structures, systems, and components 
to which this section applies, are correctly translated into 
specifications, drawings, procedures, and instructions. These measures 
must include provisions to ensure that appropriate quality standards are 
specified and included in design documents and that deviations from 
standards are controlled. Measures must be established for the selection 
and review for suitability of application of materials, parts, 
equipment, and processes that are essential to the functions of the 
structures, systems, and components which are important to safety.
    (b) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures for the identification and 
control of design interfaces and for coordination among participating 
design organizations. These measures must include the establishment of 
written procedures among participating design organizations for the 
review, approval, release, distribution, and revision of documents 
involving design interfaces. The design control measures must provide 
for verifying or checking the adequacy of design by methods such as 
design reviews, alternate or simplified calculational methods, or by a 
suitable testing program. For the verifying or checking process, the 
licensee and certificate holder shall designate individuals or groups 
other than those who were responsible for the original design, but who 
may be from the same organization. Where a test program is used to 
verify the adequacy of a specific design feature in lieu of other 
verifying or checking processes, the licensee and certificate holder 
shall include suitable qualification testing of a prototype or sample 
unit under the most adverse design conditions. The licensee, applicant 
for a license, certificate holder, and applicant for a CoC shall apply 
design control measures to items such as the following: criticality 
physics, radiation, shielding, stress, thermal, hydraulic, and accident 
analyses; compatibility of materials; accessibility for inservice 
inspection, maintenance, and repair; features to facilitate 
decontamination; and delineation of acceptance criteria for inspections 
and tests.

[[Page 445]]

    (c) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall subject design changes, including field 
changes, to design control measures commensurate with those applied to 
the original design. Changes in the conditions specified in the license 
or CoC require prior NRC approval.



Sec. 72.148  Procurement document control.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to assure that applicable 
regulatory requirements, design bases, and other requirements which are 
necessary to assure adequate quality are included or referenced in the 
documents for procurement of material, equipment, and services, whether 
purchased by the licensee, certificate holder, or by their contractors 
and subcontractors. To the extent necessary, the licensee, applicant for 
a license, certificate holder, and applicant for a CoC, shall require 
contractors or subcontractors to provide a quality assurance program 
consistent with the applicable provisions of this subpart.



Sec. 72.150  Instructions, procedures, and drawings.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall prescribe activities affecting quality by 
documented instructions, procedures, or drawings of a type appropriate 
to the circumstances and shall require that these instructions, 
procedures, and drawings be followed. The instructions, procedures, and 
drawings must include appropriate quantitative or qualitative acceptance 
criteria for determining that important activities have been 
satisfactorily accomplished.



Sec. 72.152  Document control.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to control the issuance of 
documents such as instructions, procedures, and drawings, including 
changes, which prescribe all activities affecting quality. These 
measures must assure that documents, including changes, are reviewed for 
adequacy, approved for release by authorized personnel, and distributed 
and used at the location where the prescribed activity is performed. 
These measures must ensure that changes to documents are reviewed and 
approved.



Sec. 72.154  Control of purchased material, equipment, and services.

    (a) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to ensure that purchased 
material, equipment, and services, whether purchased directly or through 
contractors and subcontractors, conform to the procurement documents. 
These measures must include provisions, as appropriate, for source 
evaluation and selection, objective evidence of quality furnished by the 
contractor or subcontractor, inspection at the contractor or 
subcontractor source, and examination of products upon delivery.
    (b) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall have available documentary evidence that 
material and equipment conform to the procurement specifications prior 
to installation or use of the material and equipment. The licensee and 
certificate holder shall retain or have available this documentary 
evidence for the life of the ISFSI, MRS, or spent fuel storage cask. The 
licensee and certificate holder shall ensure that the evidence is 
sufficient to identify the specific requirements met by the purchased 
material and equipment.
    (c) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC, or a designee of either, shall assess the 
effectiveness of the control of quality by contractors and 
subcontractors at intervals consistent with the importance, complexity, 
and quantity of the product or services.



Sec. 72.156  Identification and control of materials, parts, 
and components.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures for the identification and 
control of materials, parts, and components. These measures must ensure 
that identification of the item is maintained by heat number, part 
number, serial number, or other

[[Page 446]]

appropriate means, either on the item or on records traceable to the 
item as required, throughout fabrication, installation, and use of the 
item. These identification and control measures must be designed to 
prevent the use of incorrect or defective materials, parts, and 
components.



Sec. 72.158  Control of special processes.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to ensure that special 
processes, including welding, heat treating, and nondestructive testing, 
are controlled and accomplished by qualified personnel using qualified 
procedures in accordance with applicable codes, standards, 
specifications, criteria, and other special requirements.



Sec. 72.160  Licensee and certificate holder inspection.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish and execute a program for inspection 
of activities affecting quality by or for the organization performing 
the activity to verify conformance with the documented instructions, 
procedures, and drawings for accomplishing the activity. The inspection 
must be performed by individuals other than those who performed the 
activity being inspected. Examinations, measurements, or tests of 
material or products processed must be performed for each work operation 
where necessary to assure quality. If direct inspection of processed 
material or products cannot be carried out, indirect control by 
monitoring processing methods, equipment, and personnel must be 
provided. Both inspection and process monitoring must be provided when 
quality control is inadequate without both. If mandatory inspection hold 
points that require witnessing or inspecting by the licensee's or 
certificate holder's designated representative, and beyond which work 
should not proceed without the consent of its designated representative, 
are required, the specific hold points must be indicated in appropriate 
documents.



Sec. 72.162  Test control.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish a test program to ensure that all 
testing, required to demonstrate that the structures, systems, and 
components will perform satisfactorily in service, is identified and 
performed in accordance with written test procedures that incorporate 
the requirements of this part and the requirements and acceptance limits 
contained in the ISFSI, MRS, or spent fuel storage cask license or CoC. 
The test procedures must include provisions to ensure that all 
prerequisites for the given test are met, that adequate test 
instrumentation is available and used, and that the test is performed 
under suitable environmental conditions. The licensee, applicant for a 
license, certificate holder, and applicant for a CoC shall document and 
evaluate the test results to ensure that test requirements have been 
satisfied.



Sec. 72.164  Control of measuring and test equipment.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to ensure that tools, 
gauges, instruments, and other measuring and testing devices used in 
activities affecting quality are properly controlled, calibrated, and 
adjusted at specified periods to maintain accuracy within necessary 
limits.



Sec. 72.166  Handling, storage, and shipping control.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to control, in accordance 
with work and inspection instructions, the handling, storage, shipping, 
cleaning, and preservation of materials and equipment to prevent damage 
or deterioration. When necessary for particular products, special 
protective environments, such as inert gas atmosphere, and specific 
moisture content and temperature levels must be specified and provided.



Sec. 72.168  Inspection, test, and operating status.

    (a) The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to

[[Page 447]]

indicate, by the use of markings such as stamps, tags, labels, routing 
cards, or other suitable means, the status of inspections and tests 
performed upon individual items of the ISFSI, MRS, or spent fuel storage 
cask. These measures must provide for the identification of items which 
have satisfactorily passed required inspections and tests where 
necessary to preclude inadvertent bypassing of the inspections and 
tests.
    (b) The licensee shall establish measures to identify the operating 
status of structures, systems, and components of the ISFSI or MRS, such 
as tagging valves and switches, to prevent inadvertent operation.



Sec. 72.170  Nonconforming materials, parts, or components.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to control materials, 
parts, or components that do not conform to their requirements in order 
to prevent their inadvertent use or installation. These measures must 
include, as appropriate, procedures for identification, documentation, 
segregation, disposition, and notification to affected organizations. 
Nonconforming items must be reviewed and accepted, rejected, repaired, 
or reworked in accordance with documented procedures.



Sec. 72.172  Corrective action.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall establish measures to ensure that conditions 
adverse to quality, such as failures, malfunctions, deficiencies, 
deviations, defective material and equipment, and nonconformances, are 
promptly identified and corrected. In the case of a significant 
condition identified as adverse to quality, the measures must ensure 
that the cause of the condition is determined and corrective action is 
taken to preclude repetition. The identification of the significant 
condition adverse to quality, the cause of the condition, and the 
corrective action taken must be documented and reported to appropriate 
levels of management.



Sec. 72.174  Quality assurance records.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall maintain sufficient records to furnish 
evidence of activities affecting quality. The records must include the 
following: design records, records of use, and the results of reviews, 
inspections, tests, audits, monitoring of work performance, and 
materials analyses. The records must include closely related data such 
as qualifications of personnel, procedures, and equipment. Inspection 
and test records must, at a minimum, identify the inspector or data 
recorder, the type of observation, the results, the acceptability, and 
the action taken in connection with any noted deficiencies. Records must 
be identifiable and retrievable. Records pertaining to the design, 
fabrication, erection, testing, maintenance, and use of structures, 
systems, and components important to safety must be maintained by or 
under the control of the licensee or certificate holder until the NRC 
terminates the license or CoC.



Sec. 72.176  Audits.

    The licensee, applicant for a license, certificate holder, and 
applicant for a CoC shall carry out a comprehensive system of planned 
and periodic audits to verify compliance with all aspects of the quality 
assurance program and to determine the effectiveness of the program. The 
audits must be performed in accordance with written procedures or 
checklists by appropriately trained personnel not having direct 
responsibilities in the areas being audited. Audited results must be 
documented and reviewed by management having responsibility in the area 
audited. Follow-up action, including reaudit of deficient areas, must be 
taken where indicated.



                      Subpart H_Physical Protection



Sec. 72.180  Physical protection plan.

    The licensee shall establish, maintain, and follow a detailed plan 
for physical protection as described in Sec. 73.51 of this chapter. The 
licensee shall retain a copy of the current plan

[[Page 448]]

as a record until the Commission terminates the license for which the 
procedures were developed and, if any portion of the plan is superseded, 
retain the superseded material for 3 years after each change or until 
termination of the license. The plan must describe how the applicant 
will meet the requirements of Sec. 73.51 of this chapter and provide 
physical protection during on-site transportation to and from the 
proposed ISFSI or MRS and include within the plan the design for 
physical protection, the licensee's safeguards contingency plan, and the 
security organization personnel training and qualification plan. The 
plan must list tests, inspections, audits, and other means to be used to 
demonstrate compliance with such requirements.

[63 FR 26961, May 15, 1998]



Sec. 72.182  Design for physical protection.

    The design for physical protection must show the site layout and the 
design features provided to protect the ISFSI or MRS from sabotage. It 
must include:
    (a) The design criteria for the physical protection of the proposed 
ISFSI or MRS;
    (b) The design bases and the relation of the design bases to the 
design criteria submitted pursuant to paragraph (a) of this section; and
    (c) Information relative to materials of construction, equipment, 
general arrangement, and proposed quality assurance program sufficient 
to provide reasonable assurance that the final security system will 
conform to the design bases for the principal design criteria submitted 
pursuant to paragraph (a) of this section.



Sec. 72.184  Safeguards contingency plan.

    (a) The requirements of the licensee's safeguards contingency plan 
for responding to threats and radiological sabotage must be as defined 
in appendix C to part 73 of this chapter. This plan must include 
Background, Generic Planning Base, Licensee Planning Base, and 
Responsibility Matrix, the first four categories of information relating 
to nuclear facilities licensed under part 50 of this chapter. (The fifth 
and last category of information, Procedures, does not have to be 
submitted for approval.)
    (b) The licensee shall prepare and maintain safeguards contingency 
plan procedures in accordance with appendix C to 10 CFR part 73 for 
effecting the actions and decisions contained in the Responsibility 
Matrix of the licensee's safeguards contingency plan. The licensee shall 
retain a copy of the current procedures as a record until the Commission 
terminates the license for which the procedures were developed and, if 
any portion of the procedures is superseded, retain the superseded 
material for three years after each change.

[53 FR 31658, Aug. 19, 1988, as amended at 57 FR 33429, July 29, 1992]



Sec. 72.186  Change to physical security and safeguards contingency
plans.

    (a) The licensee shall make no change that would decrease the 
safeguards effectiveness of the physical security plan, guard training 
plan or the first four categories of information (Background, Generic 
Planning Base, Licensee Planning Base, and Responsibility Matrix) 
contained in the licensee safeguards contingency plan without prior 
approval of the Commission. A licensee desiring to make a change must 
submit an application for a license amendment pursuant to Sec. 72.56.
    (b) The licensee may, without prior Commission approval, make 
changes to the physical security plan, guard training plan, or the 
safeguards contingency plan, if the changes do not decrease the 
safeguards effectiveness of these plans. The licensee shall maintain 
records of changes to any such plan made without prior approval for a 
period of three years from the date of the change, and shall, within two 
months after the change is made, submit a report addressed to Director, 
Division of Spent Fuel Management, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, in accordance with Sec. 
72.4, containing a description of each change. A copy of the report must 
be sent to the Regional Administrator of the appropriate NRC

[[Page 449]]

Regional Office specified in appendix A to part 73 of this chapter.

[53 FR 31658, Aug. 19, 1988, as amended at 67 FR 3586, Jan. 25, 2002; 68 
FR 58819, Oct. 10, 2003; 75 FR 73945, Nov. 30, 2010; 79 FR 75741, Dec. 
19, 2014]



            Subpart I_Training and Certification of Personnel



Sec. 72.190  Operator requirements.

    Operation of equipment and controls that have been identified as 
important to safety in the Safety Analysis Report and in the license 
must be limited to trained and certified personnel or be under the 
direct visual supervision of an individual with training and 
certification in the operation. Supervisory personnel who personally 
direct the operation of equipment and controls that are important to 
safety must also be certified in such operations.



Sec. 72.192  Operator training and certification program.

    The applicant for a license under this part shall establish a 
program for training, proficiency testing, and certification of ISFSI or 
MRS personnel. This program must be submitted to the Commission for 
approval with the license application.



Sec. 72.194  Physical requirements.

    The physical condition and the general health of personnel certified 
for the operation of equipment and controls that are important to safety 
must not be such as might cause operational errors that could endanger 
other in-plant personnel or the public health and safety. Any condition 
that might cause impaired judgment or motor coordination must be 
considered in the selection of personnel for activities that are 
important to safety. These conditions need not categorically disqualify 
a person, if appropriate provisions are made to accommodate such defect.



 Subpart J_Provision of MRS Information to State Governments and Indian 
                                 Tribes



Sec. 72.200  Provision of MRS information.

    (a) The Director, Office of Nuclear Material Safety and Safeguards, 
or the Director's designee shall provide to the Governor and legislature 
of any State in which an MRS authorized under the Nuclear Waste Policy 
Act of 1982, as amended, is or may be located, to the Governors of any 
contiguous States, to each affected unit of local government and to the 
governing body of any affected Indian Tribe, timely and complete 
information regarding determinations or plans made by the Commission 
with respect to siting, development, design, licensing, construction, 
operation, regulation or decommissioning of such monitored retrievable 
storage facility.
    (b) Notwithstanding paragraph (a) of this section, the Director or 
the Director's designee is not required to distribute any document to 
any entity if, with respect to such document, that entity or its counsel 
is included on a service list prepared pursuant to part 2 of this 
chapter.
    (c) Copies of all communications by the Director or the Director's 
designee under this section must be made available at the NRC Web site, 
http://www.nrc.gov, and/or at the NRC Public Document Room, and must be 
furnished to DOE.

[53 FR 31658, Aug. 19, 1988, as amended at 64 FR 48954, Sept. 9, 1999]



Sec. 72.202  Participation in license reviews.

    States, local governmental bodies and affected, Federally-recognized 
Indian Tribes may participate in license reviews as provided in Subpart 
C of Part 2 of this chapter.

[69 FR 2280, Jan. 14, 2004]



Sec. 72.204  Notice to States.

    If the Governor and legislature of a State have jointly designated 
on their behalf a single person or entity to receive notice and 
information from the Commission under this part, the Commission will 
provide such notice and information to the jointly designated

[[Page 450]]

person or entity instead of the Governor and the legislature separately.



Sec. 72.206  Representation.

    Any person who acts under this subpart as a representative for a 
State (or for the Governor or legislature thereof) or for an affected 
Indian Tribe shall include in the request or other submission, or at the 
request of the Commission, a statement of the basis of his or her 
authority to act in such representative capacity.



  Subpart K_General License for Storage of Spent Fuel at Power Reactor 
                                  Sites

    Source: 55 FR 29191, July 18, 1990, unless otherwise noted.



Sec. 72.210  General license issued.

    A general license is hereby issued for the storage of spent fuel in 
an independent spent fuel storage installation at power reactor sites to 
persons authorized to possess or operate nuclear power reactors under 10 
CFR part 50 or 10 CFR part 52.

[72 FR 49561, Aug. 28, 2007]



Sec. 72.212  Conditions of general license issued under Sec. 72.210.

    (a)(1) The general license is limited to that spent fuel which the 
general licensee is authorized to possess at the site under the specific 
license for the site.
    (2) This general license is limited to storage of spent fuel in 
casks approved under the provisions of this part.
    (3) The general license for the storage of spent fuel in each cask 
fabricated under a Certificate of Compliance shall commence upon the 
date that the particular cask is first used by the general licensee to 
store spent fuel, shall continue through any renewals of the Certificate 
of Compliance, unless otherwise specified in the Certificate of 
Compliance, and shall terminate when the cask's Certificate of 
Compliance expires. For any cask placed into service during the final 
renewal term of a Certificate of Compliance, or during the term of a 
Certificate of Compliance that was not renewed, the general license for 
that cask shall terminate after a storage period not to exceed the 
length of the term certified by the cask's Certificate of Compliance. 
Upon expiration of the general license, all casks subject to that 
general license must be removed from service.
    (b) The general licensee must:
    (1) Notify the Nuclear Regulatory Commission using instructions in 
Sec. 72.4 at least 90 days before first storage of spent fuel under 
this general license. The notice may be in the form of a letter, but 
must contain the licensee's name, address, reactor license and docket 
numbers, and the name and means of contacting a person responsible for 
providing additional information concerning spent fuel under this 
general license. A copy of the submittal must be sent to the 
administrator of the appropriate Nuclear Regulatory Commission regional 
office listed in appendix D to part 20 of this chapter.
    (2) Register use of each cask with the Nuclear Regulatory Commission 
no later than 30 days after using that cask to store spent fuel. This 
registration may be accomplished by submitting a letter using 
instructions in Sec. 72.4 containing the following information: the 
licensee's name and address, the licensee's reactor license and docket 
numbers, the name and title of a person responsible for providing 
additional information concerning spent fuel storage under this general 
license, the cask certificate number, the CoC amendment number to which 
the cask conforms, unless loaded under the initial certificate, cask 
model number, and the cask identification number. A copy of each 
submittal must be sent to the administrator of the appropriate Nuclear 
Regulatory Commission regional office listed in appendix D to part 20 of 
this chapter.
    (3) Ensure that each cask used by the general licensee conforms to 
the terms, conditions, and specifications of a CoC or an amended CoC 
listed in Sec. 72.214.
    (4) In applying the changes authorized by an amended CoC to a cask 
loaded under the initial CoC or an earlier amended CoC, register each 
such cask with the Nuclear Regulatory Commission no later than 30 days 
after applying the changes authorized by the amended CoC. This 
registration may be

[[Page 451]]

accomplished by submitting a letter using instructions in Sec. 72.4 
containing the following information: the licensee's name and address, 
the licensee's reactor license and docket numbers, the name and title of 
a person responsible for providing additional information concerning 
spent fuel storage under this general license, the cask certificate 
number, the CoC amendment number to which the cask conforms, cask model 
number, and the cask identification number. A copy of each submittal 
must be sent to the administrator of the appropriate Nuclear Regulatory 
Commission regional office listed in appendix D to part 20 of this 
chapter.
    (5) Perform written evaluations, before use and before applying the 
changes authorized by an amended CoC to a cask loaded under the initial 
CoC or an earlier amended CoC, which establish that:
    (i) The cask, once loaded with spent fuel or once the changes 
authorized by an amended CoC have been applied, will conform to the 
terms, conditions, and specifications of a CoC or an amended CoC listed 
in Sec. 72.214;
    (ii) Cask storage pads and areas have been designed to adequately 
support the static and dynamic loads of the stored casks, considering 
potential amplification of earthquakes through soil-structure 
interaction, and soil liquefaction potential or other soil instability 
due to vibratory ground motion; and
    (iii) The requirements of Sec. 72.104 have been met. A copy of this 
record shall be retained until spent fuel is no longer stored under the 
general license issued under Sec. 72.210.
    (6) Review the Safety Analysis Report referenced in the CoC or 
amended CoC and the related NRC Safety Evaluation Report, prior to use 
of the general license, to determine whether or not the reactor site 
parameters, including analyses of earthquake intensity and tornado 
missiles, are enveloped by the cask design bases considered in these 
reports. The results of this review must be documented in the evaluation 
made in paragraph (b)(5) of this section.
    (7) Evaluate any changes to the written evaluations required by 
paragraphs (b)(5) and (b)(6) of this section using the requirements of 
Sec. 72.48(c). A copy of this record shall be retained until spent fuel 
is no longer stored under the general license issued under Sec. 72.210.
    (8) Before use of the general license, determine whether activities 
related to storage of spent fuel under this general license involve a 
change in the facility Technical Specifications or require a license 
amendment for the facility pursuant to Sec. 50.59(c) of this chapter. 
Results of this determination must be documented in the evaluations made 
in paragraph (b)(5) of this section.
    (9) Protect the spent fuel against the design basis threat of 
radiological sabotage in accordance with the same provisions and 
requirements as are set forth in the licensee's physical security plan 
pursuant to Sec. 73.55 of this chapter with the following additional 
conditions and exceptions:
    (i) The physical security organization and program for the facility 
must be modified as necessary to assure that activities conducted under 
this general license do not decrease the effectiveness of the protection 
of vital equipment in accordance with Sec. 73.55 of this chapter;
    (ii) Storage of spent fuel must be within a protected area, in 
accordance with Sec. 73.55(e) of this chapter, but need not be within a 
separate vital area. Existing protected areas may be expanded or new 
protected areas added for the purpose of storage of spent fuel in 
accordance with this general license;
    (iii) For the purpose of this general license, personnel searches 
required by Sec. 73.55(h) of this chapter before admission to a new 
protected area may be performed by physical pat-down searches of persons 
in lieu of firearms and explosives detection equipment;
    (iv) The observational capability required by Sec. 73.55(i)(3) of 
this chapter as applied to a new protected area may be provided by a 
guard or watchman on patrol in lieu of video surveillance technology;
    (v) For the purpose of this general license, the licensee is exempt 
from requirements to interdict and neutralize threats in Sec. 73.55 of 
this chapter; and
    (vi) Each general licensee that receives and possesses power reactor

[[Page 452]]

spent fuel and other radioactive materials associated with spent fuel 
storage shall protect Safeguards Information against unauthorized 
disclosure in accordance with the requirements of Sec. 73.21 and the 
requirements of Sec. 73.22 or Sec. 73.23 of this chapter, as 
applicable.
    (10) Review the reactor emergency plan, quality assurance program, 
training program, and radiation protection program to determine if their 
effectiveness is decreased and, if so, prepare the necessary changes and 
seek and obtain the necessary approvals.
    (11) Maintain a copy of the CoC and, for those casks to which the 
licensee has applied the changes of an amended CoC, the amended CoC, and 
the documents referenced in such Certificates, for each cask model used 
for storage of spent fuel, until use of the cask model is discontinued. 
The licensee shall comply with the terms, conditions, and specifications 
of the CoC and, for those casks to which the licensee has applied the 
changes of an amended CoC, the terms, conditions, and specifications of 
the amended CoC, including but not limited to, the requirements of any 
AMP put into effect as a condition of the NRC approval of a CoC renewal 
application in accordance with Sec. 72.240.
    (12) Accurately maintain the record provided by the CoC holder for 
each cask that shows, in addition to the information provided by the CoC 
holder, the following:
    (i) The name and address of the CoC holder or lessor;
    (ii) The listing of spent fuel stored in the cask; and
    (iii) Any maintenance performed on the cask.
    (13) Conduct activities related to storage of spent fuel under this 
general license only in accordance with written procedures.
    (14) Make records and casks available to the Commission for 
inspection.
    (c) The record described in paragraph (b)(12) of this section must 
include sufficient information to furnish documentary evidence that any 
testing and maintenance of the cask has been conducted under an NRC-
approved quality assurance program.
    (d) In the event that a cask is sold, leased, loaned, or otherwise 
transferred to another registered user, the record described in 
paragraph (b)(12) of this section must also be transferred to and must 
be accurately maintained by the new registered user. This record must be 
maintained by the current cask user during the period that the cask is 
used for storage of spent fuel and retained by the last user until 
decommissioning of the cask is complete.
    (e) Fees for inspections related to spent fuel storage under this 
general license are those shown in Sec. 170.31 of this chapter.

[55 FR 29191, July 18, 1990, as amended at 64 FR 53616, Oct. 4, 1999; 68 
FR 54160, Sept. 16, 2003; 73 FR 63573, Oct. 24, 2008; 74 FR 13970, Mar. 
27, 2009; 76 FR 8890, Feb. 16, 2011]



Sec. 72.214  List of approved spent fuel storage casks.

    The following casks are approved for storage of spent fuel under the 
conditions specified in their Certificates of Compliance.

Certificate Number: 1004.
Initial Certificate Effective Date: January 23, 1995, superseded by 
Initial Certificate, Revision 1, on April 25, 2017, superseded by 
Renewed Initial Certificate, Revision 1, on December 11, 2017.
Initial Certificate, Revision 1, Effective Date: April 25, 2017.
Renewed Initial Certificate, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 1 Effective Date: April 27, 2000, superseded by 
Amendment Number 1, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 1, Revision 1, on December 11, 2017.
Amendment Number 1, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 1, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 2 Effective Date: September 5, 2000, superseded by 
Amendment Number 2, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 2, Revision 1, on December 11, 2017.
Amendment Number 2, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 2, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 3 Effective Date: September 12, 2001, superseded by 
Amendment Number 3, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 3, Revision 1, on December 11, 2017.
Amendment Number 3, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 3, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 4 Effective Date: February 12, 2002, superseded by 
Amendment

[[Page 453]]

Number 4, Revision 1, on April 25, 2017, superseded by Renewed Amendment 
Number 4, Revision 1, on December 11, 2017.
Amendment Number 4, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 4, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 5 Effective Date: January 7, 2004, superseded by 
Amendment Number 5, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 5, Revision 1, on December 11, 2017.
Amendment Number 5, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 5, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 6 Effective Date: December 22, 2003, superseded by 
Amendment Number 6, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 6, Revision 1, on December 11, 2017.
Amendment Number 6, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 6, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 7 Effective Date: March 2, 2004, superseded by 
Amendment Number 7, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 7, Revision 1, on December 11, 2017.
Amendment Number 7, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 7, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 8 Effective Date: December 5, 2005, superseded by 
Amendment Number 8, Revision 1 on April 25, 2017, superseded by Renewed 
Amendment Number 8, Revision 1, on December 11, 2017.
Amendment Number 8, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 8, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 9 Effective Date: April 17, 2007, superseded by 
Amendment Number 9, Revision 1, on April 25, 2017, superseded by Renewed 
Amendment Number 9, Revision 1, on December 11, 2017.
Amendment Number 9, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 9, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 10 Effective Date: August 24, 2009, superseded by 
Amendment Number 10, Revision 1, on April 25, 2017, superseded by 
Renewed Amendment Number 10, Revision 1, on December 11, 2017.
Amendment Number 10, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 10, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 11 Effective Date: January 7, 2014, superseded by 
Amendment Number 11, Revision 1, on April 25, 2017, superseded by 
Renewed Amendment Number 11, Revision 1, on December 11, 2017.
Amendment Number 11, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 11, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 12 Effective Date: Amendment not issued by the NRC.
Amendment Number 13 Effective Date: May 24, 2014, superseded by 
Amendment Number 13, Revision 1, on April 25, 2017, superseded by 
Renewed Amendment Number 13, Revision 1, on December 11, 2017.
Amendment Number 13, Revision 1, Effective Date: April 25, 2017.
Renewed Amendment Number 13, Revision 1, Effective Date: December 11, 
2017.
Amendment Number 14 Effective Date: April 25, 2017, superseded by 
Renewed Amendment Number 14, on December 11, 2017.
Renewed Amendment Number 14 Effective Date: December 11, 2017.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the Standardized 
NUHOMS[supreg] Horizontal Modular Storage System for Irradiated Nuclear 
Fuel.
Docket Number: 72-1004.
Certificate Expiration Date: January 23, 2015.
Renewed Certificate Expiration Date: January 23, 2055.
Model Number: NUHOMS[supreg]-24P, -24PHB, -24PTH, -32PT, -32PTH1, -
37PTH, -52B, -61BT, -61BTH, and -69BTH.

Certificate Number: 1007.
Initial Certificate Effective Date: May 7, 1993, superseded by Renewed 
Initial Certificate, on September 20, 2017.
Renewed Initial Certificate Effective Date: September 20, 2017.
Amendment Number 1 Effective Date: May 30, 2000, superseded by Renewed 
Amendment Number 1, on September 20, 2017.
Renewed Amendment Number 1 Effective Date: September 20, 2017.
Amendment Number 2 Effective Date: September 5, 2000, superseded by 
Renewed Amendment Number 2, on September 20, 2017.
Renewed Amendment Number 2 Effective Date: September 20, 2017.
Amendment Number 3 Effective Date: May 21, 2001, superseded by Renewed 
Amendment Number 3, on September 20, 2017.
Renewed Amendment Number 3 Effective Date: September 20, 2017.
Amendment Number 4 Effective Date: February 3, 2003, superseded by 
Renewed Amendment Number 4, on September 20, 2017.
Renewed Amendment Number 4 Effective Date: September 20, 2017.
Amendment Number 5 Effective Date: September 13, 2005, superseded by 
Renewed Amendment Number 5, on September 20, 2017.
Renewed Amendment Number 5 Effective Date: September 20, 2017.

[[Page 454]]

Amendment Number 6 Effective Date: June 5, 2006, superseded by Renewed 
Amendment Number 6, on September 20, 2017.
Renewed Amendment Number 6 Effective Date: September 20, 2017.
SAR Submitted by: EnergySolutionsTM Corporation.
SAR Title: Final Safety Analysis Report for the VSC-24 Ventilated 
Storage Cask System.
Docket Number: 72-1007.
Renewed Certificate Expiration Date: May 7, 2053.
Model Number: VSC-24.

Certificate Number: 1008.
Initial Certificate Effective Date: October 4, 1999.
Amendment Number 1 Effective Date: December 26, 2000.
Amendment Number 2 Effective Date: May 29, 2001.
SAR Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STAR 100 Cask System.
Docket Number: 72-1008.
Certificate Expiration Date: October 4, 2019.
Model Number: HI-STAR 100.

Certificate No.:1014.
 Initial Certificate Effective Date: May 31, 2000.
Amendment Number 1 Effective Date: July 15, 2002.
Amendment Number 2 Effective Date: June 7, 2005.
Amendment Number 3 Effective Date: May 29, 2007.
Amendment Number 4 Effective Date: January 8, 2008.
Amendment Number 5 Effective Date: July 14, 2008.
Amendment Number 6 Effective Date: August 17, 2009.
Amendment Number 7 Effective Date: December 28, 2009.
Amendment Number 8 Effective Date: May 2, 2012, as corrected on November 
16, 2012 (ADAMS Accession No. ML12213A170); superseded by Amendment 
Number 8, Revision 1, Effective Date: February 16, 2016.
Amendment Number 8, Revision 1, Effective Date February 16, 2016.
Amendment Number 9 Effective Date: March 11, 2014, superseded by 
Amendment Number 9, Revision 1, on March 21, 2016.
Amendment Number 9, Revision 1, Effective Date: March 21, 2016, as 
corrected (ADAMS Accession No. ML17236A451).
Amendment Number 10 Effective Date: May 31, 2016, as corrected (ADAMS 
Accession No. ML17236A452).
Safety Analysis Report (SAR) Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask 
System.
Docket Number: 72-1014.
Certificate Expiration Date: May 31, 2020.
Model Number HI-STORM 100.

Certificate Number: 1015.
Initial Certificate Effective Date: November 20, 2000.
Amendment Number 1 Effective Date: February 20, 2001.
Amendment Number 2 Effective Date: December 31, 2001.
Amendment Number 3 Effective Date: March 31, 2004.
Amendment Number 4 Effective Date: October 11, 2005.
Amendment Number 5 Effective Date: January 12, 2009.
SAR Submitted by: NAC International, Inc.
SAR Title: Final Safety Analysis Report for the NAC-UMS Universal 
Storage System.
Docket Number: 72-1015.
Certificate Expiration Date: November 20, 2020.
Model Number: NAC-UMS.

Certificate Number: 1021.
Initial Certificate Effective Date: April 19, 2000.
Amendment Number 1 Effective Date: February 20, 2001.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the TN-32 Dry Storage Cask.
Docket Number: 72-1021.
Certificate Expiration Date: April 19, 2020.
Model Number: TN-32, TN-32A, TN-32B.

Certificate Number: 1025.
Initial Certificate Effective Date: April 10, 2000.
Amendment Number 1 Effective Date: November 13, 2001.
Amendment Number 2 Effective Date: May 29, 2002.
Amendment Number 3 Effective Date: October 1, 2003.
Amendment Number 4 Effective Date: October 27, 2004.
Amendment Number 5 Effective Date: July 24, 2007.
Amendment Number 6 Effective Date: October 4, 2010.
SAR Submitted by: NAC International, Inc.
SAR Title: Final Safety Analysis Report for the NAC Multi-Purpose 
Canister System (NAC-MPC System).
Docket Number: 72-1025.
Certificate Expiration Date: April 10, 2020.
Model Number: NAC-MPC.

Certificate Number: 1026.
Initial Certificate Effective Date: February 15, 2001.
Amendment Number 1 Effective Date: May 14, 2001.
Amendment Number 2 Effective Date: January 28, 2002.
Amendment Number 3 Effective Date: May 7, 2003.
Amendment Number 4 Effective Date: July 3, 2006.

[[Page 455]]

SAR Submitted by: BNG Fuel Solutions Corporation.
SAR Title: Final Safety Analysis Report for the FuelSolutions\TM\ Spent 
Fuel Management System.
Docket Number: 72-1026.
Certificate Expiration Date: February 15, 2021.
Model Number: WSNF-220, WSNF-221, and WSNF-223 systems; W-150 storage 
cask; W-100 transfer cask; and the W-21 and W-74 canisters.

Certificate Number: 1027.
Initial Certificate Effective Date: May 30, 2000.
Amendment Number 1 Effective Date: October 30, 2007.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the TN-68 Dry Storage Cask.
Docket Number: 72-1027.
Certificate Expiration Date: May 28, 2020.
Model Number: TN-68.

Certificate Number: 1029.
Initial Certificate Effective Date: February 5, 2003.
Amendment Number 1 Effective Date: May 16, 2005.
Amendment Number 2 Effective Date: Amendment not issued by the NRC.
Amendment Number 3 Effective Date: February 23, 2015.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the Standardized Advanced 
NUHOMS[supreg] Horizontal
Modular Storage System for Irradiated Nuclear Fuel.
Docket Number: 72-1029.
Certificate Expiration Date: February 5, 2023.
Model Number: Standardized Advanced NUHOMS[supreg] -24PT1, -24PT4, and -
32PTH2.

Certificate Number: 1030.
Initial Certificate Effective Date: January 10, 2007.
Amendment Number 1 Effective Date: March 29, 2011.
Amendment Number 2 Effective Date: October 14, 2014.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the NUHOMS[supreg] HD 
Horizontal Modular Storage System for Irradiated Nuclear Fuel.
Docket Number: 72-1030.
Certificate Expiration Date: January 10, 2027.
Model Number: NUHOMS[supreg] HD-32PTH.

Certificate Number: 1031.
Initial Certificate Effective Date: February 4, 2009, superseded by 
Initial Certificate, Revision 1, on February 1, 2016.
Initial Certificate, Revision 1, Effective Date: February 1, 2016.
Amendment Number 1 Effective Date: August 30, 2010, superseded by 
Amendment Number 1, Revision 1, on February 1, 2016.
Amendment Number 1, Revision 1, Effective Date: February 1, 2016.
Amendment Number 2 Effective Date: January 30, 2012, superseded by 
Amendment Number 2, Revision 1, on February 1, 2016.
Amendment Number 2, Revision 1, Effective Date: February 1, 2016.
Amendment Number 3 Effective Date: July 25, 2013, superseded by 
Amendment Number 3, Revision 1, on February 1, 2016.
Amendment Number 3, Revision 1, Effective Date: February 1, 2016.
Amendment Number 4 Effective Date: April 14, 2015.
Amendment Number 5 Effective Date: June 29, 2015.
Amendment Number 6 Effective Date: December 21, 2016.
Amendment Number 7 Effective Date: August 21, 2017.
SAR Submitted by: NAC International, Inc.
SAR Title: Final Safety Analysis Report for the MAGNASTOR[supreg] 
System.
Docket Number: 72-1031.
Certificate Expiration Date: February 4, 2029.
Model Number: MAGNASTOR[supreg].

Certificate Number: 1032.
Initial Certificate Effective Date: June 13, 2011, superseded by 
Amendment Number 0, Revision 1, on April 25, 2016.
Amendment Number 0, Revision 1, Effective Date: April 25, 2016.
Amendment Number 1 Effective Date: December 17, 2014, superseded by 
Amendment Number 1, Revision 1, on June 2, 2015.
Amendment Number 1, Revision 1, Effective Date: June 2, 2015.
Amendment Number 2 Effective Date: November 7, 2016.
Amendment Number 3 Effective Date: September 11, 2017.
SAR Submitted by: Holtec International, Inc.
SAR Title: Final Safety Analysis Report for the Holtec International HI-
STORM FW System.
Docket Number: 72-1032.
Certificate Expiration Date: June 12, 2031.
Model Number: HI-STORM FW MPC-37, MPC-89.

Certificate Number: 1040.
Initial Certificate Effective Date: April 6, 2015.
Amendment Number 1 Effective Date: September 8, 2015.
Amendment Number 2, Effective Date: January 9, 2017.
SAR Submitted by: Holtec International, Inc.
SAR Title: Final Safety Analysis Report for the Holtec International HI-
STORM UMAX Canister Storage System.
Docket Number: 72-1040.

[[Page 456]]

Certificate Expiration Date: April 6, 2035.
Model Number: MPC-37, MPC-89.

Certificate Number: 1042.
Initial Certificate Effective Date: June 7, 2017.
SAR Submitted by: TN Americas LLC.
SAR Title: Final Safety Analysis Report for the NUHOMS[supreg] EOS Dry 
Spent Fuel Storage System.
Docket Number: 72-1042.
Certificate Expiration Date: June 7, 2037.
Model Number: EOS-37PTH, EOS-89BTH.

[55 FR 29191, July 18, 1990]

    Editorial Note: For Federal Register citations affecting Sec. 
72.214, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 72.216  [Reserved]



Sec. 72.218  Termination of licenses.

    (a) The notification regarding the program for the management of 
spent fuel at thev reactor required by Sec. 50.54(bb) of this chapter 
must include a plan for removal of the spent fuel stored under this 
general license from the reactor site. The plan must show how the spent 
fuel will be managed before starting to decommission systems and 
components needed for moving, unloading, and shipping this spent fuel.
    (b) An application for termination of a reactor operating license 
issued under 10 CFR part 50 and submitted under Sec. 50.82 of this 
chapter, or a combined license issued under 10 CFR part 52 and submitted 
under Sec. 52.110 of this chapter, must contain a description of how 
the spent fuel stored under this general license will be removed from 
the reactor site.
    (c) The reactor licensee shall send a copy of submittals under Sec. 
72.218(a) and (b) to the administrator of the appropriate Nuclear 
Regulatory Commission regional office shown in appendix D to part 20 of 
this chapter.

[55 FR 29191, July 18, 1990, as amended at 72 FR 49561, Aug. 28, 2007]



Sec. 72.220  Violations.

    This general license is subject to the provisions of Sec. 72.84 for 
violation of the regulations under this part.



             Subpart L_Approval of Spent Fuel Storage Casks

    Source: 55 FR 29193, July 18, 1990, unless otherwise noted.



Sec. 72.230  Procedures for spent fuel storage cask submittals.

    (a) An application for approval of a spent fuel storage cask design 
must be submitted in accordance with the instructions contained in Sec. 
72.4. A safety analysis report describing the proposed cask design and 
how the cask should be used to store spent fuel safely must be included 
with the application.
    (b) Casks that have been certified for transportation of spent fuel 
under part 71 of this chapter may be approved for storage of spent fuel 
under this subpart. An application must be submitted in accordance with 
the instructions contained in Sec. 72.4, for a proposed term not to 
exceed 40 years. A copy of the CoC issued for the cask under part 71 of 
this chapter, and drawings and other documents referenced in the 
certificate, must be included with the application. A safety analysis 
report showing that the cask is suitable for storage of spent fuel, for 
the term proposed in the application, must also be included.
    (c) Public inspection. An application for the approval of a cask for 
storage of spent fuel may be made available for public inspection under 
Sec. 72.20.
    (d) Fees. Fees for reviews and evaluations related to issuance of a 
spent fuel storage cask Certificate of Compliance and inspections 
related to storage cask fabrication are those shown in Sec. 170.31 of 
this chapter.

[55 FR 29193, July 18, 1990, as amended at 76 FR 8891, Feb. 16, 2011]



Sec. 72.232  Inspection and tests.

    (a) The certificate holder and applicant for a CoC shall permit, and 
make provisions for, the NRC to inspect the premises and facilities 
where a spent fuel storage cask is designed, fabricated, and tested.
    (b) The certificate holder and applicant for a CoC shall make 
available to the NRC for inspection, upon reasonable notice, records 
kept by them pertaining to the design, fabrication, and testing of spent 
fuel storage casks.

[[Page 457]]

    (c) The certificate holder and applicant for a CoC shall perform, 
and make provisions that permit the NRC to perform, tests that the 
Commission deems necessary or appropriate for the administration of the 
regulations in this part.
    (d) The certificate holder and applicant for a CoC shall submit a 
notification under Sec. 72.4 at least 45 days prior to starting 
fabrication of the first spent fuel storage cask under a Certificate of 
Compliance.

[64 FR 56126, Oct. 15, 1999]



Sec. 72.234  Conditions of approval.

    (a) The certificate holder and applicant for a CoC shall ensure that 
the design, fabrication, testing, and maintenance of a spent fuel 
storage cask comply with the requirements in Sec. 72.236.
    (b) The certificate holder and applicant for a CoC shall ensure that 
the design, fabrication, testing, and maintenance of spent fuel storage 
casks are conducted under a quality assurance program that meets the 
requirements of subpart G of this part.
    (c) An applicant for a CoC may begin fabrication of spent fuel 
storage casks before the Commission issues a CoC for the cask; however, 
applicants who begin fabrication of casks without a CoC do so at their 
own risk. A cask fabricated before the CoC is issued shall be made to 
conform to the issued CoC before being placed in service or before spent 
fuel is loaded.
    (d)(1) The certificate holder shall ensure that a record is 
established and maintained for each spent fuel storage cask fabricated 
under the CoC.
    (2) This record must include:
    (i) The NRC CoC number;
    (ii) The spent fuel storage cask model number;
    (iii) The spent fuel storage cask identification number;
    (iv) Date fabrication was started;
    (v) Date fabrication was completed;
    (vi) Certification that the spent fuel storage cask was designed, 
fabricated, tested, and repaired in accordance with a quality assurance 
program accepted by NRC;
    (vii) Certification that inspections required by Sec. 72.236(j) 
were performed and found satisfactory; and
    (viii) The name and address of the licensee using the spent fuel 
storage cask.
    (3) The certificate holder shall supply the original of this record 
to the licensees using the spent fuel storage cask. A current copy of a 
composite record of all spent fuel storage casks manufactured under a 
CoC, showing the information in paragraph (d)(2) of this section, must 
be initiated and maintained by the certificate holder for each model 
spent fuel storage cask. If the certificate holder permanently ceases 
production of spent fuel storage casks under a CoC, the certificate 
holder shall send this composite record to the Commission using 
instructions in Sec. 72.4.
    (e) The certificate holder and the licensees using the spent fuel 
storage cask shall ensure that the composite record required by 
paragraph (d) of this section is available to the Commission for 
inspection.
    (f) The certificate holder shall ensure that written procedures and 
appropriate tests are established prior to use of the spent fuel storage 
casks. A copy of these procedures and tests must be provided to each 
licensee using the spent fuel storage cask.

[64 FR 56126, Oct. 15, 1999, as amended at 65 FR 50617, Aug. 21, 2000]



Sec. 72.236  Specific requirements for spent fuel storage cask
approval and fabrication.

    The certificate holder and applicant for a CoC shall ensure that the 
requirements of this section are met.
    (a) Specifications must be provided for the spent fuel to be stored 
in the spent fuel storage cask, such as, but not limited to, type of 
spent fuel (i.e., BWR, PWR, both), maximum allowable enrichment of the 
fuel prior to any irradiation, burn-up (i.e., megawatt-days/MTU), 
minimum acceptable cooling time of the spent fuel prior to storage in 
the spent fuel storage cask, maximum heat designed to be dissipated, 
maximum spent fuel loading limit, condition of the spent fuel (i.e., 
intact assembly or consolidated fuel rods), the inerting atmosphere 
requirements.
    (b) Design bases and design criteria must be provided for 
structures, systems, and components important to safety.

[[Page 458]]

    (c) The spent fuel storage cask must be designed and fabricated so 
that the spent fuel is maintained in a subcritical condition under 
credible conditions.
    (d) Radiation shielding and confinement features must be provided 
sufficient to meet the requirements in Sec. Sec. 72.104 and 72.106.
    (e) The spent fuel storage cask must be designed to provide 
redundant sealing of confinement systems.
    (f) The spent fuel storage cask must be designed to provide adequate 
heat removal capacity without active cooling systems.
    (g) The spent fuel storage cask must be designed to store the spent 
fuel safely for the term proposed in the application, and permit 
maintenance as required.
    (h) The spent fuel storage cask must be compatible with wet or dry 
spent fuel loading and unloading facilities.
    (i) The spent fuel storage cask must be designed to facilitate 
decontamination to the extent practicable.
    (j) The spent fuel storage cask must be inspected to ascertain that 
there are no cracks, pinholes, uncontrolled voids, or other defects that 
could significantly reduce its confinement effectiveness.
    (k) The spent fuel storage cask must be conspicuously and durably 
marked with--
    (1) A model number;
    (2) A unique identification number; and
    (3) An empty weight.
    (l) The spent fuel storage cask and its systems important to safety 
must be evaluated, by appropriate tests or by other means acceptable to 
the NRC, to demonstrate that they will reasonably maintain confinement 
of radioactive material under normal, off-normal, and credible accident 
conditions.
    (m) To the extent practicable in the design of spent fuel storage 
casks, consideration should be given to compatibility with removal of 
the stored spent fuel from a reactor site, transportation, and ultimate 
disposition by the Department of Energy.
    (n) Safeguards Information shall be protected against unauthorized 
disclosure in accordance with the requirements of Sec. 73.21 and the 
requirements of Sec. 73.22 or Sec. 73.23 of this chapter, as 
applicable.

[64 FR 56126, Oct. 15, 1999, as amended at 65 FR 50617, Aug. 21, 2000; 
73 FR 63573, Oct. 24, 2008; 76 FR 8891, Feb. 16, 2011]



Sec. 72.238  Issuance of an NRC Certificate of Compliance.

    A Certificate of Compliance for a cask model will be issued by NRC 
for a term not to exceed 40 years on a finding that the requirements in 
Sec. 72.236(a) through (i) are met.

[76 FR 8891, Feb. 16, 2011]



Sec. 72.240  Conditions for spent fuel storage cask renewal.

    (a) The certificate holder may apply for renewal of the design of a 
spent fuel storage cask for a term not to exceed 40 years. In the event 
that the certificate holder does not apply for a cask design renewal, 
any licensee using a spent fuel storage cask, a representative of such 
licensee, or another certificate holder may apply for a renewal of that 
cask design for a term not to exceed 40 years.
    (b) The application for renewal of the design of a spent fuel 
storage cask must be submitted not less than 30 days before the 
expiration date of the CoC. When the applicant has submitted a timely 
application for renewal, the existing CoC will not expire until the 
application for renewal has been determined by the NRC.
    (c) The application must be accompanied by a safety analysis report 
(SAR). The SAR must include the following:
    (1) Design bases information as documented in the most recently 
updated final safety analysis report (FSAR) as required by Sec. 72.248;
    (2) Time-limited aging analyses that demonstrate that structures, 
systems, and components important to safety will continue to perform 
their intended function for the requested period of extended operation; 
and
    (3) A description of the AMP for management of issues associated 
with aging that could adversely affect structures, systems, and 
components important to safety.
    (d) The design of a spent fuel storage cask will be renewed if the 
conditions in subpart G of this part and Sec. 72.238 are

[[Page 459]]

met, and the application includes a demonstration that the storage of 
spent fuel has not, in a significant manner, adversely affected 
structures, systems, and components important to safety.
    (e) In approving the renewal of the design of a spent fuel storage 
cask, the NRC may revise the CoC to include terms, conditions, and 
specifications that will ensure the safe operation of the cask during 
the renewal term, including but not limited to, terms, conditions, and 
specifications that will require the implementation of an AMP.

[76 FR 8891, Feb. 16, 2011]



Sec. 72.242  Recordkeeping and reports.

    (a) Each certificate holder or applicant shall maintain any records 
and produce any reports that may be required by the conditions of the 
CoC or by the rules, regulations, and orders of the NRC in effectuating 
the purposes of the Act.
    (b) Records that are required by the regulations in this part or by 
conditions of the CoC must be maintained for the period specified by the 
appropriate regulation or the CoC conditions. If a retention period is 
not specified, the records must be maintained until the NRC terminates 
the CoC.
    (c) Any record maintained under this part may be either the original 
or a reproduced copy by any state-of-the-art method provided that any 
reproduced copy is duly authenticated by authorized personnel and is 
capable of producing a clear and legible copy after storage for the 
period specified by NRC regulations.
    (d) Each certificate holder shall submit a written report to the NRC 
within 30 days of discovery of a design or fabrication deficiency, for 
any spent fuel storage cask which has been delivered to a licensee, when 
the design or fabrication deficiency affects the ability of structures, 
systems, and components important to safety to perform their intended 
safety function. The written report shall be sent to the NRC in 
accordance with the requirements of Sec. 72.4. The report shall include 
the following:
    (1) A brief abstract describing the deficiency, including all 
component or system failures that contributed to the deficiency and 
corrective action taken or planned to prevent recurrence;
    (2) A clear, specific, narrative description of what occurred so 
that knowledgeable readers familiar with the design of the spent fuel 
storage cask, but not familiar with the details of a particular cask, 
can understand the deficiency. The narrative description shall include 
the following specific information as appropriate for the particular 
event:
    (i) Dates and approximate times of discovery;
    (ii) The cause of each component or system failure, if known;
    (iii) The failure mode, mechanism, and effect of each failed 
component, if known;
    (iv) A list of systems or secondary functions that were also 
affected for failures of components with multiple functions;
    (v) The method of discovery of each component or system failure;
    (vi) The manufacturer and model number (or other identification) of 
each component that failed during the event;
    (vii) The model and serial numbers of the affected spent fuel 
storage casks;
    (viii) The licensees that have affected spent fuel storage casks;
    (3) An assessment of the safety consequences and implications of the 
deficiency. This assessment shall include the availability of other 
systems or components that could have performed the same function as the 
components and systems that were affected;
    (4) A description of any corrective actions planned as a result of 
the deficiency, including those to reduce the probability of similar 
occurrences in the future;
    (5) Reference to any previous similar deficiencies at the same 
facility that are known to the certificate holder; and
    (6) The name and telephone number of a person within the certificate 
holder's organization who is knowledgeable about the deficiency and can 
provide additional information.

[64 FR 56127, Oct. 15, 1999]

[[Page 460]]



Sec. 72.244  Application for amendment of a certificate of compliance.

    Whenever a certificate holder desires to amend the CoC (including a 
change to the terms, conditions or specifications of the CoC), an 
application for an amendment shall be filed with the Commission fully 
describing the changes desired and the reasons for such changes, and 
following as far as applicable the form prescribed for original 
applications.

[64 FR 53617, Oct. 4, 1999]



Sec. 72.246  Issuance of amendment to a certificate of compliance.

    In determining whether an amendment to a CoC will be issued to the 
applicant, the Commission will be guided by the considerations that 
govern the issuance of an initial CoC.

[64 FR 53617, Oct. 4, 1999]



Sec. 72.248  Safety analysis report updating.

    (a) Each certificate holder for a spent fuel storage cask design 
shall update periodically, as provided in paragraph (b) of this section, 
the final safety analysis report (FSAR) to assure that the information 
included in the report contains the latest information developed.
    (1) Each certificate holder shall submit an original FSAR to the 
Commission, in accordance with Sec. 72.4, within 90 days after the 
spent fuel storage cask design has been approved pursuant to Sec. 
72.238.
    (2) The original FSAR shall be based on the safety analysis report 
submitted with the application and reflect any changes and applicant 
commitments developed during the cask design review process. The 
original FSAR shall be updated to reflect any changes to requirements 
contained in the issued Certificate of Compliance (CoC).
    (b) Each update shall contain all the changes necessary to reflect 
information and analyses submitted to the Commission by the certificate 
holder or prepared by the certificate holder pursuant to Commission 
requirement since the submission of the original FSAR or, as 
appropriate, the last update to the FSAR under this section. The update 
shall include the effects \1\ of:
---------------------------------------------------------------------------

    \1\ Effects of changes includes appropriate revisions of 
descriptions in the FSAR such that the FSAR (as updated) is complete and 
accurate.
---------------------------------------------------------------------------

    (1) All changes made in the spent fuel storage cask design or 
procedures as described in the FSAR;
    (2) All safety analyses and evaluations performed by the certificate 
holder either in support of approved CoC amendments, or in support of 
conclusions that changes did not require a CoC amendment in accordance 
with Sec. 72.48; and
    (3) All analyses of new safety issues performed by or on behalf of 
the certificate holder at Commission request. The information shall be 
appropriately located within the updated FSAR.
    (c)(1) The update of the FSAR must be filed in accordance with Sec. 
72.4. If the update is filed on paper, then it should be filed on a 
page-replacement basis; if filed electronically, it should be filed on a 
full replacement basis. See Guidance for Electronic Submissions to the 
Commission at http://www.nrc.gov/site-help/e-submittals.html.
    (2) A paper update filed on a page-replacement basis must include a 
list that identifies the current pages of the FSAR following page 
replacement. If the update is filed electronically on a full replacement 
basis, it must include a list of changed pages.
    (3) Each replacement page shall include both a change indicator for 
the area changed, e.g., a bold line vertically drawn in the margin 
adjacent to the portion actually changed, and a page change 
identification (date of change or change number or both);
    (4) The update shall include:
    (i) A certification by a duly authorized officer of the certificate 
holder that either the information accurately presents changes made 
since the previous submittal, or that no such changes were made; and
    (ii) An identification of changes made by the certificate holder 
under the provisions of Sec. 72.48, but not previously submitted to the 
Commission;
    (5) The update shall reflect all changes implemented up to a maximum 
of 6 months prior to the date of filing;

[[Page 461]]

    (6) Updates shall be filed every 24 months from the date of issuance 
of the CoC; and
    (7) The certificate holder shall provide a copy of the updated FSAR 
to each general and specific licensee using its cask design.
    (d) The updated FSAR shall be retained by the certificate holder 
until the Commission terminates the certificate.
    (e) A certificate holder who permanently ceases operation, shall 
provide the updated FSAR to the new certificate holder or to the 
Commission, as appropriate, in accordance with Sec. 72.234(d)(3).

[64 FR 53617, Oct. 4, 1999, as amended at 68 FR 58819, Oct. 10, 2003; 74 
FR 62684, Dec. 1, 2009]



PART 73_PHYSICAL PROTECTION OF PLANTS AND MATERIALS--Table of Contents



                           General Provisions

Sec.
73.1 Purpose and scope.
73.2 Definitions.
73.3 Interpretations.
73.4 Communications.
73.5 Specific exemptions.
73.6 Exemptions for certain quantities and kinds of special nuclear 
          material.
73.8 Information collection requirements: OMB approval.
73.20 General performance objective and requirements.
73.21 Protection of Safeguards Information: Performance requirements.
73.22 Protection of Safeguards Information: Specific requirements.
73.23 Protection of Safeguards Information--Modified Handling: Specific 
          requirements.
73.24 Prohibitions.

       Physical Protection of Special Nuclear Material in Transit

73.25 Performance capabilities for physical protection of strategic 
          special nuclear material in transit.
73.26 Transportation physical protection systems, subsystems, 
          components, and procedures.
73.27 Notification requirements.
73.28 Security background checks for secure transfer of nuclear 
          materials.
73.35 Requirements for physical protection of irradiated reactor fuel 
          (100 grams or less) in transit.
73.37 Requirements for physical protection of irradiated reactor fuel in 
          transit.
73.38 Personnel access authorization requirements for irradiated reactor 
          fuel in transit.

             Physical Protection Requirements at Fixed Sites

73.40 Physical protection: General requirements at fixed sites.
73.45 Performance capabilities for fixed site physical protection 
          systems.
73.46 Fixed site physical protection systems, subsystems, components, 
          and procedures.
73.50 Requirements for physical protection of licensed activities.
73.51 Requirements for the physical protection of stored spent nuclear 
          fuel and high-level radioactive waste.
73.54 Protection of digital computer and communication systems and 
          networks.
73.55 Requirements for physical protection of licensed activities in 
          nuclear power reactors against radiological sabotage.
73.56 Personnel access authorization requirements for nuclear power 
          plants.
73.57 Requirements for criminal history records checks of individuals 
          granted unescorted access to a nuclear power facility, a non-
          power reactor, or access to Safeguards Information.
73.58 Safety/security interface requirements for nuclear power reactors.
73.59 Relief from fingerprinting, identification and criminal history 
          records checks and other elements of background checks for 
          designated categories of individuals.
73.60 Additional requirements for physical protection at nonpower 
          reactors.
73.61 Relief from fingerprinting and criminal history records check for 
          designated categories of individuals permitted unescorted 
          access to certain radioactive materials or other property.

  Physical Protection of Special Nuclear Material of Moderate and Low 
                         Strategic Significance

73.67 Licensee fixed site and in-transit requirements for the physical 
          protection of special nuclear material of moderate and low 
          strategic significance.

                           Records and Reports

73.70 Records.
73.71 Reporting of safeguards events.
73.72 Requirement for advance notice of shipment of formula quantities 
          of strategic special nuclear material, special nuclear 
          material of moderate strategic significance, or irradiated 
          reactor fuel.
73.73 Requirement for advance notice and protection of export shipments 
          of special nuclear material of low strategic significance.

[[Page 462]]

73.74 Requirement for advance notice and protection of import shipments 
          of nuclear material from countries that are not party to the 
          Convention on the Physical Protection of Nuclear Material.
73.75 Posting.
73.77 Cyber security event notifications.

                               Enforcement

73.80 Violations.
73.81 Criminal penalties.

Appendix A to Part 73--U.S. Nuclear Regulatory Commission Offices and 
          Classified Mailing Addresses
Appendix B to Part 73--General Criteria for Security Personnel
Appendix C to Part 73--Licensee Safeguards Contingency Plans
Appendix D to Part 73--Physical Protection of Irradiated Reactor Fuel in 
          Transit, Training Program Subject Schedule
Appendix E to Part 73--Levels of Physical Protection To Be Applied in 
          International Transport of Nuclear Material
Appendix F to Part 73--Nations That Are Parties to the Convention on the 
          Physical Protection of Nuclear Material
Appendix G to Part 73--Reportable Safeguards Events
Appendix H to Part 73--Weapons Qualification Criteria

    Authority: Atomic Energy Act of 1954, secs. 53, 147, 149, 161, 170D, 
170E, 170H, 170I, 223, 229, 234, 1701 (42 U.S.C. 2073, 2167, 2169, 2201, 
2210d, 2210e, 2210h, 2210i, 2273, 2278a, 2282, 2297f); Energy 
Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); 
Nuclear Waste Policy Act of 1982, secs. 135, 141 (42 U.S.C. 10155, 
10161); 44 U.S.C. 3504 note.
    Section 73.1 also issued under Nuclear Waste Policy Act secs. 135, 
141 (42 U.S.C. 10155, 10161).
    Section 73.37(b)(2) also issued under Sec. 301, Public Law 96-295, 
94 Stat. 789 (42 U.S.C. 5841 note).
    Section 73.37(f) also issued under Sec. 301, Pub. L. 96-295, 94 
Stat. 789 (42 U.S.C. 5841 note).

    Source: 38 FR 35430, Dec. 28, 1973, unless otherwise noted.

                           General Provisions



Sec. 73.1  Purpose and scope.

    (a) Purpose. This part prescribes requirements for the establishment 
and maintenance of a physical protection system which will have 
capabilities for the protection of special nuclear material at fixed 
sites and in transit and of plants in which special nuclear material is 
used. The following design basis threats, where referenced in ensuing 
sections of this part, shall be used to design safeguards systems to 
protect against acts of radiological sabotage and to prevent the theft 
or diversion of special nuclear material. Licensees subject to the 
provisions of Sec. 73.20 (except for fuel cycle licensees authorized 
under Part 70 of this chapter to receive, acquire, possess, transfer, 
use, or deliver for transportation formula quantities of strategic 
special nuclear material), Sec. Sec. 73.50, and 73.60 are exempt from 
Sec. Sec. 73.1(a)(1)(i)(E), 73.1(a)(1)(iii), 73.1(a)(1)(iv), 
73.1(a)(2)(iii), and 73.1(a)(2)(iv). Licensees subject to the provisions 
of Sec. 72.212 are exempt from Sec. 73.1(a)(1)(iv).
    (1) Radiological sabotage. (i) A determined violent external 
assault, attack by stealth, or deceptive actions, including diversionary 
actions, by an adversary force capable of operating in each of the 
following modes: A single group attacking through one entry point, 
multiple groups attacking through multiple entry points, a combination 
of one or more groups and one or more individuals attacking through 
multiple entry points, or individuals attacking through separate entry 
points, with the following attributes, assistance and equipment:
    (A) Well-trained (including military training and skills) and 
dedicated individuals, willing to kill or be killed, with sufficient 
knowledge to identify specific equipment or locations necessary for a 
successful attack;
    (B) Active (e.g., facilitate entrance and exit, disable alarms and 
communications, participate in violent attack) or passive (e.g., provide 
information), or both, knowledgeable inside assistance;
    (C) Suitable weapons, including hand-held automatic weapons, 
equipped with silencers and having effective long range accuracy;
    (D) Hand-carried equipment, including incapacitating agents and 
explosives for use as tools of entry or for otherwise destroying 
reactor, facility, transporter, or container integrity or features of 
the safeguards system; and

[[Page 463]]

    (E) Land and water vehicles, which could be used for transporting 
personnel and their hand-carried equipment to the proximity of vital 
areas; and
    (ii) An internal threat; and
    (iii) A land vehicle bomb assault, which may be coordinated with an 
external assault; and
    (iv) A waterborne vehicle bomb assault, which may be coordinated 
with an external assault; and
    (v) A cyber attack.
    (2) Theft or diversion of formula quantities of strategic special 
nuclear material. (i) A determined violent external assault, attack by 
stealth, or deceptive actions, including diversionary actions, by an 
adversary force capable of operating in each of the following modes: a 
single group attacking through one entry point, multiple groups 
attacking through multiple entry points, a combination of one or more 
groups and one or individuals attacking through multiple entry points, 
or individuals attacking through separate entry points, with the 
following attributes, assistance and equipment:
    (A) Well-trained (including military training and skills) and 
dedicated individuals, willing to kill or be killed, with sufficient 
knowledge to identify specific equipment or locations necessary for a 
successful attack;
    (B) Active (e.g., facilitate entrance and exit, disable alarms and 
communications, participate in violent attack) or passive (e.g., provide 
information), or both, knowledgeable inside assistance;
    (C) Suitable weapons, including hand-held automatic weapons, 
equipped with silencers and having effective long-range accuracy;
    (D) Hand-carried equipment, including incapacitating agents and 
explosives for use as tools of entry or for otherwise destroying 
reactor, facility, transporter, or container integrity or features of 
the safe-guards system;
    (E) Land and water vehicles, which could be used for transporting 
personnel and their hand-carried equipment; and
    (ii) An internal threat; and
    (iii) A land vehicle bomb assault, which may be coordinated with an 
external assault; and
    (iv) A waterborne vehicle bomb assault, which may be coordinated 
with an external assault; and
    (v) A cyber attack.
    (b) Scope. (1) This part prescribes requirements for:
    (i) The physical protection of production and utilization facilities 
licensed under parts 50 or 52 of this chapter,
    (ii) The physical protection of plants in which activities licensed 
pursuant to part 70 of this chapter are conducted, and
    (iii) The physical protection of special nuclear material by any 
person who, pursuant to the regulations in part 61 or 70 of this 
chapter, possesses or uses at any site or contiguous sites subject to 
the control by the licensee, formula quantities of strategic special 
nuclear material or special nuclear material of moderate strategic 
significance or special nuclear material of low strategic significance.
    (2) This part prescribes requirements for the physical protection of 
special nuclear material in transportation by any person who is licensed 
pursuant to the regulations in parts 70 and 110 of this chapter who 
imports, exports, transports, delivers to a carrier for transport in a 
single shipment, or takes delivery of a single shipment free on board 
(F.O.B.) where it is delivered to a carrier, formula quantities of 
strategic special nuclear material, special nuclear material of moderate 
strategic significance or special nuclear material of low strategic 
significance.
    (3) This part also applies to shipments by air of special nuclear 
material in quantities exceeding: (i) 20 grams or 20 curies, whichever 
is less, of plutonium or uranium-233, or (ii) 350 grams of uranium-235 
(contained in uranium enriched to 20 percent or more in the U-235 
isotope).
    (4) Special nuclear material subject to this part may also be 
protected pursuant to security procedures prescribed by the Commission 
or another Government agency for the protection of classified materials. 
The provisions and requirements of this part are in addition to, and not 
in substitution for, any such security procedures. Compliance with the 
requirements of this part does

[[Page 464]]

not relieve any licensee from any requirement or obligation to protect 
special nuclear material pursuant to security procedures prescribed by 
the Commission or other Government agency for the protection of 
classified materials.
    (5) This part also applies to the shipment of irradiated reactor 
fuel in quantities that in a single shipment both exceed 100 grams in 
net weight of irradiated fuel, exclusive of cladding or other structural 
or packaging material, and have a total radiation dose in excess of 100 
rems per hour at a distance of 3 feet from any accessible surface 
without intervening shielding.
    (6) This part prescribes requirements for the physical protection of 
spent nuclear fuel and high-level radioactive waste stored in either an 
independent spent fuel storage installation (ISFSI) or a monitored 
retrievable storage (MRS) installation licensed under part 72 of this 
chapter, or stored at the geologic repository operations area licensed 
under part 60 or part 63 of this chapter.
    (7) This part prescribes requirements for the protection of 
Safeguards Information (including Safeguards Information with the 
designation or marking: Safeguards Information--Modified Handling) in 
the hands of any person, whether or not a licensee of the Commission, 
who produces, receives, or acquires that information.
    (8) This part prescribes requirements for advance notice of export 
and import shipments of special nuclear material, including irradiated 
reactor fuel.
    (9) As provided in part 76 of this chapter, the regulations of this 
part establish procedures and criteria for physical security for the 
issuance of a certificate of compliance or the approval of a compliance 
plan.

[44 FR 68186, Nov. 28, 1979]

    Editorial Note: For Federal Register citations affecting Sec. 73.1, 
see the List of CFR Sections Affected, which appears in the Finding Aids 
section of the printed volume and at www.fdsys.gov.



Sec. 73.2  Definitions.

    As used in this part:
    (a) Terms defined in parts 50, 52, and 70 of this chapter have the 
same meaning when used in this part.
    Appropriate Nuclear Regulatory Commission Regional Office listed in 
appendix A means:
    (1) For domestic shipments--the Regional Office within whose region 
the licensee who is responsible for the physical protection arrangements 
of the shipment is located.
    (2) For export shipments--the Regional Office within whose region 
the licensee who is responsible for the physical protection arrangements 
of the shipment is located, and the Regional Office for the region in 
which the last point of exit of the shipment from the U.S. is located.
    (3) For import shipments--the Regional Office within whose region 
the licensee who is responsible for the physical protection arrangements 
of the shipment is located, and the Regional Office for the region in 
which the first point of entry of the shipment into the U.S. is located.
    Armed escort means an armed person, not necessarily uniformed, whose 
primary duty is to accompany shipments of special nuclear material for 
the protection of such shipments against theft or radiological sabotage.
    Armed response personnel means persons, not necessarily uniformed, 
whose primary duty in the event of attempted theft of special nuclear 
material or radiological sabotage shall be to respond, armed and 
equipped, to prevent or delay such actions.
    Authorized individual means any individual, including an employee, a 
student, a consultant, or an agent of a licensee who has been designated 
in writing by a licensee to have responsibility for surveillance of or 
control over special nuclear material or to have unescorted access to 
areas where special nuclear material is used or stored.
    Background check includes, at a minimum, a Federal Bureau of 
Investigation (FBI) criminal history records check (including 
verification of identity based on fingerprinting), employment history, 
education, and personal references. Individuals engaged in activities 
subject to regulation by the Commission, applicants for licenses to 
engage in Commission-regulated activities, and individuals who have 
notified the Commission in writing of an

[[Page 465]]

intent to file an application for licensing, certification, permitting, 
or approval of a product or activity subject to regulation by the 
Commission are required under Sec. 73.57 to conduct fingerprinting and 
criminal history records checks before granting access to Safeguards 
Information. A background check must be sufficient to support the 
trustworthiness and reliability determination so that the person 
performing the check and the Commission have assurance that granting 
individuals access to Safeguards Information does not constitute an 
unreasonable risk to the public health and safety or the common defense 
and security.
    Bullet/resisting means protection against complete penetration, 
passage of fragments of projectiles, and spalling (fragmentation) of the 
protective material that could cause injury to a person standing 
directly behind the bullet-resisting barrier.
    Contiguous sites means licensee controlled locations, deemed by the 
Commission to be in close enough proximity to each other, that the 
special nuclear material must be considered in the aggregate for the 
purpose of physical protection.
    Continuous visual surveillance means unobstructed view at all times 
of a shipment of special nuclear material, and of all access to a 
temporary storage area or cargo compartment containing the shipment.
    Controlled access area means any temporarily or permanently 
established area which is clearly demarcated, access to which is 
controlled and which affords isolation of the material or persons within 
it.
    Deceit means methods used to attempt to gain unauthorized access, 
introduce unauthorized materials, or remove strategic special nuclear 
materials, where the attempt involves falsification to present the 
appearance of authorized access.
    DOE and Department of Energy means the Department of Energy 
established by the Department of Energy Organization Act (Pub. L. 95-91, 
91 Stat. 565, 42 U.S.C. 7101 et seq.), to the extent that the 
Department, or its duly authorized representatives, exercises functions 
formerly vested in the U.S. Atomic Energy Commission, its Chairman, 
members, officers and components and transfered to the U.S. Energy 
Research and Development Administration and to the Administrator thereof 
pursuant to sections 104(b), (c) and (d) of the Energy Reorganization 
Act of 1974 (Pub. L. 93-438, 88 Stat. 1233 at 1237, 42 U.S.C. 5814) and 
retransferred to the Secretary of Energy pursuant to section 301(a) of 
the Department of Energy Organization Act (Pub. L. 95-91, 91 Stat. 565 
at 577-578, 42 U.S.C. 7151).
    Force means violent methods used by an adversary to attempt to steal 
strategic special nuclear material or to sabotage a nuclear facility or 
violent methods used by response personnel to protect against such 
adversary actions.
    Formula quantity means strategic special nuclear material in any 
combination in a quantity of 5,000 grams or more computed by the 
formula, grams = (grams contained U-235) + 2.5 (grams U-233 + grams 
plutonium). This class of material is sometimes referred to as a 
Category I quantity of material.
    Guard means a uniformed individual armed with a firearm whose 
primary duty is the protection of special nuclear material against 
theft, the protection of a plant against radiological sabotage, or both.
    Incendiary device means any self-contained device intended to create 
an intense fire that can damage normally flame-resistant or retardant 
materials.
    Indian Tribe means an Indian or Alaska Native Tribe, band, nation, 
pueblo, village, or community that the Secretary of the Interior 
acknowledges to exist as an Indian Tribe pursuant to the Federally 
Recognized Indian Tribe List Act of 1994, 25 U.S.C. 5130.
    Individual authorized access to Safeguards Information is an 
individual authorized to have access to and handle such information 
pursuant to the requirements of Sec. Sec. 73.21 and 73.22 of this part.
    Individual authorized access to Safeguards Information--Modified 
Handling is an individual authorized to have access to and handle 
Safeguards Information designated as Safeguards Information--Modified 
Handling information pursuant to the requirements of Sec. Sec. 73.21 
and 73.23 of this part.

[[Page 466]]

    Intrusion alarm means a tamper indicating electrical, 
electromechanical, electrooptical, electronic or similar device which 
will detect intrusion by an individual into a building, protected area, 
vital area, or material access area, and alert guards or watchmen by 
means of actuated visible and audible signals.
    Isolation zone means any area adjacent to a physical barrier, clear 
of all objects which could conceal or shield an individual.
    Lock in the case of vaults or vault type rooms means a three-
position, manipulation resistant, dial type, built-in combination lock 
or combination padlock and in the case of fences, walls, and buildings 
means an integral door lock or padlock which provides protection 
equivalent to a six-tumbler cylinder lock. Lock in the case of a vault 
or vault type room also means any manipulation resistant, 
electromechanical device which provides the same function as a built-in 
combination lock or combination padlock, which can be operated remotely 
or by the reading or insertion of information, which can be uniquely 
characterized, and which allows operation of the device. Locked means 
protected by an operable lock.
    Material access area means any location which contains special 
nuclear material, within a vault or a building, the roof, walls, and 
floor of which each constitute a physical barrier.
    Movement control center means an operations center which is remote 
from transport activity and which maintains periodic position 
information on the movement of strategic special nuclear material, 
receives reports of attempted attacks or thefts, provides a means for 
reporting these and other problems to appropriate agencies and can 
request and coordinate appropriate aid.
    Need to know means a determination by a person having responsibility 
for protecting Safeguards Information (including Safeguards Information 
designated as Safeguards Information--Modified Handling) that a proposed 
recipient's access to Safeguards Information is necessary in the 
performance of official, contractual, licensee, applicant, or 
certificate holder employment. In an adjudication, ``need to know'' 
means a determination by the originator of the information that the 
information is necessary to enable the proposed recipient to proffer 
and/or adjudicate a specific contention in that proceeding, and the 
proposed recipient of the specific Safeguards Information possesses 
demonstrable knowledge, skill, training, or education to effectively 
utilize the specific Safeguards Information in the proceeding. Where the 
information is in the possession of the originator and the NRC staff 
(dual possession), whether in its original form or incorporated into 
another document or other matter by the recipient, the NRC staff makes 
the determination. In the event of a dispute regarding the ``need to 
know'' determination, the presiding officer of the proceeding shall make 
the ``need to know'' determination.
    Person means (1) any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
government agency other than the Commission or the Department of Energy 
(DOE), (except that the DOE shall be considered a person to the extent 
that its facilities are subject to the licensing and related regulatory 
authority of the Commission pursuant to section 202 of the Energy 
Reorganization Act of 1974 and sections 104, 105, and 202 of the Uranium 
Mill Tailings Radiation Control Act of 1978), any state or political 
subdivision of a state, or any political subdivision of any government 
or nation, or other entity; and (2) any legal successor, representative, 
agent, or agency of the foregoing.
    Physical barrier means:
    (1) Fences constructed of No. 11 American wire gauge, or heavier 
wire fabric, topped by three strands or more of barbed wire or similar 
material on brackets angled inward or outward between 30[deg] and 
45[deg] from the vertical, with an overall height of not less than eight 
feet, including the barbed topping;
    (2) Building walls, ceilings and floors constructed of stone, brick, 
cinder block, concrete, steel or comparable materials (openings in which 
are secured by grates, doors, or covers of construction and fastening of 
sufficient strength such that the integrity of the

[[Page 467]]

wall is not lessened by any opening), or walls of similar construction, 
not part of a building, provided with a barbed topping described in 
paragraph (1) of this definition of a height of not less than 8 feet; or
    (3) Any other physical obstruction constructed in a manner and of 
materials suitable for the purpose for which the obstruction is 
intended.
    Protected area means an area encompassed by physical barriers and to 
which access is controlled.
    Radiological sabotage means any deliberate act directed against a 
plant or transport in which an activity licensed pursuant to the 
regulations in this chapter is conducted, or against a component of such 
a plant or transport which could directly or indirectly endanger the 
public health and safety by exposure to radiation.
    Safeguards Information means information not classified as National 
Security Information or Restricted Data which specifically identifies a 
licensee's or applicant's detailed control and accounting procedures for 
the physical protection of special nuclear material in quantities 
determined by the Commission through order or regulation to be 
significant to the public health and safety or the common defense and 
security; detailed security measures (including security plans, 
procedures, and equipment) for the physical protection of source, 
byproduct, or special nuclear material in quantities determined by the 
Commission through order or regulation to be significant to the public 
health and safety or the common defense and security; security measures 
for the physical protection of and location of certain plant equipment 
vital to the safety of production or utilization facilities; and any 
other information within the scope of Section 147 of the Atomic Energy 
Act of 1954, as amended, the unauthorized disclosure of which, as 
determined by the Commission through order or regulation, could 
reasonably be expected to have a significant adverse effect on the 
health and safety of the public or the common defense and security by 
significantly increasing the likelihood of sabotage or theft or 
diversion of source, byproduct, or special nuclear material.
    Safeguards Information--Modified Handling is the designation or 
marking applied to Safeguards Information which the Commission has 
determined requires handling requirements modified from the specific 
Safeguards Information handling requirements that are applicable to 
Safeguards Information needing a higher level of protection.
    Security management means persons responsible for security at the 
policy and general management level.
    Security Storage Container includes any of the following 
repositories: (1) For storage in a building located within a protected 
or controlled access area, a steel filing cabinet equipped with a steel 
locking bar and a three position, changeable combination, GSA approved 
padlock; (2) A security filing cabinet that bears a Test Certification 
Label on the side of the locking drawer, or interior plate, and is 
marked, General Services Administration Approved Security Container on 
the exterior of the top drawer or door; (3) A bank safe-deposit box; and 
(4) Other repositories which in the judgement of the NRC, would provide 
comparable physical protection.
    Security supervision means persons, not necessarily uniformed or 
armed, whose primary duties are supervision and direction of security at 
the day-to-day operating level.
    Special nuclear material of low strategic significance means:
    (1) Less than an amount of special nuclear material of moderate 
strategic significance as defined in paragraph (1) of the definition of 
strategic nuclear material of moderate strategic significance in this 
section, but more than 15 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in U-235 isotope) or 15 grams of uranium-
233 or 15 grams of plutonium or the combination of 15 grams when 
computed by the equation, grams = (grams contained U-235) + (grams 
plutonium) + (grams U-233); or
    (2) Less than 10,000 grams but more than 1,000 grams of uranium-235 
(contained in uranium enriched to 10 percent or more but less than 20 
percent in the U-235 isotope); or
    (3) 10,000 grams or more of uranium-235 (contained in uranium 
enriched

[[Page 468]]

above natural but less than 10 percent in the U-235 isotope).

This class of material is sometimes referred to as a Category III 
quantity of material.
    Special nuclear material of moderate strategic significance means:
    (1) Less than a formula quantity of strategic special nuclear 
material but more than 1,000 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in the U-235 isotope) or more than 500 
grams of uranium-233 or plutonium, or in a combined quantity of more 
than 1,000 grams when computed by the equation, grams = (grams contained 
U-235) + 2 (grams U-233 + grams plutonium); or
    (2) 10,000 grams or more of uranium-235 (contained in uranium 
enriched to 10 percent or more but less than 20 percent in the U-235 
isotope).

This class of material is sometimes referred to as a Category II 
quantity of material.
    Stealth means methods used to attempt to gain unauthorized access, 
introduce unauthorized materials, or remove strategic special nuclear 
material, where the fact of such attempt is concealed or an attempt is 
made to conceal it.
    Strategic special nuclear material means uranium-235 (contained in 
uranium enriched to 20 percent or more in the U-235 isotope), uranium-
233, or plutonium.
    Tactical Response Team means the primary response force for each 
shift which can be identified by a distinctive item of uniform, armed 
with specified weapons, and whose other duties permit immediate 
response.
    Transport means any land, sea, or air conveyance or modules for 
these conveyances such as rail cars or standardized cargo containers.
    Tribal official means the highest ranking individual that represents 
Tribal leadership, such as the Chief, President, or Tribal Council 
leadership.
    Trustworthiness and reliability are characteristics of an individual 
considered dependable in judgment, character, and performance, such that 
disclosure of Safeguards Information (including Safeguards Information 
designated as Safeguards Information--Modified Handling) to that 
individual does not constitute an unreasonable risk to the public health 
and safety or common defense and security. A determination of 
trustworthiness and reliability for this purpose is based upon a 
background check.
    Undergoing processing means performing active operations on material 
such as chemical transformation, physical transformation, or transit 
between such operations, to be differentiated from storage or packaging 
for shipment.
    Vault means a windowless enclosure with walls, floor, roof and 
door(s) designed and constructed to delay penetration from forced entry.
    Vault-type room means a room with one or more doors, all capable of 
being locked, protected by an intrusion alarm which creates an alarm 
upon the entry of a person anywhere into the room and upon exit from the 
room or upon movement of an individual within the room.
    Vital area means any area which contains vital equipment.
    Vital equipment means any equipment, system, device, or material, 
the failure, destruction, or release of which could directly or 
indirectly endanger the public health and safety by exposure to 
radiation. Equipment or systems which would be required to function to 
protect public health and safety following such failure, destruction, or 
release are also considered to be vital.
    Watchman means an individual, not necessarily uniformed or armed 
with a firearm, who provides protection for a plant and the special 
nuclear material therein in the course of performing other duties.

[38 FR 35430, Dec. 28, 1973]

    Editorial Note: For Federal Register citations affecting Sec. 73.2, 
see the List of CFR Sections Affected, which appears in the Finding Aids 
section of the printed volume and at www.fdsys.gov.



Sec. 73.3  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretations of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized as binding upon 
the Commission.

[[Page 469]]



Sec. 73.4  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent as follows:
    (a) By mail addressed to: ATTN: Document Control Desk, Director, 
Office of Nuclear Reactor Regulation, Director, Office of New Reactors, 
Director, Office of Nuclear Material Safety and Safeguards, or Director, 
Division of Security Policy, Office of Nuclear Security and Incident 
Response, as appropriate, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001;
    (b) By hand delivery to the NRC's offices at 11555 Rockville Pike, 
Rockville, Maryland;
    (c) Where practicable, by electronic submission, for example, 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.
    (d) Classified communications shall be transmitted to the NRC 
Headquarters' classified mailing address as specified in appendix A to 
part 73 of this chapter or delivered by hand in accordance with this 
paragraph.

[68 FR 58819, Oct. 10, 2003, as amended at 73 FR 5725, Jan. 31, 2008; 74 
FR 62684, Dec. 1, 2009; 80 FR 74981, Dec. 1, 2015]



Sec. 73.5  Specific exemptions.

    The Commission may, upon application of any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
will not endanger life or property or the common defense and security, 
and are otherwise in the public interest.



Sec. 73.6  Exemptions for certain quantities and kinds of special
nuclear material.

    A licensee is exempt from the requirements of 10 CFR part 26 and 
Sec. Sec. 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 
with respect to the following special nuclear material:
    (a) Uranium-235 contained in uranium enriched to less than 20 
percent in the U-235 isotope.
    (b) Special nuclear material which is not readily separable from 
other radioactive material and which has a total external radiation 
level in excess of 1 Gray (100 Rad) per hour at a distance of 1 meter 
(3.3 feet) from any accessible surface without intervening shielding.
    (c) Special nuclear material in a quantity not exceeding 350 grams 
of uranium-235, uranium-233, plutonium, or a combination thereof, 
possessed in any analytical, research, quality control, metallurgical or 
electronic laboratory.
    (d) Special nuclear material that is being transported by the United 
States Department of Energy transport system.
    (e) Special nuclear material at non-power reactors.

Licensees subject to Sec. 73.60 are not exempted from Sec. Sec. 73.70 
and 73.72, and licensees subject to Sec. 73.67(e) are not exempted from 
Sec. 73.72 of this part.

[40 FR 52841, Nov. 13, 1975, as amended at 44 FR 68187, Nov. 28, 1979; 
58 FR 31471, June 3, 1993; 78 FR 34250, June 7, 2013]



Sec. 73.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information is it does not display a currently valid OMB control number. 
OMB has approved the information collection requirements contained in 
this part under control number 3150-0002.

[[Page 470]]

    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 73.5, 73.20, 73.21, 73.23, 73.24, 73.25, 
73.26, 73.27, 73.37, 73.38, 73.40, 73.45, 73.46, 73.50, 73.51, 73.54, 
73.55, 73.56, 73.57, 73.58, 73.60, 73.67, 73.70, 73.71, 73.72, 73.73, 
73.74, and appendices B, C, and G to this part.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. The information collection requirement 
and the control numbers under which it is approved are as follows:
    (1) In Sec. Sec. 73.71 and 73.77, NRC Form 366 is approved under 
control number 3150-0104.
    (2) [Reserved]

[62 FR 52189, Oct. 6, 1997, as amended at 67 FR 67101, Nov. 4, 2002; 73 
FR 63574, Oct. 24, 2008; 74 FR 13970, Mar. 27, 2009; 77 FR 39909, July 
6, 2012; 78 FR 29550, May 20, 2013; 80 FR 67275, Nov. 2, 2015; 80 FR 
74981, Dec. 1, 2015]



Sec. 73.20  General performance objective and requirements.

    (a) In addition to any other requirements of this part, each 
licensee who is authorized to operate a fuel reprocessing plant pursuant 
to part 50 of this chapter; possesses or uses formula quantities of 
strategic special nuclear material at any site or contiguous sites 
subject to control by the licensee; is authorized to transport or 
deliver to a carrier for transportation pursuant to part 70 of this 
chapter formula quantities of strategic special nuclear material; takes 
delivery of formula quantities of strategic special nuclear material 
free on board (f.o.b.) the point at which it is delivered to a carrier 
for transportation; or imports or exports formula quantities of 
strategic special nuclear material, shall establish and maintain or make 
arrangements for a physical protection system which will have as its 
objective to provide high assurance that activities involving special 
nuclear material are not inimical to the common defense and security, 
and do not constitute an unreasonable risk to the public health and 
safety. The physical protection system shall be designed to protect 
against the design basis threats of theft or diversion of strategic 
special nuclear material and radiological sabotage as stated in Sec. 
73.1(a).
    (b) To achieve the general performance objective of paragraph (a) of 
this section a licensee shall establish and maintain, or arrange for, a 
physical protection system that:
    (1) Provides the performance capabilities described in Sec. 73.25 
for in-transit protection or in Sec. 73.45 for fixed site protection 
unless otherwise authorized by the Commission;
    (2) Is designed with sufficient redundancy and diversity to ensure 
maintenance of the capabilities described in Sec. Sec. 73.25 and 73.45;
    (3) Includes a safeguards contingency capability that can meet the 
criteria in appendix C to this part ``Licensee Safeguards Contingency 
Plans;'' and
    (4) Includes a testing and maintenance program to assure control 
over all activities and devices affecting the effectiveness, 
reliability, and availability of the physical protection system, 
including a demonstration that any defects of such activities and 
devices will be promptly detected and corrected for the total period of 
time they are required as a part of the physical protection system.
    (c) Each licensee subject to the requirements of paragraphs (a) and 
(b) of this section shall establish, maintain, and follow NRC-approved 
safeguards physical protection and safeguards contingency plans that 
describe how the licensee will comply with the requirements of 
paragraphs (a) and (b) of this section.

[44 FR 68188, Nov. 28, 1979, as amended at 57 FR 33430, July 29, 1992]



Sec. 73.21  Protection of Safeguards Information: 
Performance requirements.

    (a) General performance requirement. (1) Each licensee, certificate 
holder, applicant, or other person who produces, receives, or acquires 
Safeguards Information (including Safeguards Information with the 
designation or marking: Safeguards Information--Modified Handling) shall 
ensure that it is protected against unauthorized disclosure. To meet 
this general performance requirement, such licensees, certificate 
holders, applicants, or other persons subject to this section shall:

[[Page 471]]

    (i) Establish, implement, and maintain an information protection 
system that includes the applicable measures for Safeguards Information 
specified in Sec. 73.22 related to: Power reactors; a formula quantity 
of strategic special nuclear material; transportation of or delivery to 
a carrier for transportation of a formula quantity of strategic special 
nuclear material or more than 100 grams of irradiated reactor fuel; 
uranium hexafluoride production or conversion facilities; fuel 
fabrication facilities; uranium enrichment facilities; independent spent 
fuel storage installations; and geologic repository operations areas.
    (ii) Establish, implement, and maintain an information protection 
system that includes the applicable measures for Safeguards Information 
specified in Sec. 73.23 related to: Research and test reactors that 
possess special nuclear material of moderate strategic significance or 
special nuclear material of low strategic significance.
    (iii) Protect the information in accordance with the requirements of 
Sec. 73.22 if the Safeguards Information is not described in paragraphs 
(a)(1)(i) and (a)(1)(ii) of this section.
    (2) Information protection procedures employed by Federal, State, 
Tribal, and local law enforcement agencies are presumed to meet the 
general performance requirement in paragraph (a)(1) of this section.
    (b) Commission authority. (1) Pursuant to Section 147 of the Atomic 
Energy Act of 1954, as amended, the Commission may impose, by order or 
regulation, Safeguards Information protection requirements different 
from or in addition to those specified in this Part on any person who 
produces, receives, or acquires Safeguards Information.
    (2) The Commission may require, by regulation or order, that 
information within the scope of Section 147 of the Atomic Energy Act of 
1954, as amended, related to facilities or materials not specifically 
described in Sec. Sec. 73.21, 73.22 or 73.23 be protected under this 
part.

[73 FR 63574, Oct. 24, 2008, as amended at 77 FR 34205, June 11, 2012; 
79 FR 58671, Sept. 30, 2014]



Sec. 73.22  Protection of Safeguards Information:
Specific requirements.

    This section contains specific requirements for the protection of 
Safeguards Information in the hands of any person subject to the 
requirements of Sec. 73.21(a)(1)(i) and related to power reactors; a 
formula quantity of strategic special nuclear material; transportation 
of or delivery to a carrier for transportation of a formula quantity of 
strategic special nuclear material or more than 100 grams of irradiated 
reactor fuel; uranium hexafluoride production or conversion facilities, 
fuel fabrication facilities, and uranium enrichment facilities; 
independent spent fuel storage installations; geologic repository 
operations areas and Safeguards Information in the hands of any person 
subject to the requirements of Sec. 73.21(a)(1)(iii).
    (a) Information to be protected. The types of information and 
documents that must be protected as Safeguards Information include non-
public security-related requirements such as:
    (1) Physical protection. Information not classified as Restricted 
Data or National Security Information related to physical protection, 
including:
    (i) The composite physical security plan for the facility or site;
    (ii) Site-specific drawings, diagrams, sketches, or maps that 
substantially represent the final design features of the physical 
security system not easily discernible by members of the public;
    (iii) Alarm system layouts showing the location of intrusion 
detection devices, alarm assessment equipment, alarm system wiring, 
emergency power sources for security equipment, and duress alarms not 
easily discernible by members of the public;
    (iv) Physical security orders and procedures issued by the licensee 
for members of the security organization detailing duress codes, patrol 
routes and schedules, or responses to security contingency events;
    (v) Site-specific design features of plant security communications 
systems;
    (vi) Lock combinations, mechanical key design, or passwords integral 
to the physical security system;

[[Page 472]]

    (vii) Documents and other matter that contain lists or locations of 
certain safety-related equipment explicitly identified in the documents 
or other matter as vital for purposes of physical protection, as 
contained in security plans, contingency measures, or plant specific 
safeguards analyses;
    (viii) The composite safeguards contingency plan/measures for the 
facility or site;
    (ix) The composite facility guard qualification and training plan/
measures disclosing features of the physical security system or response 
procedures;
    (x) Information relating to on-site or off-site response forces, 
including size, armament of response forces, and arrival times of such 
forces committed to respond to security contingency events;
    (xi) The adversary characteristics document and related information, 
including implementing guidance associated with the Design Basis Threat 
in Sec. 73.1(a)(1) or (a)(2); and
    (xii) Engineering and safety analyses, security-related procedures 
or scenarios, and other information revealing site-specific details of 
the facility or materials if the unauthorized disclosure of such 
analyses, procedures, scenarios, or other information could reasonably 
be expected to have a significant adverse effect on the health and 
safety of the public or the common defense and security by significantly 
increasing the likelihood of theft, diversion, or sabotage of source, 
byproduct, or special nuclear material.
    (2) Physical protection in transit. Information not classified as 
Restricted Data or National Security Information related to the 
transportation of, or delivery to a carrier for transportation of a 
formula quantity of strategic special nuclear material or more than 100 
grams of irradiated reactor fuel, including:
    (i) The composite physical security plan for transportation;
    (ii) Schedules and itineraries for specific shipments of source 
material, byproduct material, high-level nuclear waste, or irradiated 
reactor fuel. Schedules for shipments of source material, byproduct 
material, high-level nuclear waste, or irradiated reactor fuel are no 
longer controlled as Safeguards Information 10 days after the last 
shipment of a current series;
    (iii) Vehicle immobilization features, intrusion alarm devices, and 
communications systems;
    (iv) Arrangements with and capabilities of local police response 
forces, and locations of safe havens identified along the transportation 
route;
    (v) Limitations of communications during transport;
    (vi) Procedures for response to security contingency events;
    (vii) Information concerning the tactics and capabilities required 
to defend against attempted sabotage, or theft and diversion of formula 
quantities of special nuclear material, irradiated reactor fuel, or 
related information; and
    (viii) Engineering or safety analyses, security-related procedures 
or scenarios and other information related to the protection of the 
transported material if the unauthorized disclosure of such analyses, 
procedures, scenarios, or other information could reasonably be expected 
to have a significant adverse effect on the health and safety of the 
public or the common defense and security by significantly increasing 
the likelihood of theft, diversion, or sabotage of source, byproduct, or 
special nuclear material.
    (3) Inspections, audits and evaluations. Information not classified 
as National Security Information or Restricted Data pertaining to 
safeguards and security inspections and reports, including:
    (i) Portions of inspection reports, evaluations, audits, or 
investigations that contain details of a licensee's or applicant's 
physical security system or that disclose uncorrected defects, 
weaknesses, or vulnerabilities in the system. Disclosure of corrected 
defects, weaknesses, or vulnerabilities is subject to an assessment 
taking into account such factors as trending analyses and the impacts of 
disclosure on licensees having similar physical security systems; and
    (ii) Reports of investigations containing general information may be 
released after corrective actions have been completed, unless withheld 
pursuant to other authorities, e.g., the Freedom of Information Act (5 
U.S.C. 552).

[[Page 473]]

    (4) Correspondence. Portions of correspondence insofar as they 
contain Safeguards Information as set forth in paragraphs (a)(1) through 
(a)(3) of this section.
    (5) Other information within the scope of Section 147 of the Atomic 
Energy Act of 1954, as amended, that the Commission determines by order 
or regulation could reasonably be expected to have a significant adverse 
effect on the health and safety of the public or the common defense and 
security by significantly increasing the likelihood of theft, diversion, 
or sabotage of source, byproduct, or special nuclear material or a 
facility.
    (b) Conditions for access. (1) Except as the Commission may 
otherwise authorize, no person may have access to Safeguards Information 
unless the person has an established ``need to know'' for the 
information and has undergone a Federal Bureau of Investigation (FBI) 
criminal history records check using the procedures set forth in Sec. 
73.57.
    (2) In addition, a person to be granted access to Safeguards 
Information must be trustworthy and reliable, based on a background 
check or other means approved by the Commission.
    (3) The categories of individuals specified in 10 CFR 73.59 are 
exempt from the criminal history records check and background check 
requirements in paragraphs (b)(1) and (b)(2) of this section by virtue 
of their occupational status.
    (4) For persons participating in an NRC adjudicatory proceeding, the 
``need to know'' determination shall be made by the originator of the 
Safeguards Information upon receipt of a request for access to the 
Safeguards Information. Where the information is in the possession of 
the originator and the NRC staff, whether in its original form or 
incorporated into another document or other matter by the recipient, the 
NRC staff shall make the determination. In the event of a dispute 
regarding the ``need to know'' determination, the presiding officer of 
the proceeding shall determine whether the ``need to know'' findings in 
Sec. 73.2 can be made.
    (5) Except as the Commission may otherwise authorize, no person may 
disclose Safeguards Information to any other person except as set forth 
in this section.
    (c) Protection while in use or storage. (1) While in use, matter 
containing Safeguards Information must be under the control of an 
individual authorized access to Safeguards Information. This requirement 
is satisfied if the Safeguards Information is attended by such an 
individual even though the information is in fact not constantly being 
used. Safeguards Information within alarm stations, or rooms 
continuously occupied by authorized individuals need not be stored in a 
locked security storage container.
    (2) While unattended, Safeguards Information must be stored in a 
locked security storage container. The container shall not identify the 
contents of the matter contained and must preclude access by individuals 
not authorized access in accordance with the provisions of this section. 
Knowledge of lock combinations protecting Safeguards Information must be 
limited to a minimum number of personnel for operating purposes who have 
a ``need to know'' and are otherwise authorized access to Safeguards 
Information in accordance with the provisions of this Part. Access to 
lock combinations must be strictly controlled so as to prevent 
disclosure to an individual not authorized access to Safeguards 
Information.
    (d) Preparation and marking of documents or other matter. (1) Each 
document or other matter that contains Safeguards Information as 
described in Sec. 73.21(a)(1)(i) and this section must be marked to 
indicate the presence of such information in a conspicuous manner on the 
top and bottom of each page. The first page of the document or other 
matter must also contain:
    (i) The name, title, and organization of the individual authorized 
to make a Safeguards Information determination, and who has determined 
that the document or other matter contains Safeguards Information;
    (ii) The date the determination was made; and
    (iii) An indication that unauthorized disclosure will be subject to 
civil and criminal sanctions.
    (2) In addition to the markings at the top and bottom of each page, 
any

[[Page 474]]

transmittal letters or memoranda to or from the NRC which do not in 
themselves contain Safeguards Information shall be marked to indicate 
that attachments or enclosures contain Safeguards Information but that 
the transmittal document or other matter does not (i.e., ``When 
separated from Safeguards Information enclosure(s), this document is 
decontrolled provided the transmittal document does not otherwise 
warrant protection from unauthorized disclosure'').
    (3) Any transmittal document or other matter forwarding Safeguards 
Information must alert the recipient that protected information is 
enclosed. Certification that a document or other matter contains 
Safeguards Information must include the name and title of the certifying 
official and date designated. Portion marking is required only for 
correspondence to and from the NRC (i.e., cover letters, but not 
attachments) that contains Safeguards Information. The portion marking 
must be sufficient to allow the recipient to identify and distinguish 
those sections of the transmittal document or other information 
containing the Safeguards Information from non-Safeguards Information.
    (4) Marking of documents or other matter containing or transmitting 
Safeguards Information shall, at a minimum include the words 
``Safeguards Information'' to ensure identification of protected 
information for the protection of facilities and material covered by 
Sec. 73.22.
    (e) Reproduction of matter containing Safeguards Information. 
Safeguards Information may be reproduced to the minimum extent necessary 
consistent with need without permission of the originator. Equipment 
used to reproduce Safeguards Information must be evaluated to ensure 
that unauthorized individuals cannot access Safeguards Information 
(e.g., unauthorized individuals cannot access Safeguards Information by 
gaining access to retained memory or network connectivity).
    (f) External transmission of documents and material. (1) Documents 
or other matter containing Safeguards Information, when transmitted 
outside an authorized place of use or storage, must be packaged in two 
sealed envelopes or wrappers to preclude disclosure of the presence of 
protected information. The inner envelope or wrapper must contain the 
name and address of the intended recipient and be marked on both sides, 
top and bottom, with the words ``Safeguards Information.'' The outer 
envelope or wrapper must be opaque, addressed to the intended recipient, 
must contain the address of the sender, and may not bear any markings or 
indication that the document or other matter contains Safeguards 
Information.
    (2) Safeguards Information may be transported by any commercial 
delivery company that provides service with computer tracking features, 
U.S. first class, registered, express, or certified mail, or by any 
individual authorized access pursuant to these requirements.
    (3) Except under emergency or extraordinary conditions, Safeguards 
Information shall be transmitted outside an authorized place of use or 
storage only by NRC approved secure electronic devices, such as 
facsimiles or telephone devices, provided that transmitters and 
receivers implement processes that will provide high assurance that 
Safeguards Information is protected before and after the transmission or 
electronic mail through the internet, provided that the information is 
encrypted by a method (Federal Information Processing Standard [FIPS] 
140-2 or later) approved by the appropriate NRC Office; the information 
is produced by a self contained secure automatic data process system; 
and transmitters and receivers implement the information handling 
processes that will provide high assurance that Safeguards Information 
is protected before and after transmission. Physical security events 
required to be reported pursuant to Sec. 73.71 are considered to be 
extraordinary conditions. Cyber security event notifications required to 
be reported pursuant to Sec. 73.77 are considered to be extraordinary 
conditions.
    (g) Processing of Safeguards Information on electronic systems. (1) 
Safeguards Information may be stored, processed or produced on a stand-
alone computer (or computer system) for processing of Safeguards 
Information. ``Stand-alone'' means a computer or computer system

[[Page 475]]

to which access is limited to individuals authorized access to 
Safeguards Information. A stand-alone computer or computer system shall 
not be physically or in any other way connected to a network accessible 
by users who are not authorized access to Safeguards Information.
    (2) Each computer not located within an approved and lockable 
security storage container that is used to process Safeguards 
Information must have a removable storage medium with a bootable 
operating system. The bootable operating system must be used to load and 
initialize the computer. The removable storage medium must also contain 
the software application programs. Data may be saved on either the 
removable storage medium that is used to boot the operating system, or 
on a different removable storage medium. The removable storage medium 
must be secured in a locked security storage container when not in use.
    (3) A mobile device (such as a laptop computer) may also be used for 
the processing of Safeguards Information provided the device is secured 
in a locked security storage container when not in use. Other systems 
may be used if approved for security by the appropriate NRC office.
    (4) Any electronic system that has been used for storage, processing 
or production of Safeguards Information must be free of recoverable 
Safeguards Information prior to being returned to nonexclusive use.
    (h) Removal from Safeguards Information category. Documents or other 
matter originally containing Safeguards Information must be removed from 
the Safeguards Information category at such time as the information no 
longer meets the criteria contained in this part. Care must be exercised 
to ensure that any document or other matter decontrolled not disclose 
Safeguards Information in some other form or be combined with other 
unprotected information to disclose Safeguards Information. The 
authority to determine that a document or other matter may be 
decontrolled will only be exercised by the NRC, with NRC approval, or in 
consultation with the individual or organization that made the original 
determination.
    (i) Destruction of matter containing Safeguards Information. 
Documents or other matter containing Safeguards Information shall be 
destroyed when no longer needed. The information can be destroyed by 
burning, shredding or any other method that precludes reconstruction by 
means available to the public at large. Piece sizes no wider than one 
quarter inch composed of several pages or documents and thoroughly mixed 
are considered completely destroyed.

[73 FR 63574, Oct. 24, 2008, as amended at 80 FR 67275, Nov. 2, 2015]



Sec. 73.23  Protection of Safeguards Information--Modified Handling:
Specific requirements.

    This section contains specific requirements for the protection of 
Safeguards Information in the hands of any person subject to the 
requirements of Sec. 73.21(a)(1)(ii) and research and test reactors 
that possess special nuclear material of moderate strategic significance 
or special nuclear material of low strategic significance. The 
requirements of this section distinguish Safeguards Information 
requiring modified handling requirements (SGI-M) from the specific 
Safeguards Information handling requirements applicable to facilities 
and materials needing a higher level of protection, as set forth in 
Sec. 73.22.
    (a) Information to be protected. The types of information and 
documents that must be protected as Safeguards Information--Modified 
Handling include non-public security-related requirements such as 
protective measures, interim compensatory measures, additional security 
measures, and the following, as applicable:
    (1) Physical protection. Information not classified as Restricted 
Data or National Security Information related to physical protection, 
including:
    (i) The composite physical security plan for the facility or site;
    (ii) Site specific drawings, diagrams, sketches, or maps that 
substantially represent the final design features of the physical 
security system not easily discernible by members of the public;

[[Page 476]]

    (iii) Alarm system layouts showing the location of intrusion 
detection devices, alarm assessment equipment, alarm system wiring, 
emergency power sources for security equipment, and duress alarms not 
easily discernible by members of the public;
    (iv) Physical security orders and procedures issued by the licensee 
for members of the security organization detailing duress codes, patrol 
routes and schedules, or responses to security contingency events;
    (v) Site specific design features of plant security communications 
systems;
    (vi) Lock combinations, mechanical key design, or passwords integral 
to the physical security system;
    (vii) The composite facility guard qualification and training plan/
measures disclosing features of the physical security system or response 
procedures;
    (viii) Descriptions of security activities which disclose features 
of the physical security system or response measures;
    (ix) Information relating to onsite or offsite response forces, 
including size, armament of the response forces, and arrival times of 
such forces committed to respond to security contingency events; and
    (x) Engineering and safety analyses, security-related procedures or 
scenarios, and other information revealing site-specific details of the 
facility or materials if the unauthorized disclosure of such analyses, 
procedures, scenarios, or other information could reasonably be expected 
to have a significant adverse effect on the health and safety of the 
public or the common defense and security by significantly increasing 
the likelihood of theft, diversion, or sabotage of source, byproduct, or 
special nuclear material.
    (2) Physical protection in transit. Information not classified as 
Restricted Data or National Security Information related to the physical 
protection of shipments of special nuclear material in less than a 
formula quantity (except for those materials covered under Sec. 73.22), 
including:
    (i) Information regarding transportation security measures, 
including physical security plans and procedures, immobilization 
devices, and escort requirements, more detailed than NRC regulations;
    (ii) Scheduling and itinerary information for shipments (scheduling 
and itinerary information for shipments that are inherently self-
disclosing, such as a shipment that created extensive news coverage or 
an announcement by a public official confirming receipt, may be 
decontrolled after shipment departure). Scheduling and itinerary 
information for shipments that are not inherently self-disclosing may be 
decontrolled 2 days after the shipment is completed. Scheduling and 
itinerary information used for the purpose of preplanning, coordination, 
and advance notification may be shared with others on a ``need to know'' 
basis and need not be designated as Safeguards Information-Modified 
Handling);
    (iii) Arrangements with and capabilities of local police response 
forces, and locations of safe havens identified along the transportation 
route;
    (iv) Details of alarm and communication systems, communication 
procedures, and duress codes;
    (v) Procedures for response to security contingency events; and
    (vi) Engineering or safety analyses, security-related procedures or 
scenarios and other information related to the protection of the 
transported material if the unauthorized disclosure of such analyses, 
procedures, scenarios, or other information could reasonably be expected 
to have a significant adverse effect on the health and safety of the 
public or the common defense and security by significantly increasing 
the likelihood of theft, diversion, or sabotage of source, byproduct, or 
special nuclear material.
    (3) Inspections, audits and evaluations. Information not classified 
as National Security Information or Restricted Data pertaining to 
safeguards and security inspections and reports, including:
    (i) Portions of inspection reports, evaluations, audits, or 
investigations that contain details of a licensee's or applicant's 
physical security system or that disclose uncorrected defects, 
weaknesses, or vulnerabilities in the system. Disclosure of corrected 
defects,

[[Page 477]]

weaknesses, or vulnerabilities is subject to an assessment taking into 
account such factors as trending analyses and the impacts of disclosure 
on licensees having similar physical security systems; and
    (ii) Reports of investigations containing general information may be 
released after the corrective actions have been completed, unless 
withheld pursuant to other authorities, e.g., the Freedom of Information 
Act (5 U.S.C. 552).
    (4) Correspondence. Portions of correspondence insofar as they 
contain Safeguards Information designated as Safeguards Information-
Modified Handling, as set forth in paragraphs (a)(1) through (a)(3) of 
this section.
    (5) Other information within the scope of Section 147 of the Atomic 
Energy Act of 1954, as amended, that the Commission determines by order 
or regulation could reasonably be expected to have a significant adverse 
effect on the health and safety of the public or the common defense and 
security by significantly increasing the likelihood of theft, diversion, 
or sabotage of source, byproduct, or special nuclear material or a 
facility.
    (b) Conditions for access. (1) Except as the Commission may 
otherwise authorize, no person may have access to Safeguards Information 
designated as Safeguards Information-Modified Handling unless the person 
has an established ``need to know'' for the information and has 
undergone a Federal Bureau of Investigation criminal history records 
check using the procedures set forth in Sec. 73.57.
    (2) In addition, a person to be granted access to Safeguards 
Information must be trustworthy and reliable, based on a background 
check or other means approved by the Commission.
    (3) The categories of individuals specified in 10 CFR 73.59 are 
exempt from the criminal history records check and background check 
requirements in paragraphs (b)(1) and (b)(2) of this section by virtue 
of their occupational status:
    (4) For persons participating in an NRC adjudicatory proceeding, the 
``need to know'' determination shall be made by the originator of the 
Safeguards Information designated as Safeguards Information-Modified 
Handling upon receipt of a request for access to the Safeguards 
Information designated as Safeguards Information-Modified Handling. 
Where the information is in the possession of the originator and the NRC 
staff, whether in its original form or incorporated into another 
document or other matter by the recipient, the NRC staff shall make the 
determination. In the event of a dispute regarding the ``need to know'' 
determination, the presiding officer of the proceeding shall determine 
whether the ``need to know'' findings in Sec. 73.2 can be made.
    (5) Except as the Commission may otherwise authorize, no person may 
disclose Safeguards Information designated as Safeguards Information-
Modified Handling to any other person except as set forth in this 
section.
    (c) Protection while in use or storage. (1) While in use, matter 
containing Safeguards Information designated as Safeguards Information-
Modified Handling must be under the control of an individual authorized 
access to such information. This requirement is satisfied if the 
Safeguards Information designated as Safeguards Information-Modified 
Handling is attended by such an individual even though the information 
is in fact not constantly being used. Safeguards Information designated 
as Safeguards Information-Modified Handling within alarm stations, or 
rooms continuously occupied by authorized individuals, need not be 
locked in a file drawer or cabinet.
    (2) While unattended, Safeguards Information designated as 
Safeguards Information-Modified Handling must be stored in a locked file 
drawer or cabinet. The container shall not identify the contents of the 
matter contained and must preclude access by individuals not authorized 
access in accordance with the provisions of this section. Knowledge of 
lock combinations or access to keys protecting Safeguards Information 
designated as Safeguards Information-Modified Handling must be limited 
to a minimum number of personnel for operating purposes who have a 
``need to know'' and are otherwise authorized access to Safeguards 
Information in accordance with the provisions of this Part. Access to 
lock combinations must be strictly controlled so as to prevent 
disclosure to an

[[Page 478]]

individual not authorized access to Safeguards Information designated as 
Safeguards Information-Modified Handling.
    (d) Preparation and marking of documents or other matter. (1) Each 
document or other matter that contains Safeguards Information designated 
as Safeguards Information-Modified Handling as described in Sec. 
73.23(a) and in this section must be marked to indicate the presence of 
Safeguards Information with modified handling requirements in a 
conspicuous manner on the top and bottom of each page. The first page of 
the document or other matter must also contain:
    (i) The name, title, and organization of the individual authorized 
to make a ``Safeguards Information designated as Safeguards Information-
Modified Handling'' determination, and who has determined that the 
document or other matter contains Safeguards Information designated as 
Safeguards Information-Modified Handling;
    (ii) The date the determination was made; and
    (iii) An indication that unauthorized disclosure will be subject to 
civil and criminal sanctions.
    (2) In addition to the markings at the top and bottom of each page, 
any transmittal letters or memoranda to or from the NRC which do not in 
themselves contain Safeguards Information designated as Safeguards 
Information-Modified Handling shall be marked to indicate that 
attachments or enclosures contain Safeguards Information designated as 
Safeguards Information-Modified Handling but that the transmittal 
document does not (i.e., ``When separated from Safeguards Information 
designated as Safeguards Information-Modified Handling enclosure(s), 
this document is decontrolled provided the transmittal document does not 
otherwise warrant protection from unauthorized disclosure'').
    (3) Any transmittal document or other matter forwarding Safeguards 
Information designated as Safeguards Information-Modified Handling must 
alert the recipient that protected information is enclosed. 
Certification that a document or other matter contains Safeguards 
Information designated as Safeguards Information-Modified Handling must 
include the name and title of the certifying official and date 
designated. Portion marking is required only for correspondence to and 
from the NRC (i.e., cover letters, but not attachments) that contains 
Safeguards Information designated as Safeguards Information-Modified 
Handling. The portion marking must be sufficient to allow the recipient 
to identify and distinguish those sections of the transmittal document 
or other information containing the Safeguards Information from non-
Safeguards Information.
    (4) Marking of documents or other matter containing or transmitting 
Safeguards Information with modified handling requirements shall, at a 
minimum include the words ``Safeguards Information-Modified Handling'' 
to ensure identification of protected information for the protection of 
facilities and material covered by Sec. 73.23.
    (e) Reproduction of matter containing Safeguards Information 
designated as Safeguards Information-Modified Handling. Safeguards 
Information designated as Safeguards Information-Modified Handling may 
be reproduced to the minimum extent necessary, consistent with need, 
without permission of the originator. Equipment used to reproduce 
Safeguards Information designated as Safeguards Information-Modified 
Handling must be evaluated to ensure that unauthorized individuals 
cannot access the information (e.g. , unauthorized individuals cannot 
access Safeguards Information by gaining access to retained memory or 
network connectivity).
    (f) External transmission of documents and material. (1) Documents 
or other matter containing Safeguards Information designated as 
Safeguards Information-Modified Handling, when transmitted outside an 
authorized place of use or storage, must be packaged in two sealed 
envelopes or wrappers to preclude disclosure of the presence of 
protected information. The inner envelope or wrapper must contain the 
name and address of the intended recipient and be marked on both sides, 
top and bottom, with the words ``Safeguards Information-Modified 
Handling.'' The outer envelope or wrapper must be opaque, addressed to 
the intended recipient, must contain the address of

[[Page 479]]

the sender, and may not bear any markings or indication that the 
document contains Safeguards Information designated as Safeguards 
Information-Modified Handling.
    (2) Safeguards Information designated Safeguards Information-
Modified Handling may be transported by any commercial delivery company 
that provides service with computer tracking features, U.S. first class, 
registered, express, or certified mail, or by any individual authorized 
access pursuant to these requirements.
    (3) Except under emergency or extraordinary conditions, Safeguards 
Information designated as Safeguards Information-Modified Handling must 
be transmitted electronically only by protected telecommunications 
circuits (including facsimile) or encryption by a method (Federal 
Information Processing Standard [FIPS] 140-2 or later) approved by the 
appropriate NRC office. For the purpose of this section, emergency or 
extraordinary conditions are defined as any circumstances that require 
immediate communications in order to report, summon assistance for, or 
respond to a security contingency event or an event that has potential 
security significance. Physical security events required to be reported 
pursuant to Sec. 73.71 are considered to be extraordinary conditions.
    (g) Processing of Safeguards Information-Modified Handling on 
electronic systems. (1) Safeguards Information designated for modified 
handling may be stored, processed or produced on a computer or computer 
system, provided that the system is assigned to the licensee's or 
contractor's facility. Safeguards Information designated as Safeguards 
Information-Modified Handling files must be protected, either by a 
password or encryption, to prevent unauthorized individuals from gaining 
access. Word processors such as typewriters are not subject to these 
requirements as long as they do not transmit information off-site.

    Note: If Safeguards Information designated as Safeguards 
Information-Modified Handling is produced on a typewriter, the ribbon 
must be properly marked and be removed and stored in the same manner as 
other Safeguards Information designated as Safeguards Information-
Modified Handling.

    (2) Safeguards Information designated as Safeguards Information-
Modified Handling files may be transmitted over a network if the file is 
encrypted. In such cases, the licensee will select a commercially 
available encryption system that the National Institute of Standards and 
Technology (NIST) has validated as conforming to Federal Information 
Processing Standards (FIPS) 140-2 or later. Safeguards Information 
designated as Safeguards Information-Modified Handling files shall be 
properly labeled to indicate the presence of Safeguards Information with 
modified handling requirements and saved to removable matter and stored 
in a locked file drawer or cabinet.
    (3) A mobile device (such as a laptop computer) may also be used for 
the processing of Safeguards Information designated as Safeguards 
Information-Modified Handling provided the device is secured in an 
appropriate locked storage container when not in use. Other systems may 
be used if approved for security by the appropriate NRC office.
    (4) Any electronic system that has been used for storage, processing 
or production of Safeguards Information must be free of recoverable 
Safeguards Information designated as Safeguards Information-Modified 
Handling prior to being returned to nonexclusive use.
    (h) Removal from Safeguards Information-Modified Handling category. 
Documents or other matter originally containing Safeguards Information 
designated as Safeguards Information-Modified Handling must be removed 
from the Safeguards Information category at such time as the information 
no longer meets the criteria contained in this Part. Care must be 
exercised to ensure that any document or other matter decontrolled shall 
not disclose Safeguards Information in some other form or be combined 
with other unprotected information to disclose Safeguards Information. 
The authority to determine that a document or other matter may be 
decontrolled will only be exercised by the NRC, with NRC approval, or in 
consultation with the individual or organization that made the original 
determination.

[[Page 480]]

    (i) Destruction of matter containing Safeguards Information 
designated as Safeguards Information-Modified Handling. Documents or 
other matter containing Safeguards Information shall be destroyed when 
no longer needed. The information can be destroyed by burning, 
shredding, or any other method that precludes reconstruction by means 
available to the public at large. Piece sizes no wider than one quarter 
inch composed of several pages or documents and thoroughly mixed are 
considered completely destroyed.

[73 FR 63577, Oct. 24, 2008]



Sec. 73.24  Prohibitions.

    (a) Except as specifically approved by the Nuclear Regulatory 
Commission, no shipment of special nuclear material shall be made in 
passenger aircraft in excess of (1) 20 grams or 20 curies, whichever is 
less, of plutonium or uranium-233, or (2) 350 grams of uranium-235 
(contained in uranium enriched to 20 percent or more in the U-235 
isotope).
    (b) Unless otherwise approved by the Nuclear Regulatory Commission, 
no licensee may make shipments of special nuclear material in which 
individual shipments are less than a formula quantity, but the total 
quantity in shipments in transit at the same time could equal or exceed 
a formula quantity, unless either of the following conditions are met:
    (1) The licensee shall confirm and log the arrival at the final 
destination of each individual shipment and retain the log for three 
years from the date of the last entry in the log. The licensee shall 
also schedule shipments to ensure that the total quantity for two or 
more shipments in transit at the same time does not equal or exceed the 
formula quantity, or
    (2) Physical protection in accordance with the requirements of 
Sec. Sec. 73.20, 73.25, and 73.26 is provided by the licensee for such 
shipments as appropriate so that the total quantity of special nuclear 
material in the remaining shipments not so protected, and in transit at 
the same time, does not equal or exceed a formula quantity.

[44 FR 68188, Nov. 28, 1979, as amended at 53 FR 19257, May 27, 1988]

       Physical Protection of Special Nuclear Material in Transit



Sec. 73.25  Performance capabilities for physical protection of
strategic special nuclear material in transit.

    (a) To meet the general performance objective and requirements of 
Sec. 73.20 an in-transit physical protection system shall include the 
performance capabilities described in paragraphs (b) through (d) of this 
section unless otherwise authorized by the Commission.
    (b) Restrict access to and activity in the vicinity of transports 
and strategic special nuclear material. To achieve this capability the 
physical protection system shall:
    (1) Minimize the vulnerability of the strategic special nuclear 
material by using the following subfunctions and procedures:
    (i) Preplanning itineraries for the movement of strategic special 
nuclear material;
    (ii) Periodically updating knowledge of route conditions for the 
movement of strategic special nuclear material;
    (iii) Maintaining knowledge of the status and position of the 
strategic special nuclear material en route; and
    (iv) Determining and communicating alternative itineraries en route 
as conditions warrant.
    (2) Detect and delay any unauthorized attempt to gain access or 
introduce unauthorized materials by stealth or force into the vicinity 
of transports and strategic special nuclear material using the following 
subsystems and subfunctions:
    (i) Controlled access areas to isolate strategic special nuclear 
material and transports to assure that unauthorized persons shall not 
have direct access to, and unauthorized materials shall not be 
introduced into the vicinity of, the transports and strategic special 
nuclear material, and
    (ii) Access detection subsystems and procedures to detect, assess 
and communicate any unauthorized penetration (or such attempts) of a 
controlled access area by persons, vehicles or materials so that the 
response will satisfy the general performance objective and requirements 
of Sec. 73.20(a).
    (3) Detect attempts to gain unauthorized access or introduce 
unauthorized

[[Page 481]]

materials into the vicinity of transports by deceit using the following 
subsystems and subfunctions:
    (i) Access authorization controls and procedures to provide current 
authorization schedules and access criteria for persons, materials and 
vehicles; and
    (ii) Access controls and procedures to verify the identity of 
persons, materials and vehicles, to assess such identity against current 
authorization schedules and access criteria before permitting access, 
and to initiate response measures to deny unauthorized entries.
    (c) Prevent or delay unauthorized entry or introduction of 
unauthorized materials into, and unauthorized removal of, strategic 
special nuclear material from transports. To achieve this capability the 
physical protection system shall:
    (1) Detect attempts to gain unauthorized entry or introduce 
unauthorized materials into transports by deceit using the following 
subsystems and subfunctions:
    (i) Access authorization controls and procedures to provide current 
authorization schedules and entry criteria for access into transports 
for both persons and materials; and
    (ii) Entry controls and procedures to verify the identity of persons 
and materials and to permit transport entry only to those persons and 
materials specified by the current authorization schedules and entry 
criteria.
    (2) Detect attempts to gain unauthorized entry or introduce 
unauthorized material into transports by stealth or force using the 
following subsystems and subfunctions:
    (i) Transport features to delay access to strategic special nuclear 
material sufficient to permit the detection and response systems to 
function so as to satisfy the general performance objective and 
requirements of Sec. 73.20(a);
    (ii) Inspection and detection subsystems and procedures to detect 
unauthorized tampering with transports and cargo containers; and
    (iii) Surveillance subsystems and procedures to detect, assess and 
communicate any unauthorized presence of persons or materials and any 
unauthorized attempt to penetrate the transport so that the response 
will satisfy the general performance objective and requirements of Sec. 
73.20(a).
    (3) Prevent unauthorized removal of strategic special nuclear 
material from transports by deceit using the following subsystems and 
subfunctions:
    (i) Authorization controls and procedures to provide current 
schedules for authorized removal of strategic special nuclear material 
which specify the persons authorized to remove and receive the material, 
the authorized times for such removal and receipt and authorized places 
for such removal and receipt.
    (ii) Removal controls and procedures to establish activities for 
transferring cargo in emergency situations; and
    (iii) Removal controls and procedures to permit removal of strategic 
special nuclear material only after verification of the identity of 
persons removing or receiving the strategic special nuclear material, 
and after verification of the identity and integrity of the strategic 
special nuclear material being removed from transports.
    (4) Detect attempts to remove strategic special nuclear material 
from transports by stealth or force using the following subsystems and 
subfunctions:
    (i) Transport features to delay unauthorized strategic special 
nuclear material removal attempts sufficient to assist detection and 
permit a response to satisfy the general performance objective and 
requirements of Sec. 73.20(a); and
    (ii) Detection subsystems and procedures to detect, assess and 
communicate any attempts at unauthorized removal of strategic special 
nuclear material so that response to the attempt can be such as to 
satisfy the general performance objective and requirements of Sec. 
73.20(a).
    (d) Respond to safeguards contingencies and emergencies to assure 
that the two capabilities in paragraphs (b) and (c) of this section are 
achieved, and to engage and impede adversary forces until local law 
enforcement forces arrive. To achieve this capability, the physical 
protection system shall:
    (1) Respond rapidly and effectively to safeguards contingencies and 
emergencies using the following subsystems and subfunctions:

[[Page 482]]

    (i) A security organization composed of trained and qualifed 
personnel, including armed escorts, one of whom is designated as escort 
commander, with procedures for command and control, to execute response 
functions.
    (ii) Assessment procedures to assess the nature and extent of 
security related incidents.
    (iii) A predetermined plan to respond to safeguards contingency 
events.
    (iv) Equipment and procedures to enable responses to security 
related incidents sufficiently rapid and effective to achieve the 
predetermined objective of each action.
    (v) Equipment, vehicle design features, and procedures to protect 
security organization personnel, including those at the movement control 
center, in their performance of assessment and response related 
functions.
    (2) Transmit detection, assessment and other response related 
information using the following subsystems and subfunctions:
    (i) Communications equipment and procedures to rapidly and 
accurately transmit security information among armed escorts.
    (ii) Equipment and procedures for two-way communications between the 
escort commander and the movement control center to rapidly and 
accurately transmit assessment information and requests for assistance 
by local law enforcement forces, and to coordinate such assistance.
    (iii) Communications equipment and procedures for the armed escorts 
and the movement control center personnel to notify local law 
enforcement forces of the need for assistance.
    (3) Establish liaisons with local law enforcement authorities to 
arrange for assistance en route.
    (4) Assure that a single adversary action cannot destroy the 
capability of armed escorts to notify the local law enforcement forces 
of the need for assistance.

[44 FR 68188, Nov. 28, 1979]



Sec. 73.26  Transportation physical protection systems, subsystems,
components, and procedures.

    (a) A transportation physical protection system established pursuant 
to the general performance objectives and requirements of Sec. 73.20 
and performance capability requirements of Sec. 73.25 shall include, 
but are not necessarily limited to, the measures specified in paragraphs 
(b) through (l) of this section. The Commission may require, depending 
on the individual transportation conditions or circumstances, alternate 
or additional measures deemed necessary to meet the general performance 
objectives and requirements of Sec. 73.20. The Commission also may 
authorize protection measures other than those required by this section 
if, in its opinion, the overall level of performance meets the general 
performance objectives and requirements of Sec. 73.20 and the 
performance capability requirements of Sec. 73.25.
    (b) Planning and scheduling. (1) Shipments shall be scheduled to 
avoid regular patterns and preplanned to avoid areas of natural disaster 
or civil disorders, such as strikes or riots. Such shipments shall be 
planned in order to avoid storage times in excess of 24 hours and to 
assure that deliveries occur at a time when the receiver at the final 
delivery point is present to accept the shipment.
    (2) Arrangements shall be made with law enforcement authorities 
along the route of shipments for their response to an emergency or a 
call for assistance.
    (3) Security arrangements for each shipment shall be approved by the 
Nuclear Regulatory Commission prior to the time for the seven-day notice 
required by Sec. 73.72. Information to be supplied to the Commission in 
addition to the general security plan information is as follows:
    (i) Shipper, consignee, carriers, transfer points, modes of 
shipment,
    (ii) Point where escorts will relinquish responsibility or will 
accept responsibility for the shipment,
    (iii) Arrangements made for transfer of shipment security, and
    (iv) Security arrangements at point where escorts accept 
responsibility for an import shipment.
    (4) Hand-to-hand receipts shall be completed at origin and 
destination and at all points enroute where there is a transfer of 
custody.
    (c) Export/import shipments. (1) A licensee who imports a formula 
quantity

[[Page 483]]

of strategic special nuclear material shall make arrangements to assure 
that the material will be protected in transit as follows:
    (i) An individual designated by the licensee or his agent, or as 
specified by a contract of carriage, shall confirm the container count 
and examine locks and/or seals for evidence of tampering, at the first 
place in the United States at which the shipment is discharged from the 
arriving carrier.
    (ii) The shipment must be protected at all times within the 
geographical limits of the United States as provided in this section and 
Sec. Sec. 73.25 and 73.27. The licensee shall retain each record 
required by these sections for three years after the close of period for 
which the licensee possesses the special nuclear material under each 
license authorizing the licensee to ship this material, and superseded 
material for three years after each change.
    (2) A licensee who exports a formula quantity of strategic special 
nuclear material shall comply with the requirements of this section and 
Sec. Sec. 73.25 and 73.27, as applicable, up to the first point where 
the shipment is taken off the transport outside the United States. The 
licensee shall retain each record required by these sections for three 
years after the close of period for which the licensee possesses the 
special nuclear material under each license authorizing the licensee to 
export this material, and superseded material for three years after each 
change.
    (d) Security organization. (1) The licensee or his agent shall 
establish a transportation security organization, including armed 
escorts, armed response personnel or guards, and a movement control 
center manned and equipped to monitor and control shipments, to 
communicate with local law enforcement authorities, and to respond to 
safeguards contingencies.
    (2) At least one full time member of the security organization who 
has the authority to direct the physical protection activities of the 
security organization shall be on duty at the movement control center 
during the course of any shipment.
    (3) The licensee or the licensee's agent shall establish, maintain, 
and follow a written management system to provide for the development, 
revision, implementation, and enforcement of transportation physical 
protection procedures. The licensee or the agent shall retain as a 
record the current management system for three years after the close of 
period for which the licensee possesses the special nuclear material 
under the license for which the system was developed and, if any portion 
of the system is superseded, retain the superseded material for three 
years after each change. The system shall include:
    (i) Written security procedures which document the structure of the 
transportation security organization and which detail the duties of 
drivers and escorts and other individuals responsible for security; and
    (ii) Provision for written approval of such procedures and any 
revisions thereto by the individual with overall responsibility for the 
security function.
    (4) Neither the licensee nor the licensee's agent shall permit an 
individual to act as an escort or other security organization member 
unless the individual has been trained, equipped, and qualified to 
perform each assigned security job duty in accordance with appendix B, 
of this part, ``General Criteria for Security Personnel.'' Upon the 
request of an authorized representative of the Commission, the licensee 
or the agent shall demonstrate the ability of the physical security 
personnel to carry out their assigned duties and responsibilities. Armed 
escorts shall requalify in accordance with appendix B to this part at 
least every 12 months. Each requalification must be documented. The 
licensee or the agent shall retain documentation of the initial 
qualification for the term of employment and of each requalification as 
a record for three years from the date of the requalification.
    (5) Armed escort and armed response force personnel armament shall 
include handguns, shotguns, and semiautomatic rifles, as described in 
appendix B to this part.
    (e) Contingency and Response Plans and Procedures. (1) The licensee 
or the licensee's agent shall establish, maintain, and follow a written 
safeguards contingency plan for dealing with

[[Page 484]]

threats, thefts, and radiological sabotage related to strategic special 
nuclear material in transit subject to the provisions of this section. 
This safeguards contingency plan must be in accordance with the criteria 
in appendix C of this part, ``Licensee Safeguards Contingency Plan.'' 
The licensee or the agent shall retain the contingency plan as a record 
for three years after the close of period for which the licensee 
possesses the special nuclear material under each license for which the 
plan is used and superseded material for three years after each change.
    (2) Upon detection of abnormal presence or activity of persons or 
vehicles attempting to penetrate a moving convoy or persons attempting 
to gain access to a parked cargo vehicle or upon evidence or indication 
of penetration of the cargo vehicle the armed escorts or other armed 
response personnel shall:
    (i) Determine whether or not a threat exists;
    (ii) Assess the extent of the threat, if any;
    (iii) Take immediate concurrent measures to neutralize the threat 
by:
    (A) Making the necessary tactical moves to prevent or impede acts of 
radiological sabotage or theft of strategic special nuclear material, 
and
    (B) Informing local law enforcement agencies of the threat and 
requesting assistance.
    (3) The licensee or his agent shall instruct every armed escort and 
all armed response personnel to prevent or impede acts of radiological 
sabotage or theft of strategic special material by using sufficient 
force to counter the force directed at him including the use of deadly 
force when armed escorts or armed response personnel have a reasonable 
belief that it is necessary in self-defense or in the defense of others.
    (f) Transfer and storage of strategic special nuclear material for 
domestic shipments. (1) Strategic special nuclear material shall be 
placed in a protected area at transfer points if transfer is not 
immediate from one transport to another. Where a protected area is not 
available a controlled access area shall be established for the 
shipment. The transport may serve as a controlled access area.
    (2) All transfers shall be protected by at least seven armed escorts 
or other armed personnel--one of whom shall serve as commander. At least 
five of the armed personnel (including the commander) shall be available 
to protect the shipment and at least three of the five shall keep the 
strategic special nuclear material under continuous surveillance while 
it is at the transfer point. The two remaining armed personnel shall 
take up positions at a remote monitoring location. The remote location 
may be a radio-equipped vehicle or a nearby place, apart from the 
shipment area, so that a single act cannot remove the capability of the 
personnel protecting the shipment for calling for assistance. Each of 
the seven armed escorts or other armed personnel shall be capable of 
maintaining communication with each other. The commander shall have the 
capability to communicate with the personnel at the remote location and 
with local law enforcement agencies for emergency assistance. In 
addition, the armed escort personnel at the remote location shall have 
the capability to communicate with the law enforcement agencies and with 
the shipment movement control center. The commander shall call the 
remote location at least every 30 minutes to report the status of the 
shipment. If the calls are not received within the prescribed time, the 
personnel in the remote location shall request assistance from the law 
enforcement authorities, notify the shipment movement control center and 
initiate the appropriate contingency plans. Armed escorts or other armed 
personnel shall observe the opening of the cargo compartment of the 
incoming transport and ensure that the shipment is complete by checking 
locks and seals. A shipment loaded onto or transferred to another 
transport shall be checked to assure complete loading or transfer. 
Continuous visual surveillance of the cargo compartment shall be 
maintained up to the time the transport departs from the terminal. The 
escorts shall observe the transport until it has departed and shall 
notify the licensee or his agent of the latest status immediately 
thereafter.
    (g) Access control subsystems and procedures. (1) A numbered picture 
badge

[[Page 485]]

identification procedure shall be used to identify all individuals who 
will have custody of a shipment. The identification procedure shall 
require that the individual who has possession of the strategic special 
nuclear material shall have, in advance, identification picture badges 
of all individuals who are to assume custody for the shipment. The 
shipment shall be released only when the individual who has possession 
of strategic special nuclear material has assured positive 
identification of all of the persons assuming custody for the shipment 
by comparing the copies of the identification badges that have been 
received in advance to the identification badges carried by the 
individuals who will assume custody of the shipment.
    (2) Access to protected areas, controlled access areas, transports, 
escort vehicles, aircraft, rail cars, and containers where strategic 
special nuclear material is located shall be limited to individuals who 
have been properly identified and have been authorized access to these 
areas.
    (3) Strategic special nuclear material shall be shipped in 
containers that are protected by tamper-indicating seals. The containers 
also shall be locked if they are not in another locked container or 
transport. The outermost container or transport also shall be protected 
by tamper-indicating seals.
    (h) Test and maintenance programs. The licensee or his agent shall 
establish, maintain and follow a test and maintenance program for 
communications equipment and other physical protection related devices 
and equipment used pursuant to this section which shall include the 
following:
    (1) Tests and inspections shall be conducted during the 
installation, and construction of physical protection related subsystems 
and components to assure that they comply with their respective design 
criteria and performance specifications.
    (2) Preoperational tests and inspections shall be conducted for 
physical protection related subsystems and components to demonstrate 
their effectiveness, availability, and reliability with respect to their 
respective design criteria and performance specifications.
    (3) Operational tests and inspections shall be conducted for 
physical protection related subsystems and components to assure their 
maintenance in an operable and effective condition.
    (4) Preventive maintenance programs shall be established for 
physical protection related subsystems and components to assure their 
continued maintenance in an operable and effective condition.
    (5) All physical protection related subsystems and components shall 
be maintained in operable condition. Corrective action procedures and 
compensatory measures shall be developed and employed to assure that the 
effectiveness of the physical protection system is not reduced by any 
single failure or other contingencies affecting the operation of the 
physical protection related equipment or structures.
    (6) The transportation security program must be reviewed at least 
every 12 months by individuals independent of both security program 
management and personnel who have direct responsibility for 
implementation of the security program. The review must include an audit 
of transportation security procedures and practices, an evaluation of 
the effectiveness of the transportation physical protection system, an 
audit of the transportation physical protection system testing and 
maintenance program, and an audit of commitments established for 
response by local law enforcement authorities. The results and 
recommendations of the review, management's findings on whether the 
transportation security program is currently effective, and any actions 
taken as a result of recommendations from prior reviews, must be 
documented in a report to the responsible organization management and to 
corporate management at least one level higher than that having 
responsibility for the day-to-day plant operation. These reports must be 
maintained in an auditable form, available for inspection for a period 
of 3 years.
    (i) Shipment by road. (1) A detailed route plan shall be prepared 
which shows the routes to be taken, the refueling and rest stops, and 
the call-in times to the movement control center. All shipments shall be 
made on primary highways with minimum use of

[[Page 486]]

secondary roads. All shipments shall be made without intermediate stops 
except for refueling, rest or emergency stops.
    (2) Cargo compartments of the trucks or trailers shall be locked and 
protected by tamper-indicating seals.
    (3) The shipment shall be protected by one of the following methods:
    (i) A specially designed cargo vehicle truck or trailer that reduces 
the vulnerability to theft. Design features of the truck or trailer 
shall permit immobilization of the truck or of the cargo-carrying 
portion of the vehicle and shall provide a deterrent to physical 
penetration of the cargo compartment. Two separate escort vehicles shall 
accompany the cargo vehicle. There shall be a total of seven armed 
escorts with at least two in the cargo vehicle. Escorts may also operate 
the cargo and escort vehicles.
    (ii) An armored car cargo vehicle. Three separate escort vehicles 
shall accompany such a cargo vehicle. There shall be a total of seven 
armed escorts, with at least two in the cargo vehicle. Escorts may also 
operate the cargo and escort vehicles.
    (4) All escort vehicles shall be bullet-resisting.
    (5) Procedures shall be established to assure that no unauthorized 
persons or materials are on the cargo vehicle before strategic special 
nuclear material is loaded, or on the escort vehicles, immediately 
before the trip begins.
    (6) Cargo and escort vehicles shall maintain continuous intraconvoy 
two-way communication. In addition at least two of the vehicles shall be 
equipped with radio telephones having the capability of communicating 
with the movement control center. A redundant means of communication 
shall also be available. Calls to the movement control center shall be 
made at least every half hour to convey the status and position of the 
shipment. In the event no call is received in accordance with these 
requirements, the licensee or his agent shall immediately notify the law 
enforcement authorities and the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, and initiate the 
appropriate contingency plan.
    (7) At refueling, rest, or emergency stops at least seven armed 
escorts or other armed personnel shall be available to protect the 
shipment and at least three armed escorts or other armed personnel shall 
maintain continuous visual surveillance of the cargo compartment.
    (8) Transfers to and from other modes of transportation shall be in 
accordance with paragraph (f) of this section.
    (j) Shipment by air. (1) All shipments on commercial cargo aircraft 
shall be accompanied by two armed escorts who shall be able to converse 
in a common language with the captain of the aircraft.
    (2) Transfers of these shipments shall be minimized and shall be 
conducted in accordance with paragraph (f) of this section. Such 
shipments shall be scheduled so that the strategic special nuclear 
material is loaded last and unloaded first.
    (3) At scheduled stops, at least seven armed escorts or other armed 
personnel shall be available to protect the shipment and at least three 
armed escorts or other armed personnel shall maintain continuous visual 
surveillance of the cargo compartment.
    (4) Export shipments shall be accompanied by two armed escorts from 
the last terminal in the United States until the shipment is unloaded at 
a foreign terminal and primary responsibility for physical protection is 
assumed by agents of the consignee. While on foreign soil, the escorts 
may surrender their weapons to legally constituted local authorities. 
After leaving the last terminal in the United States the shipment shall 
be scheduled with no intermediate stops.
    (5) Import shipments shall be accompanied by two armed escorts at 
all times within the geographical limits of the United States. These 
escorts shall provide physical protection for the shipment until 
relieved by verified agents of the U.S. consignee.
    (6) Procedures shall be established to assure that no unauthorized 
persons or material are on the aircraft before strategic special nuclear 
material is loaded on board.
    (7) Arrangements shall be made at all domestic airports to assure 
that the seven required armed escorts or other

[[Page 487]]

armed personnel are available and that the required security measures 
will be taken upon landing.
    (8) Arrangements shall be made at the foreign terminal at which the 
shipment is to be unloaded to assure that security measures will be 
taken on arrival.
    (k) Shipment by rail. (1) A shipment by rail shall be escorted by 
seven armed escorts in the shipment car or an escort car next to the 
shipment car of the train. At least three escorts shall keep the 
shipment car under continuous visual surveillance. Escorts shall detrain 
at stops when practicable and time permits to maintain the shipment cars 
under continuous visual surveillance and to check car or container locks 
and seals.
    (2) Procedures shall be established to assure that no unauthorized 
persons or materials are on the shipment or escort car before strategic 
special nuclear material is loaded on board.
    (3) Only containers weighing 5,000 lbs or more shall be shipped on 
open rail cars.
    (4) A voice communication capability between the escorts and the 
movement control center shall be maintained. A redundant means of 
continuous communication also shall be available. Calls to the movement 
control center shall be made at least every half hour to convey the 
status and position of the shipment. In the event no call is received in 
accordance with these requirements, the licensee or his agent shall 
immediately notify the law enforcement authorities and the appropriate 
Nuclear Regulatory Commission Regional Office listed in appendix A of 
this part and initiate their contingency plan.
    (5) Transfer to and from other modes of transportation shall be in 
accordance with paragraph (f) of this section.
    (l) Shipment by sea. (1) Shipments shall be made only on container-
ships. The strategic special nuclear material container(s) shall be 
loaded into exclusive use cargo containers conforming to American 
National Standards Institute (ANSI) Standard MH5.1--``Basic Requirements 
for Cargo Containers'' (1971) or International Standards Organization 
(ISO) 1496, ``General Cargo Containers'' (1978). Locks and seals shall 
be inspected by the escorts whenever access is possible. The ANSI 
Standard MH5.1 (1971) and the (ISO) 1496 (1978), have been approved for 
incorporation by reference by the Director of the Federal Register. A 
copy of each of these standards is available for inspection at the NRC 
Library, 11545 Rockville Pike, Rockville, Maryland 20852-2738.
    (2) All shipments shall be accompanied by two armed escorts who 
shall be able to converse in a common language with the captain of the 
ship.
    (3) Minimum domestic ports of call shall be scheduled and there 
shall be no scheduled transfer to other vessels after the shipment 
leaves the last port in the United States. Transfer to and from other 
modes of transportation shall be in accordance with paragraph (f) of 
this section.
    (4) At all ports of call the escorts shall ensure that the shipment 
is not removed. At least two armed escorts or other armed personnel 
shall maintain continuous visual surveillance of the cargo area where 
the container is stored up to the time the ship departs.
    (5) Export shipments shall be accompanied by two armed escorts from 
the last port in the United States until the shipment is unloaded at a 
foreign terminal and prime responsibility for physical protection is 
assumed by agents of the consignee. While on foreign soil, the escorts 
may surrender their weapons to legally constituted local authorities.
    (6) Import shipments shall be accompanied by two armed escorts at 
all times within the geographical limits of the United States. These 
escorts shall provide physical protection for the shipment until 
relieved by verified agents of the U.S. consignee.
    (7) Ship-to-shore communications shall be available, and a ship-to-
shore contact shall be made every six hours to relay position 
information, and the status of the shipment.
    (8) Arrangements shall be made at the foreign terminals at which the 
shipment is to be unloaded to assure

[[Page 488]]

that security measures will be taken upon arrival.

[44 FR 68190, Nov. 28, 1979, as amended at 46 FR 2025, Jan. 8, 1981; 53 
FR 19257, May 27, 1988; 57 FR 33430, July 29, 1992; 57 FR 61787, Dec. 
29, 1992; 59 FR 50689, Oct. 5, 1994; 67 FR 3586, Jan. 25, 2002; 68 FR 
14530, Mar. 26, 2003; 68 FR 23575, May 5, 2003; 74 FR 62684, Dec. 1, 
2009]



Sec. 73.27  Notification requirements.

    (a)(1) A licensee who delivers formula quantities of strategic 
special nuclear material to a carrier for transport shall immediately 
notify the consignee by telephone, telegraph, or teletype, of the time 
of departure of the shipment, and shall notify or confirm with the 
consignee the method of transportation, including the names of carriers, 
and the estimated time of arrival of the shipment at its destination.
    (2) In the case of a shipment (f.o.b.) the point where it is 
delivered to a carrier for transport, a licensee shall, before the 
shipment is delivered to the carrier, obtain written certification from 
the licensee who is to take delivery of the shipment at the f.o.b. point 
that the physical protection arrangements required by Sec. Sec. 73.25 
and 73.26 for licensed shipments have been made. When a contractor 
exempt from the requirements for a Commission license is the consignee 
of a shipment, the licensee shall, before the shipment is delivered to 
the carrier, obtain written certification from the contractor who is to 
take delivery of the shipment at the f.o.b. point that the physical 
protection arrangements required by the United States Department of 
Energy Order Nos. 5632.1 or 5632.2, as appropriate, have been made.
    (3) A licensee who delivers formula quantities of strategic special 
nuclear material to a carrier for transport or releases such special 
nuclear material f.o.b. at the point where it is delivered to a carrier 
for transport shall also make arrangements with the consignee to be 
notified immediately by telephone and telegraph, teletype, or cable, of 
the arrival of the shipment at its destination or of any such shipment 
that is lost or unaccounted for after the estimated time of arrival at 
its destination.
    (b) Each licensee who receives a shipment of formula quantities of 
strategic special nuclear material shall immediately notify by telephone 
and telegraph or teletype, the person who delivered the material to a 
carrier for transport and the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, of the arrival of the 
shipment at its destination. When a United States Department of Energy 
license-exempt contractor is the consignee, the licensee who is the 
consignor shall notify by telephone and telegraph, or teletype, the 
Director, Division of Security Policy, Office of Nuclear Security and 
Incident Response of the arrival of the shipment at its destination 
immediately upon being notified of the receipt of the shipment by the 
license-exempt contractor as arranged pursuant to paragraph (a)(3) of 
this section. In the event such a shipment fails to arrive at its 
destination at the estimated time, or in the case of an export shipment, 
the licensee who exported the shipment, shall immediately notify by 
telephone and telegraph or teletype, the Director, Division of Security 
Policy, Office of Nuclear Security and Incident Response, and the 
licensee or other person who delivered the material to a carrier for 
transport. The licensee who made the physical protection arrangements 
shall also immediately notify by telephone and telegraph, or teletype, 
the Director, Division of Security Policy, Office of Nuclear Security 
and Incident Response of the action being taken to trace the shipment.
    (c) Each licensee who makes arrangements for physical protection of 
a shipment of formula quantities of strategic special nuclear material 
as required by Sec. Sec. 73.25 and 73.26 shall immediately conduct a 
trace investigation of any shipment that is lost or unaccounted for 
after the estimated arrival time and file a report with the Commission 
as specified in Sec. 73.71.

[44 FR 68192, Nov. 28, 1979, as amended at 67 FR 3586, Jan. 25, 2002; 68 
FR 14530, Mar. 26, 2003; 68 FR 23575, May 5, 2003; 74 FR 62684, Dec. 1, 
2009]

[[Page 489]]



Sec. 73.28  Security background checks for secure transfer of nuclear
materials.

    Licensees are excepted from the security background check provisions 
in Section 170I of the AEA if they have not received Orders from the 
Nuclear Regulatory Commission containing requirements for background 
checks for trustworthiness and reliability that include fingerprinting 
and criminal history record checks as a prerequisite for unescorted 
access to radioactive materials.

[72 FR 3027, Jan. 24, 2007]



Sec. 73.35  Requirements for physical protection of irradiated reactor 
fuel (100 grams or less) in transit.

    Each licensee who transports, or delivers to a carrier for 
transport, in a single shipment, a quantity of irradiated reactor fuel 
weighing 100 grams (0.22 pounds) or less in net weight of irradiated 
fuel, exclusive of cladding or other structural or packaging material, 
which has a total external radiation dose rate in excess of 1 Gray (100 
rad) per hour at a distance of 1 meter (3.3 feet) from any accessible 
surface without intervening shielding, shall follow the physical 
protection requirements for category 1 quantities of radioactive 
material in subpart D of part 37 of this chapter.

[78 FR 17021, Mar. 19, 2013]



Sec. 73.37  Requirements for physical protection of irradiated reactor
fuel in transit.

    (a) Performance objectives. (1) Each licensee who transports, or 
delivers to a carrier for transport, in a single shipment, a quantity of 
irradiated reactor fuel \1\ in excess of 100 grams (0.22 lbs) in net 
weight of irradiated fuel, exclusive of cladding or other structural or 
packaging material, which has a total external radiation dose rate in 
excess of 1 Gy (100 rad) per hour at a distance of 1 meter (3.3 feet) 
from any accessible surface without intervening shielding, shall 
establish and maintain, or make arrangements for, and assure the proper 
implementation of, a physical protection system for shipments of such 
material that will achieve the following objectives:
---------------------------------------------------------------------------

    \1\ For purposes of 10 CFR 73.37, the terms ``irradiated reactor 
fuel'' and ``spent nuclear fuel'' are used interchangeably.
---------------------------------------------------------------------------

    (i) Minimize the potential for theft, diversion, or radiological 
sabotage of spent nuclear fuel shipments; and
    (ii) Facilitate the location and recovery of spent nuclear fuel 
shipments that may have come under the control of unauthorized persons.
    (2) To achieve these objectives, the physical protection system 
shall:
    (i) Provide for early detection and assessment of attempts to gain 
unauthorized access to, or control over, spent nuclear fuel shipments;
    (ii) Delay and impede attempts at theft, diversion, or radiological 
sabotage of spent nuclear fuel shipments; and
    (iii) Provide for notification to the appropriate response forces of 
any attempts at theft, diversion, or radiological sabotage of a spent 
nuclear fuel shipment.
    (b) General requirements. To achieve the performance objectives of 
paragraph (a) of this section, a physical protection system established 
and maintained, or arranged for, by the licensee shall include the 
following elements:
    (1) Preplan and coordinate spent nuclear fuel shipments. Each 
licensee shall:
    (i) Ensure that each armed escort, as defined in Sec. 73.2, is 
instructed on the use of force sufficient to counter the force directed 
at the person, including the use of deadly force when the armed escort 
has a reasonable belief that the use of deadly force is necessary in 
self-defense or in the defense of others, or any other circumstances, as 
authorized by applicable Federal and State laws. This deadly force 
training requirement does not apply to members of local law enforcement 
agencies (LLEAs) performing escort duties for spent nuclear fuel 
shipments.
    (ii) Preplan and coordinate shipment itineraries to ensure that the 
receiver at the final delivery point is present to accept the shipment.
    (iii) Ensure written certification of any transfer of custody.
    (iv) Preplan and coordinate shipment information no later than 2 
weeks prior to the shipment or prior to the first

[[Page 490]]

shipment of a series of shipments with the governor of a State, or the 
governor's designee, of a shipment of spent nuclear fuel through or 
across the boundary of the State, in order to:
    (A) Minimize intermediate stops and delays;
    (B) Arrange for State law enforcement escorts;
    (C) Arrange for positional information sharing when requested; and
    (D) Develop route information, including the identification of safe 
havens.
    (v) Arrange with local law enforcement authorities along the 
shipment route, including U.S. ports where vessels carrying spent 
nuclear fuel shipments are docked, for their response to a security-
related emergency or a call for assistance.
    (vi) Preplan and coordinate with the NRC to obtain advance approval 
of the routes used for road and rail shipments of spent nuclear fuel, 
and of any U.S. ports where vessels carrying spent nuclear fuel 
shipments are scheduled to stop. In addition to the requirements of this 
section, routes used for shipping spent nuclear fuel shall comply with 
the applicable requirements of the DOT regulations in Title 49 of the 
Code of Federal Regulations (49 CFR), in particular those identified in 
Sec. 71.5 of this chapter. The advance approval application shall 
provide:
    (A) For road shipments, the route shall include locations of safe 
havens that have been coordinated with the appropriate State(s).
    (B) The NRC approval shall be obtained prior to the 10-day advance 
notification requirement in Sec. 73.72 of this part.
    (C) Information to be supplied to the NRC shall include, but is not 
limited to, the following:
    (1) Shipper, consignee, carriers, transfer points, modes of 
shipment; and
    (2) A statement of shipment security arrangements, including, if 
applicable, points where armed escorts transfer responsibility for the 
shipment.
    (vii) Document the preplanning and coordination activities.
    (viii) Ensure the protection of Safeguards Information relative to 
spent nuclear fuel in transit in accordance with Sec. Sec. 73.21 and 
73.22 of this part, especially the information described in Sec. 
73.22(a)(2), which would include, at a minimum, the protection of the 
following information:
    (A) The preplanning and coordination activities;
    (B) Transportation physical security plan;
    (C) Schedules and itineraries for specific spent nuclear fuel 
shipments until the information is no longer controlled as Safeguards 
Information, that is until at least 10 days after the shipment has 
entered or originated within the state; or for the case of a shipment in 
a series of shipments whose schedules are related, a statement that 
schedule information must be protected until 10 days after the last 
shipment in the series has entered or originated within the state and an 
estimate of the date on which the last shipment in the series will enter 
or originate within the state;
    (D) Vehicle immobilization features, intrusion alarm devices, and 
communications;
    (E) Arrangements with and capabilities of local police response 
forces, and locations of safe havens identified along the transportation 
route;
    (F) Limitations of communications during transport;
    (G) Procedures for response to security contingency events;
    (H) Information concerning the tactics and capabilities required to 
defend against attempted sabotage, or theft and diversion of irradiated 
reactor fuel, or related information; and
    (I) Engineering or safety analyses, security-related procedures or 
scenarios and other information related to the protection of the 
transported material if the unauthorized disclosure of such analyses, 
procedures, scenarios, or other information could reasonably be expected 
to have a significant adverse effect on the health and safety of the 
public or the common defense and security by significantly increasing 
the likelihood of theft, diversion, or sabotage of spent nuclear fuel in 
transit.
    (2) Advance notifications. Prior to the shipment of spent nuclear 
fuel moving through or across the boundary of any State, outside the 
confines of the licensee's facility or other place of use or storage, a 
licensee subject to this

[[Page 491]]

section shall provide notification to the NRC, under Sec. 73.72 of this 
part, and the governor of the State(s), or the governor's designee(s), 
of the spent nuclear fuel shipment. After June 11, 2013, the compliance 
date of the Tribal notification final rule, a licensee subject to this 
section shall notify the Tribal official or Tribal official's designee 
of each participating Tribe referenced in Sec. 71.97(c)(3) of this 
chapter prior to the transport of spent fuel within or across the Tribal 
reservation. Contact information for each State, including telephone and 
mailing addresses of governors and governors' designees, and 
participating Tribes, including telephone and mailing addresses of 
Tribal officials and Tribal official's designees, is available on the 
NRC Web site at: https://scp.nrc.gov/special/designee.pdf''. A list of 
the contact information is also available upon request from the 
Director, Division of Material Safety, State, Tribal, and Rulemaking 
Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555. The 
licensee shall comply with the following criteria in regard to each 
notification:
    (i) Procedures for submitting advance notification. (A) The 
notification must be in writing and sent to the office of each 
appropriate governor or the governor's designee and each appropriate 
Tribal official or the Tribal official's designee.
    (B) A notification delivered by mail must be postmarked at least 10 
days before transport of a shipment within or through the State or 
Tribal reservation.
    (C) A notification delivered by any other method must reach the 
office of the governor or the governor's designee and any Tribal 
official or Tribal official's designee at least 7 days before transport 
of a shipment within or through the State.
    (ii) Information to be furnished in advance notification of 
shipment. The notification must include the following information:
    (A) The name, address, and telephone number of the shipper, carrier 
and receiver of the shipment and the license number of the shipper and 
receiver;
    (B) A description of the shipment as specified by DOT in 49 CFR 
172.202 and 172.203(d); and
    (C) A listing of the routes to be used within the State or Tribal 
reservation.
    (iii) Separate enclosure. The licensee shall provide the following 
information, under Sec. 73.22(f)(1), in a separate enclosure to the 
written notification:
    (A) The estimated date and time of departure from the point of 
origin of the shipment;
    (B) The estimated date and time of entry into the State or Tribal 
reservation;
    (C) The estimated date and time of arrival of the shipment at the 
destination;
    (D) For the case of a single shipment whose schedule is not related 
to the schedule of any subsequent shipment, a statement that schedule 
information must be protected under the provisions of Sec. Sec. 73.21 
and 73.22 until at least 10 days after the shipment has entered or 
originated within the State or Tribal reservation; and
    (E) For the case of a shipment in a series of shipments whose 
schedules are related, a statement that schedule information must be 
protected under the provisions of Sec. Sec. 73.21 and 73.22 of this 
part until 10 days after the last shipment in the series has entered or 
originated within the State or Tribal reservation, and an estimate of 
the date on which the last shipment in the series will enter or 
originate within the State or Tribal reservation.
    (iv) Revision notice. A licensee shall notify by telephone a 
responsible individual in the office of the governor or in the office of 
the governor's designee and the office of the Tribal official or in the 
office of the Tribal official's designee of any schedule change that 
differs by more than 6 hours from the schedule information previously 
furnished under paragraph (b)(2)(iii) of this section, and shall inform 
that individual of the number of hours of advance or delay relative to 
the written schedule information previously furnished.
    (v) Cancellation notice. Each licensee who cancels a shipment for 
which advance notification has been sent shall send a cancellation 
notice to the governor or to the governor's designee of each State 
previously notified, each Tribal official or the Tribal official's 
designee previously notified, and to the

[[Page 492]]

NRC's Director, Division of Security Policy, Office of Nuclear Security 
and Incident Response, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555. The licensee shall state in the notice that it is a 
cancellation and identify the advance notification that is being 
canceled.
    (vi) Records. The licensee shall retain a copy of the preplanning 
and coordination activities, advance notification, and any revision or 
cancellation notice as a record for 3 years under Sec. 73.70 of this 
part.
    (3) Transportation physical protection program. (i) The 
transportation physical protection program established under paragraph 
(a)(1) of this section shall include armed escorts to protect spent 
nuclear fuel shipments and a movement control center, as defined in 
Sec. 73.2 of this part, staffed and equipped to monitor and control 
spent nuclear fuel shipments, to communicate with local law enforcement 
authorities, and to respond to safeguards contingencies.
    (ii) The movement control center must be staffed continuously by at 
least one individual who will actively monitor the progress of the spent 
nuclear fuel shipment and who has the authority to coordinate the 
physical protection activities.
    (iii) The movement control center personnel must monitor the 
shipment continuously, i.e., 24-hours per day, from the time the 
shipment commences, or if delivered to a carrier for transport, from the 
time of delivery of the shipment to the carrier, until safe delivery of 
the shipment at its final destination, and must immediately notify the 
appropriate agencies in the event of a safeguards event under the 
provisions of Sec. 73.71 of this part.
    (iv) The movement control center personnel and the armed escorts 
must maintain a written log for each spent nuclear fuel shipment, which 
will include information describing the shipment and significant events 
that occur during the shipment. The log must be available for review by 
authorized NRC personnel for a period of at least 3 years following 
completion of the shipment.
    (v) The licensee shall develop, maintain, revise and implement 
written transportation physical protection procedures which address the 
following:
    (A) Access controls to ensure no unauthorized persons have access to 
the shipment and Safeguards Information;
    (B) Roles and responsibilities of the movement control center 
personnel, drivers, armed escorts and other individuals relative to the 
security of the shipment;
    (C) Reporting of safeguards events under Sec. 73.71 of this part;
    (D) Communications protocols that include a strategy for the use of 
authentication and duress codes, the management of refueling or other 
stops, detours, and the loss of communications, temporarily or 
otherwise; and
    (E) Normal conditions operating procedures.
    (vi) The licensee shall retain as a record the transportation 
physical protection procedures for 3 years after the close of period for 
which the licensee possesses the spent nuclear fuel.
    (vii) The transportation physical protection program shall:
    (A) Provide that escorts (other than members of local law 
enforcement agencies serving as armed escorts, or ship's officers 
serving as unarmed escorts) have successfully completed the training 
required by appendix D of this part, including the equivalent of the 
weapons training and qualifications program required of guards, as 
described in sections III and IV of appendix B of this part, to assure 
that each such individual is fully qualified to use the assigned 
weapons;
    (B) Provide that shipment escorts communicate with the movement 
control center at random intervals, not to exceed 2 hours, to advise of 
the status of the shipment for road and rail shipments, and for sea 
shipments while shipment vessels are docked at U.S. ports; and
    (C) Provide that at least one armed escort remains alert at all 
times, maintains constant visual surveillance of the shipment, and 
periodically reports to the movement control center at regular intervals 
not to exceed 30 minutes during periods when the shipment vehicle is 
stopped, or the shipment vessel is docked.

[[Page 493]]

    (4) Contingency and response procedures. (i) In addition to the 
procedures established under paragraph (b)(3)(v) of this section, the 
licensee shall establish, maintain, and follow written contingency and 
response procedures to address threats, thefts, and radiological 
sabotage related to spent nuclear fuel in transit.
    (ii) The licensee shall ensure that personnel associated with the 
shipment shall be appropriately trained regarding contingency and 
response procedures.
    (iii) The licensee shall retain the contingency and response 
procedures as a record for 3 years after the close of period for which 
the licensee possesses the spent nuclear fuel.
    (iv) The contingency and response procedures must direct that, upon 
detection of the abnormal presence of unauthorized persons, vehicles, or 
vessels in the vicinity of a spent nuclear fuel shipment or upon 
detection of a deliberately induced situation that has the potential for 
damaging a spent nuclear fuel shipment, the armed escort will:
    (A) Determine whether or not a threat exists;
    (B) Assess the extent of the threat, if any;
    (C) Implement the procedures developed under paragraph (b)(4)(i) of 
this section;
    (D) Take the necessary steps to delay or impede threats, thefts, or 
radiological sabotage of spent nuclear fuel; and
    (E) Inform local law enforcement agencies of the threat and request 
assistance without delay, but not to exceed 15 minutes after discovery.
    (c) Shipments by road. In addition to the provisions of paragraph 
(b) of this section, the physical protection system for any portion of a 
spent nuclear fuel shipment by road shall provide that:
    (1) The transport vehicle is:
    (i) Occupied by at least two individuals, one of whom serves as an 
armed escort, and escorted by an armed member of the local law 
enforcement agency in a mobile unit of such agency; or
    (ii) Led by a separate vehicle occupied by at least one armed 
escort, and trailed by a third vehicle occupied by at least one armed 
escort.
    (2) As permitted by law, all armed escorts are equipped with a 
minimum of two weapons. This requirement does not apply to local law 
enforcement agency personnel who are performing escort duties.
    (3) The transport vehicle and each escort vehicle are equipped with 
redundant communication abilities that provide 2-way communications 
between the transport vehicle, the escort vehicle(s), the movement 
control center, local law enforcement agencies, and one another. To 
ensure that 2-way communication is possible at all times, alternate 
communications should not be subject to the same failure modes as the 
primary communication.
    (4) The transport vehicle is equipped with NRC-approved features 
that permit immobilization of the cab or cargo-carrying portion of the 
vehicle.
    (5) The transport vehicle driver has been familiarized with, and is 
capable of implementing, transport vehicle immobilization, 
communications, and other security procedures.
    (6) Shipments are continuously and actively monitored by a 
telemetric position monitoring system or an alternative tracking system 
reporting to a movement control center. A movement control center shall 
provide positive confirmation of the location, status, and control over 
the shipment. The movement control center shall implement preplanned 
procedures in response to deviations from the authorized route or a 
notification of actual, attempted, or suspicious activities related to 
the theft, loss, diversion, or radiological sabotage of a shipment. 
These procedures shall include, but not be limited to, the 
identification of and contact information for the appropriate local law 
enforcement agency along the shipment route.
    (d) Shipments by rail. In addition to the provisions of paragraph 
(b) of this section, the physical protection system for any portion of a 
spent nuclear fuel shipment by rail shall provide that:
    (1) A shipment car is accompanied by two armed escorts (who may be 
members of a local law enforcement agency), at least one of whom is 
stationed at a location on the train that will permit observation of the 
shipment car while in motion.

[[Page 494]]

    (2) As permitted by law, all armed escorts are equipped with a 
minimum of two weapons. This requirement does not apply to local law 
enforcement agency personnel who are performing escort duties.
    (3) The train operator(s) and each escort are equipped with 
redundant communication abilities that provide 2-way communications 
between the transport, the escort vehicle(s), the movement control 
center, local law enforcement agencies, and one another. To ensure that 
2-way communication is possible at all times, alternate communications 
should not be subject to the same failure modes as the primary 
communication.
    (4) Rail shipments are monitored by a telemetric position monitoring 
system or an alternative tracking system reporting to the licensee, 
third-party, or railroad movement control center. The movement control 
center shall provide positive confirmation of the location of the 
shipment and its status. The movement control center shall implement 
preplanned procedures in response to deviations from the authorized 
route or to a notification of actual, attempted, or suspicious 
activities related to the theft, diversion, or radiological sabotage of 
a shipment. These procedures shall include, but not be limited to, the 
identification of and contact information for the appropriate local law 
enforcement agency along the shipment route.
    (e) Shipments by U.S. waters. In addition to the provisions of 
paragraph (b) of this section, the physical protection system for any 
portion of a spent nuclear fuel shipment traveling on U.S. waters shall 
provide that:
    (1) A shipment vessel while docked at a U.S. port is protected by:
    (i) Two armed escorts stationed on board the shipment vessel, or 
stationed on the dock at a location that will permit observation of the 
shipment vessel; or
    (ii) A member of a local law enforcement agency, equipped with 
normal local law enforcement agency radio communications, who is 
stationed on board the shipment vessel, or on the dock at a location 
that will permit observation of the shipment vessel.
    (2) As permitted by law, all armed escorts are equipped with a 
minimum of two weapons. This requirement does not apply to local law 
enforcement agency personnel who are performing escort duties.
    (3) A shipment vessel while within U.S. territorial waters shall be 
accompanied by an individual, who may be an officer of the shipment 
vessel's crew, who will assure that the shipment is unloaded only as 
authorized by the licensee.
    (4) Each armed escort is equipped with redundant communication 
abilities that provide 2-way communications between the vessel, the 
movement control center, local law enforcement agencies, and one 
another. To ensure that 2-way communication is possible at all times, 
alternate communications should not be subject to the same failure modes 
as the primary communication.
    (f) Investigations. Each licensee who makes arrangements for the 
shipment of spent nuclear fuel shall immediately conduct an 
investigation, in coordination with the receiving licensee, of any 
shipment that is lost or unaccounted for after the designated no-later-
than arrival time in the advance notification.
    (g) State officials, State employees, Tribal officials, Tribal 
employees, and other individuals, whether or not licensees of the NRC, 
who receive information of the kind specified in paragraph (b)(2)(iii) 
of this section and any other Safeguards Information as defined in Sec. 
73.22(a) of this part shall protect that information against 
unauthorized disclosure as specified in Sec. Sec. 73.21 and 73.22 of 
this part.

[78 FR 29550, May 20, 2013, as amended at 79 FR 75741, Dec. 19, 2014; 80 
FR 74981, Dec. 1, 2015]



Sec. 73.38  Personnel access authorization requirements for irradiated
reactor fuel in transit.

    (a) General. (1) Each licensee who transports, or delivers to a 
carrier for transport, in a single shipment, a quantity of spent nuclear 
fuel as described in Sec. 73.37(a)(1) of this part shall comply with 
the requirements of this section,

[[Page 495]]

as appropriate, before any spent nuclear fuel is transported or 
delivered to a carrier for transport.
    (2) Each licensee shall establish, implement, and maintain its 
access authorization program under the requirements of this section.
    (i) Each licensee shall be responsible for the continuing 
effectiveness of the access authorization program.
    (ii) Each licensee shall ensure that the access authorization 
program is reviewed at an appropriate frequency to confirm compliance 
with the requirements of this section and that prompt comprehensive 
actions are taken to correct any noncompliance that is identified.
    (iii) The review shall evaluate all program performance objectives 
and requirements.
    (iv) Each review report must document conditions that are adverse to 
the proper performance of the access authorization program, the cause of 
the condition(s), and when appropriate, recommended corrective actions, 
and corrective actions taken. The licensee shall review the audit 
findings and take any additional corrective actions necessary to 
preclude repetition of the condition, including reassessment of the 
deficient areas where indicated.
    (3) By August 19, 2013, each licensee that is subject to this 
provision shall implement the requirements of this section through 
revisions to its physical security plan or transportation security plan.
    (b) General performance objective. The licensee's access 
authorization program must ensure that the individuals specified in 
paragraph (c) of this section are trustworthy and reliable such that 
they do not constitute an unreasonable risk to public health and safety 
or the common defense and security.
    (c) Applicability. (1) Licensees shall subject the following 
individuals to an access authorization program:
    (i) Any individual to whom a licensee intends to grant unescorted 
access to spent nuclear fuel in transit, including employees of a 
contractor or vendor;
    (ii) Any individual whose duties and responsibilities permit the 
individual to take actions by physical or electronic means that could 
adversely impact the safety, security, or emergency response to spent 
nuclear fuel in transit (i.e., movement control personnel, vehicle 
drivers, or other individuals accompanying spent nuclear fuel 
shipments);
    (iii) Any individual whose duties and responsibilities include 
implementing a licensee's physical protection program under Sec. 73.37, 
including but not limited to, non-LLEA armed escorts;
    (iv) Any individual whose assigned duties and responsibilities 
provide access to spent nuclear fuel shipment information that is 
considered to be Safeguards Information under Sec. 73.22(a)(2); and
    (v) The licensee access authorization program reviewing official.
    (2) Fingerprinting, and the identification and criminal history 
records checks required by Section 149 of the Atomic Energy Act of 1954, 
as amended, and other elements of the background investigation are not 
required for the following individuals prior to granting access 
authorization relative to spent nuclear fuel in transit:
    (i) Persons identified in Sec. Sec. 73.59 and 73.61 of this part;
    (ii) Federal, State, and local officials, including inspectors, 
whose occupational status are consistent with the promotion of common 
defense and security and the protection of public health and safety 
relative to spent nuclear fuel in transit;
    (iii) Emergency response personnel who are responding to an 
emergency;
    (iv) An individual who has had a favorably adjudicated U.S. 
Government criminal history records check within the last 5 years, under 
a comparable U.S. Government program involving fingerprinting and an FBI 
identification and criminal history records check (e.g. National Agency 
Check, Transportation Worker Identification Credentials (TWIC) under 49 
CFR part 1572, Bureau of Alcohol Tobacco Firearms and Explosives 
background check and clearances under 27 CFR part 555, Health and Human 
Services security risk assessments for possession and use of select 
agents and toxins under 42 CFR part 73, Hazardous Material security 
threat assessment for hazardous material endorsement to commercial 
drivers license under 49 CFR part 1572, Customs and Border Patrol's Free 
and

[[Page 496]]

Secure Trade (FAST) Program) provided that he or she makes available the 
appropriate documentation. Written confirmation from the agency/employer 
that granted the Federal security clearance or reviewed the criminal 
history records check must be provided to the licensee. The licensee 
shall retain this documentation for a period of 3 years from the date 
the individual no longer requires access authorization relative to spent 
nuclear fuel in transit; and
    (v) Any individual who has an active Federal security clearance, 
provided that he or she makes available the appropriate documentation. 
Written confirmation from the agency/employer that granted the Federal 
security clearance or reviewed the criminal history records check must 
be provided to the licensee. The licensee shall retain this 
documentation for a period of 3 years from the date the individual no 
longer requires access authorization relative to spent nuclear fuel in 
transit.
    (d) Background investigation. Before allowing an individual to have 
unescorted access or access authorization relative to spent nuclear fuel 
\2\ in transit the licensees shall complete a background investigation 
as defined in Sec. 73.2 of this part of the individual seeking to have 
unescorted access or access authorization. The scope of the 
investigation must encompass at least the past 10 years, or if 10 years 
of information is not available then as many years in the past that 
information is available. The background investigation does not apply to 
Federal, State or local law enforcement personnel who are performing 
escort duties. The background investigation must include, but is not 
limited to, the following elements:
---------------------------------------------------------------------------

    \2\ For purposes of 10 CFR 73.38, the terms ``irradiated reactor 
fuel'' as described in 10 CFR 73.37 and ``spent nuclear fuel'' are used 
interchangeably.
---------------------------------------------------------------------------

    (1) Informed consent. Licensees shall not initiate any element of a 
background investigation without the informed and signed consent of the 
subject individual. This consent shall include authorization to share 
personal information with appropriate entities. The licensee to whom the 
individual is applying for access authorization shall inform the 
individual of his or her right to review information collected to assure 
its accuracy, and provide the individual with an opportunity to correct 
any inaccurate or incomplete information that is developed by the 
licensee.
    (i) The subject individual may withdraw his or her consent at any 
time. Licensees shall inform the individual that:
    (A) Withdrawal of his or her consent will remove the individual's 
application for access authorization under the licensee's access 
authorization program; and
    (B) Other licensees shall have access to information documenting the 
withdrawal.
    (ii) If an individual withdraws his or her consent, licensees may 
not initiate any elements of the background investigation that were not 
in progress at the time the individual withdrew his or her consent, but 
shall complete any background investigation elements that are in 
progress at the time consent is withdrawn. The licensee shall record the 
status of the individual's application for access authorization. 
Additionally, licensees shall collect and maintain the individual's 
application for access authorization; his or her withdrawal of consent 
for the background investigation; the reason given by the individual for 
the withdrawal; and any pertinent information collected from the 
background investigation elements that were completed. This information 
must be shared with other licensees under paragraph (l)(4) of this 
section.
    (iii) Licensees shall inform, in writing, any individual who is 
applying for access authorization that the following actions are 
sufficient cause for denial or unfavorable termination of access 
authorization status:
    (A) Refusal to provide a signed consent for the background 
investigation;
    (B) Refusal to provide, or the falsification of, any personal 
history information required under this section, including the failure 
to report any previous denial or unfavorable termination of access 
authorization;

[[Page 497]]

    (C) Refusal to provide signed consent for the sharing of personal 
information with other licensees under paragraph (d)(5)(v) of this 
section; or
    (D) Failure to report any arrests or legal actions specified in 
paragraph (f) of this section.
    (2) Personal history disclosure. Any individual who is required to 
have a background investigation under this section shall disclose the 
personal history information that is required by the licensee's access 
authorization program for the reviewing official to make a determination 
of the individual's trustworthiness and reliability. Refusal to provide, 
or the falsification of, any personal history information required by 
this section is sufficient cause for denial or termination of access 
authorization.
    (3) Criminal history. Fingerprinting and an FBI identification and 
criminal history records check under Sec. 73.57 of this part.
    (4) Verification of true identity. Licensees shall verify the true 
identity of an individual who is applying to have access authorization 
to ensure that the applicant is who they claim to be. A licensee shall 
review official identification documents (e.g., driver's license, 
passport, government identification, State, province, or country of 
birth issued certificate of birth) and compare the documents to personal 
information data provided by the individual to identify any discrepancy 
in the information. Licensees shall document the type, expiration, and 
identification number of the identification, or maintain a photocopy of 
identifying documents on file under Sec. 73.38(c). Licensees shall 
certify and affirm in writing that the identification was properly 
reviewed and maintain the certification and all related documents for 
review upon inspection.
    (5) Employment history evaluation. Licensees shall ensure that an 
employment history evaluation has been completed on a best effort basis, 
by questioning the individual's present and former employers, and by 
determining the activities of the individual while unemployed.
    (i) For the claimed employment period, the individual must provide 
the reason for any termination, eligibility for rehire, and other 
information that could reflect on the individual's trustworthiness and 
reliability.
    (ii) If the claimed employment was military service the individual 
shall provide a characterization of service, reason for separation, and 
any disciplinary actions that could affect a trustworthiness and 
reliability determination.
    (iii) If education is claimed in lieu of employment, the individual 
shall provide any information related to the claimed education that 
could reflect on the individual's trustworthiness and reliability and, 
at a minimum, verify that the individual was registered for the classes 
and received grades that indicate that the individual participated in 
the educational process during the claimed period.
    (iv) If a previous employer, educational institution, or any other 
entity with which the individual claims to have been engaged fails to 
provide information or indicates an inability or unwillingness to 
provide information within 3 business days of the request, the licensee 
shall:
    (A) Document this refusal or unwillingness in the licensee's record 
of the investigation; and
    (B) Obtain a confirmation of employment, educational enrollment and 
attendance, or other form of engagement claimed by the individual from 
at least one alternate source that has not been previously used.
    (v) When any licensee is seeking the information required for an 
access authorization decision under this section and has obtained a 
signed release from the subject individual authorizing the disclosure of 
such information, other licensees shall make available the personal or 
access authorization information requested regarding the denial or 
unfavorable termination of an access authorization.
    (vi) In conducting an employment history evaluation, the licensee 
may obtain information and documents by electronic means, including, but 
not limited to, telephone, facsimile, or email. Licensees shall make a 
record of the contents of the telephone call and

[[Page 498]]

shall retain that record, and any documents or electronic files obtained 
electronically, under paragraph (l) of this section.
    (6) Credit history evaluation. Licensees shall ensure the evaluation 
of the full credit history of any individual who is applying for access 
authorization relative to spent nuclear fuel in transit. A full credit 
history evaluation must include, but is not limited to, an inquiry to 
detect potential fraud or misuse of social security numbers or other 
financial identifiers, and a review and evaluation of all of the 
information that is provided by a national credit-reporting agency about 
the individual's credit history. For foreign nationals and U.S. citizens 
who have resided outside the U.S. and do not have established credit 
history that covers at least the most recent 7 years in the U.S., the 
licensee must document all attempts to obtain information regarding the 
individual's credit history and financial responsibility from some 
relevant entity located in that other country or countries.
    (7) Criminal history review. The licensee shall evaluate the entire 
criminal history record of an individual who is applying for access 
authorization to determine whether the individual has a record of 
criminal activity that may adversely impact his or her trustworthiness 
and reliability. The scope of the applicant's criminal history review 
must cover all residences of record for the 10-year period preceding the 
date of application for access authorization.
    (8) Character and reputation determination. Licensees shall 
ascertain the character and reputation of an individual who has applied 
for access authorization relative to spent nuclear fuel in transit by 
conducting reference checks. Reference checks may not be conducted with 
any person who is known to be a close member of the individual's family, 
including but not limited to, the individual's spouse, parents, 
siblings, or children, or any individual who resides in the individual's 
permanent household. The reference checks must focus on the individual's 
reputation for trustworthiness and reliability.
    (9) Corroboration. The licensee shall also, to the extent possible, 
obtain independent information to corroborate that provided by the 
individual (e.g., seek references not supplied by the individual).
    (e) Determination of trustworthiness and reliability; Documentation. 
(1) The licensee shall determine whether to grant, deny, unfavorably 
terminate, maintain, or administratively withdraw an individual's access 
authorization based on an evaluation of all of the information required 
by this section. The licensee may terminate or administratively withdraw 
an individual's access authorization based on information obtained after 
the background investigation has been completed and the individual 
granted access authorization.
    (2) The licensee may not permit any individual to have unescorted 
access or access authorization until all of the information required by 
this section has been evaluated by the reviewing official and the 
reviewing official has determined that the individual is trustworthy and 
reliable. The licensee may deny unescorted access or access 
authorization to any individual based on disqualifying information 
obtained at any time during the background investigation.
    (f) Protection of information. (1) Licensees shall protect 
background investigation information from unauthorized disclosure.
    (2) Licensees may not disclose the background investigation 
information collected and maintained to persons other than the subject 
individual, his/her representative, or to those who have a need to know 
in performing assigned duties related to the process of granting or 
denying unescorted access to spent nuclear fuel in transit. No 
individual authorized to have access to the information may re-
disseminate the information to any other individual who does not have a 
need to know.
    (3) The personal information obtained on an individual from a 
background investigation may be transferred to another licensee:
    (i) Upon the individual's written request to the licensee holding 
the data to re-disseminate the information contained in his/her file; 
and

[[Page 499]]

    (ii) The acquiring licensee verifies information such as name, date 
of birth, social security number, sex, and other applicable physical 
characteristics for identification.
    (4) The licensee shall make background investigation records 
obtained under this section available for examination by an authorized 
representative of the NRC to determine compliance with applicable laws 
and regulations.
    (5) The licensee shall retain all fingerprint and criminal history 
records received from the FBI, or a copy if the file has been 
transferred, on an individual (including data indicating no record) for 
5 years from the date the individual no longer requires unescorted 
access or access authorization relative to spent nuclear fuel in 
transit.
    (g) Grandfathering. For purposes of this section, licensees are not 
required to obtain the fingerprints of any person who has been 
fingerprinted, pursuant to an NRC order or regulation, for an FBI 
identification and criminal history records check within the 5 years of 
the effective date of this rule.
    (h) Reinvestigations. Licensees shall conduct fingerprinting and FBI 
identification and criminal history records check, a criminal history 
review, and credit history re-evaluation every 10 years for any 
individual who has unescorted access authorization to spent nuclear fuel 
in transit. The reinvestigations must be completed within 10 years of 
the date on which these elements were last completed and should address 
the 10 years following the previous investigation.
    (i) Self-reporting of legal actions. (1) Any individual who has 
applied for an access authorization or is maintaining an access 
authorization under this section shall promptly report to the reviewing 
official, his or her supervisor, or other management personnel 
designated in licensee procedures any legal action(s) taken by a law 
enforcement authority or court of law to which the individual has been 
subject that could result in incarceration or a court order or that 
requires a court appearance, including but not limited to an arrest, an 
indictment, the filing of charges, or a conviction, but excluding minor 
civil actions or misdemeanors such as parking violations or speeding 
tickets. The recipient of the report shall, if other than the reviewing 
official, promptly convey the report to the reviewing official. On the 
day that the report is received, the reviewing official shall evaluate 
the circumstances related to the reported legal action(s) and re-
determine the reported individual's access authorization status.
    (2) The licensee shall inform the individual of this obligation, in 
writing, prior to granting unescorted access or certifying access 
authorization.
    (j) Access authorization procedures. (1) Licensees shall develop, 
implement, and maintain written procedures for conducting background 
investigations for persons who are applying for unescorted access or 
access authorization for spent nuclear fuel in transit.
    (2) Licensees shall develop, implement, and maintain written 
procedures for updating background investigations for persons who are 
applying for reinstatement of unescorted access or access authorization.
    (3) Licensees shall develop, implement, and maintain written 
procedures to ensure that persons who have been denied unescorted access 
or access authorization are not allowed access to spent nuclear fuel in 
transit or information relative to spent nuclear fuel in transit.
    (4) Licensees shall develop, implement, and maintain written 
procedures for the notification of individuals who are denied unescorted 
access or access authorization for spent nuclear fuel in transit. The 
procedures shall include provisions for the review, at the request of 
the affected individual, of a denial or termination of unescorted access 
or access authorization. The procedure must contain a provision to 
ensure that the individual is informed of the grounds for the denial or 
termination of unescorted access or access authorization and allow the 
individual an opportunity to provide additional relevant information.
    (k) Right to correct and complete information. (1) Prior to any 
final adverse determination, licensees shall provide each individual 
subject to this section with the right to complete, correct, and explain 
information obtained as a

[[Page 500]]

result of the licensee's background investigation. Confirmation of 
receipt by the individual of this notification must be maintained by the 
licensee for a period of 1 year from the date of the notification.
    (2) If after reviewing their criminal history record an individual 
believes that it is incorrect or incomplete in any respect and wishes to 
change, correct, update, or explain anything in the record, the 
individual may initiate challenge procedures.
    (l) Records. (1) The licensee shall retain documentation regarding 
the trustworthiness and reliability of individual employees for 5 years 
from the date the individual no longer requires unescorted access or 
access authorization relative to spent nuclear fuel in transit.
    (2) The licensee shall retain a copy of the current access 
authorization program procedures as a record for 5 years after the 
procedure is no longer needed or until the Commission terminates the 
license, if the license is terminated before the end of the retention 
period. If any portion of the procedure is superseded, the licensee 
shall retain the superseded material for 5 years after the record is 
superseded.
    (3) The licensee shall retain the list of persons approved for 
unescorted access or access authorization and the list of those 
individuals that have been denied unescorted access or access 
authorization for 5 years after the list is superseded or replaced.
    (4) Licensees who have been authorized to add or manipulate data 
that is shared with licensees subject to this section shall ensure that 
data linked to the information about individuals who have applied for 
unescorted access or access authorization, which is specified in the 
licensee's access authorization program documents, is retained.
    (i) If the shared information used for determining individual's 
trustworthiness and reliability changes or new or additional information 
is developed about the individual, the licensees that acquire this 
information shall correct or augment the data and ensure it is shared 
with licensees subject to this section. If the changed, additional or 
developed information has implications for adversely affecting an 
individual's trustworthiness and reliability, licensees who discovered 
or obtained the new, additional or changed information, shall, on the 
day of discovery, inform the reviewing official of any licensee access 
authorization program under which the individual is maintaining his or 
her unescorted access or access authorization status of the updated 
information.
    (ii) The reviewing official shall evaluate the shared information 
and take appropriate actions, which may include denial or unfavorable 
termination of the individual's unescorted access or access 
authorization. If the notification of change or updated information 
cannot be made through usual methods, licensees shall take manual 
actions to ensure that the information is shared as soon as reasonably 
possible. Records maintained in any database(s) must be available for 
the NRC review.
    (5) If a licensee administratively withdraws an individual's 
unescorted access or access authorization status caused by a delay in 
completing any portion of the background investigation or for a licensee 
initiated evaluation, or re-evaluation that is not under the 
individual's control, the licensee shall record this administrative 
action to withdraw the individual's unescorted access or unescorted 
access authorization and shall share this information with other 
licensees subject to this section. However, licensees shall not document 
this administrative withdrawal as denial or unfavorable termination and 
shall not respond to a suitable inquiry conducted under the provisions 
of 10 CFR part 26, a background investigation conducted under the 
provisions of this section, or any other inquiry or investigation as 
denial nor unfavorable termination. Upon favorable completion of the 
background investigation element that caused the administrative 
withdrawal, the licensee shall immediately ensure that any matter that 
could link the individual to the administrative action is eliminated 
from the subject individual's access authorization or personnel record 
and other records, except if a review of the information obtained or 
developed causes the reviewing official to

[[Page 501]]

unfavorably terminate or deny the individual's unescorted access.

[78 FR 29553, May 20, 2013]

             Physical Protection Requirements at Fixed Sites



Sec. 73.40  Physical protection: General requirements at fixed sites.

    Each licensee shall provide physical protection at a fixed site, or 
contiguous sites where licensed activities are conducted, against 
radiological sabotage, or against theft of special nuclear material, or 
against both, in accordance with the applicable sections of this Part 
for each specific class of facility or material license. If applicable, 
the licensee shall establish and maintain physical security in 
accordance with security plans approved by the Nuclear Regulatory 
Commission.

[58 FR 13700, Mar. 15, 1993]



Sec. 73.45  Performance capabilities for fixed site physical 
protection systems.

    (a) To meet the general performance requirements of Sec. 73.20 a 
fixed site physical protection system shall include the performance 
capabilities described in paragraphs (b) through (g) of this section 
unless otherwise authorized by the Commission.
    (b) Prevent unauthorized access of persons, vehicles and materials 
into material access areas and vital areas. To achieve this capability 
the physical protection system shall:
    (1) Detect attempts to gain unauthorized access or introduce 
unauthorized material across material access or vital area boundaries by 
stealth or force using the following subsystems and subfunctions:
    (i) Barriers to channel persons and material to material access and 
vital area entry control points and to delay any unauthorized 
penetration attempts by persons or materials sufficient to assist 
detection and permit a response that will prevent the penetration; and
    (ii) Access detection subsystems and procedures to detect, assess 
and communicate any unauthorized penetration attempts by persons or 
materials at the time of the attempt so that the response can prevent 
the unauthorized access or penetration.
    (2) Detect attempts to gain unauthorized access or introduce 
unauthorized materials into material access areas or vital areas by 
deceit using the following subsystems and subfunctions:
    (i) Access authorization controls and procedures to provide current 
authorization schedules and entry criteria for both persons and 
materials; and
    (ii) Entry controls and procedures to verify the identity of persons 
and materials and assess such identity against current authorization 
schedules and entry criteria before permitting entry and to initiate 
response measures to deny unauthorized entries.
    (c) Permit only authorized activities and conditions within 
protected areas, material access areas, and vital areas. To achieve this 
capability the physical protection system shall:
    (1) Detect unauthorized activities or conditions within protected 
areas, material access areas and vital areas using the following 
subsystems and subfunctions:
    (i) Controls and procedures that establish current schedules of 
authorized activities and conditions in defined areas;
    (ii) Boundaries to define areas within which the authorized 
activities and conditions are permitted; and
    (iii) Detection and surveillance subsystems and procedures to 
discover and assess unauthorized activities and conditions and 
communicate them so that response can be such as to stop the activity or 
correct the conditions to satisfy the general performance objective and 
requirements of Sec. 73.20(a).
    (d) Permit only authorized placement and movement of strategic 
special nuclear material within material access areas. To achieve this 
capability the physical protection system shall:
    (1) Detect unauthorized placement and movement of strategic special 
nuclear material within the material access area using the following 
subsystems and subfunctions:
    (i) Controls and procedures to delineate authorized placement and 
control for strategic special nuclear material;
    (ii) Controls and procedures to establish current authorized 
placement and movement of all strategic special nuclear material within 
material access areas;

[[Page 502]]

    (iii) Controls and procedures to maintain knowledge of the identity, 
quantity, placement, and movement of all strategic special nuclear 
material within material access areas; and
    (iv) Detection and monitoring subsystems and procedures to discover 
and assess unauthorized placement and movement of strategic special 
nuclear material and communicate them so that response can be such as to 
return the strategic special nuclear material to authorized placement or 
control.
    (e) Permit removal of only authorized and confirmed forms and 
amounts of strategic special nuclear material from material access 
areas. To achieve this capability the physical protection system shall:
    (1) Detect attempts at unauthorized removal of strategic special 
nuclear material from material access areas by stealth or force using 
the following subsystems and subfunctions:
    (i) Barriers to channel persons and materials exiting a material 
access area to exit control points and to delay any unauthorized 
strategic special nuclear material removal attempts sufficient to assist 
detection and assessment and permit a response that will prevent the 
removal; and satisfy the general performance objective and requirements 
of Sec. 73.20(a); and
    (ii) Detection subsystems and procedures to detect, assess and 
communicate any attempts at unauthorized removal of strategic special 
nuclear material so that response to the attempt can be such as to 
prevent the removal and satisfy the general performance objective and 
requirements of Sec. 73.20(a).
    (2) Confirm the identity and quantity of strategic special nuclear 
material presented for removal from a material access area and detect 
attempts at unauthorized removal of strategic special nuclear material 
from material access areas by deceit using the following subsystems and 
subfunctions:
    (i) Authorization controls and procedures to provide current 
schedules for authorized removal of strategic special nuclear material 
which specify the authorized properties and quantities of material to be 
removed, the persons authorized to remove the material, and the 
authorized time schedule;
    (ii) Removal controls and procedures to identify and confirm the 
properties and quantities of material being removed and verify the 
identity of the persons making the removal and time of removal and 
assess these against the current authorized removal schedule before 
permitting removal; and
    (iii) Communications subsystems and procedures to provide for 
notification of an attempted unauthorized or unconfirmed removal so that 
response can be such as to prevent the removal and satisfy the general 
performance objective and requirements of Sec. 73.20(a).
    (f) Provide for authorized access and assure detection of and 
response to unauthorized penetrations of the protected area to satisfy 
the general performance objective and requirements of Sec. 73.20(a). To 
achieve this capability the physical protection system shall:
    (1) Detect attempts to gain unauthorized access or introduce 
unauthorized persons, vehicles, or materials into the protected area by 
stealth or force using the following subsystems and subfunctions:
    (i) Barriers to channel persons, vehicles, and materials to 
protected area entry control points; and to delay any unauthorized 
penetration attempts or the introduction of unauthorized vehicles or 
materials sufficient to assist detection and assessment and permit a 
response that will prevent the penetration or prevent such penetration 
and satisfy the general performance objective and requirements of Sec. 
73.20(a); and
    (ii) Access detection subsystems and procedures to detect, assess 
and communicate any unauthorized access or penetrations or such attempts 
by persons, vehicles, or materials at the time of the act or the attempt 
so that the response can be such as to prevent the unauthorized access 
or penetration, and satisfy the general performance objective and 
requirements of Sec. 73.20(a).
    (2) Detect attempts to gain unauthorized access or introduce 
unauthorized persons, vehicles, or materials into the protected area by 
deceit using the following subsystems and subfunctions:
    (i) Access authorization controls and procedures to provide current 
authorization schedules and entry criteria for persons, vehicles, and 
materials; and

[[Page 503]]

    (ii) Entry controls and procedures to verify the identity of 
persons, materials and vehicles and assess such identity against current 
authorization schedules before permitting entry and to initiate response 
measures to deny unauthorized access.
    (g) Response. Each physical protection program shall provide a 
response capability to assure that the five capabilities described in 
paragraphs (b) through (f) of this section are achieved and that 
adversary forces will be engaged and impeded until offsite assistance 
forces arrive. To achieve this capability a licensee shall:
    (1) Establish a security organization to:
    (i) Provide trained and qualified personnel to carry out assigned 
duties and responsibilities; and
    (ii) Provide for routine security operations and planned and 
predetermined response to emergencies and safeguards contingencies.
    (2) Establish a predetermined plan to respond to safeguards 
contingency events.
    (3) Provide equipment for the security organization and facility 
design features to:
    (i) Provide for rapid assessment of safeguards contingencies;
    (ii) Provide for response by assigned security organization 
personnel which is sufficiently rapid and effective to achieve the 
predetermined objective of the response; and
    (iii) Provide protection for the assessment and response personnel 
so that they can complete their assigned duties.
    (4) Provide communications networks to:
    (i) Transmit rapid and accurate security information among onsite 
forces for routine security operation, assessment of a contingency, and 
response to a contingency; and
    (ii) Transmit rapid and accurate detection and assessment 
information to offsite assistance forces.
    (5) Assure that a single adversary action cannot destroy the 
capability of the security organization to notify offsite response 
forces of the need for assistance.

[44 FR 68193, Nov. 28, 1979]



Sec. 73.46  Fixed site physical protection systems, subsystems,
components, and procedures.

    (a) A licensee physical protection system established pursuant to 
the general performance objective and requirements of Sec. 73.20(a) and 
the performance capability requirements of Sec. 73.45 shall include, 
but are not necessarily limited to, the measures specified in paragraphs 
(b) through (h) of this section. The Commission may require, depending 
on individual facility and site conditions, alternate or additional 
measures deemed necessary to meet the general performance objective and 
requirements of Sec. 73.20. The Commission also may authorize 
protection measures other than those required by this section if, in its 
opinion, the overall level of performance meets the general performance 
objective and requirements of Sec. 73.20 and the performance capability 
requirements of Sec. 73.45.
    (b) Security organization. (1) The licensee shall establish a 
security organization, including guards. If a contract guard force is 
utilized for site security, the licensee's written agreement with the 
contractor will clearly show that (i) the licensee is responsible to the 
Commission for maintaining safeguards in accordance with Commission 
regulations and the licensee's security plan, (ii) the NRC may inspect, 
copy, and take away copies of all reports and documents required to be 
kept by Commission regulations, orders, or applicable license conditions 
whether such reports and documents are kept by the licensee or the 
contractor, (iii) the requirement, in Sec. 73.46(b)(4) of this section 
that the licensee demonstrate the ability of physical security personnel 
to perform their assigned duties and responsibilities, include 
demonstration of the ability of the contractor's physical security 
personnel to perform their assigned duties and responsibilities in 
carrying out the provisions of the Security Plan and these regulations, 
and (iv) the contractor will not assign any personnel to the site who 
have not first been made aware of these responsibilities.
    (2) The licensee shall have onsite at all times at least one full 
time member

[[Page 504]]

of the security organization with authority to direct the physical 
protection activities of the security organization.
    (3) The licensee shall have a management system to provide for the 
development, revision, implementation, and enforcement of security 
procedures. The system shall include:
    (i) Written security procedures which document the structure of the 
security organization and which detail the duties of the Tactical 
Response Team, guards, watchmen, and other individuals responsible for 
security. The licensee shall retain a copy of the current procedures as 
a record until the Commission terminates the license for which these 
procedures were developed and, if any portion of these procedures is 
superseded, retain the superseded material for three years after each 
change; and
    (ii) Provision for written approval of such procedures and any 
revisions thereto by the individual with overall responsibility for the 
security function.
    (4) The licensee may not permit an individual to act as a Tactical 
Response Team member, armed response person, guard, or other member of 
the security organization unless the individual has been trained, 
equipped, and qualified to perform each assigned security duty in 
accordance with Appendix B of this part, ``General Criteria for Security 
Personnel.'' In addition, Tactical Response Team members, armed response 
personnel, and guards shall be trained, equipped, and qualified for use 
of their assigned weapons in accordance with paragraphs (b)(6) and 
(b)(7) of this section. Tactical Response Team members, armed response 
personnel, and guards shall also be trained and qualified in accordance 
with either paragraphs (b)(10) and (b)(11) or paragraph (b)(12) of this 
section. Upon the request of an authorized representative of the 
Commission, the licensee shall demonstrate the ability of the physical 
security personnel, whether licensee or contractor employees, to carry 
out their assigned duties and responsibilities. Each Tactical Response 
Team member, armed response person, and guard, whether a licensee or 
contractor employee, shall requalify in accordance with Appendix B of 
this part. Tactical Response Team members, armed response personnel, and 
guards shall also requalify in accordance with paragraph (b)(7) of this 
section at least once every 12 months. The licensee shall document the 
results of the qualification and requalification. The licensee shall 
retain the documentation of each qualification and requalification as a 
record for 3 years after each qualification and requalification.
    (5) Within any given period of time, a member of the security 
organization may not be assigned to, or have direct operational control 
over, more than one of the redundant elements of a physical protection 
subsystem if such assignment or control could result in the loss of 
effectiveness of the subsystem.
    (6) Each guard shall be armed with a handgun, as described in 
appendix B of this part. Each Tactical Response Team member shall be 
armed with a 9mm semiautomatic pistol. All but one member of the 
Tactical Response Team shall be armed additionally with either a shotgun 
or semiautomatic rifle, as described in appendix B of this part. The 
remaining member of the Tactical Response Team shall carry, as an 
individually assigned weapon, a rifle of no less caliber than .30 inches 
or 7.62mm.
    (7) In addition to the weapons qualification and requalification 
criteria of appendix B of this part, Tactical Response Team members, 
armed response personnel, and guards shall qualify and requalify, at 
least every 12 months, for day and night firing with assigned weapons in 
accordance with Appendix H of this part. Tactical Response Team members, 
armed response personnel, and guards shall be permitted to practice fire 
prior to qualification and requalification but shall be given only one 
opportunity to fire for record on the same calendar day. If a Tactical 
Response Team member, armed response person, or guard fails to qualify 
or requalify, the licensee shall remove the individual from security 
duties which require the use of firearms and retrain the individual 
prior to any subsequent attempt to qualify or requalify. If an 
individual fails to qualify or requalify on two successive attempts, he 
or she shall be required to

[[Page 505]]

receive additional training and successfully fire two consecutive 
qualifying scores prior to being reassigned to armed security duties.
    (i) In addition, Tactical Response Team members, armed response 
personnel, and guards shall be prepared to demonstrate day and night 
firing qualification with their assigned weapons at any time upon 
request by an authorized representative of the NRC.
    (ii) The licensee or the licensee's agent shall document the results 
of weapons qualification and requalification for day and night firing. 
The licensee shall retain the documentation of each qualification and 
requalification as a record for 3 years after each qualification and 
requalification.
    (8) In addition to the training requirements contained in appendix B 
of this part, Tactical Response Team members shall successfully complete 
training in response tactics. The licensee shall document the completion 
of training. The licensee shall retain the documentation of training as 
a record for three years after training is completed.
    (9) The licensee shall conduct Tactical Response Team and guard 
exercises to demonstrate the overall security system effectiveness and 
the ability of the security force to perform response and contingency 
plan responsibilities and to demonstrate individual skills in assigned 
team duties. During the first 12-month period following the date 
specified in paragraph (i)(2)(ii) of this section, an exercise must be 
carried out at least every three months for each shift, half of which 
are to be force-on-force. Subsequently, during each 12-month period 
commencing on the anniversary of the date specified in paragraph 
(i)(2)(ii) of this section, an exercise must be carried out at least 
every four months for each shift, one third of which are to be force-on-
force. The licensee shall use these exercises to demonstrate its 
capability to respond to attempts to steal strategic special nuclear 
material. During each of the 12-month periods, the NRC shall observe one 
of the force-on-force exercises which demonstrates overall security 
system performance. The licensee shall notify the NRC of the scheduled 
exercise 60 days prior to that exercise. The licensee shall document the 
results of all exercises. The licensee shall retain the documentation of 
each exercise as a record for three years after each exercise is 
completed.
    (10) In addition to the medical examinations and physical fitness 
requirements of paragraph I.C of Appendix B of this part, each Tactical 
Response Team member, armed response person, and guard, except as 
provided in paragraph (b)(10)(v) of this section, shall participate in a 
physical fitness training program on a continuing basis.
    (i) The elements of the physical fitness training program must 
include, but not necessarily be limited to, the following:
    (A) Training sessions of sufficient frequency, duration, and 
intensity to be of aerobic benefit, e.g., normally a frequency of three 
times per week, maintaining an intensity of approximately 75 percent of 
maximum heart rate for 20 minutes;
    (B) Activities that use large muscle groups, that can be maintained 
continuously, and that are rhythmical and aerobic in nature, e.g., 
running, bicycling, rowing, swimming, or cross-country skiing; and
    (C) Musculoskeletal training exercises that develop strength, 
flexibility, and endurance in the major muscle groups, e.g., legs, arms, 
and shoulders.
    (ii) The licensee shall assess Tactical Response Team members, armed 
response personnel, and guards for general fitness once every 4 months 
to determine the effectiveness of the continuing physical fitness 
training program. Assessments must include a recent health history, 
measures of cardiovascular fitness, percent of body fat, flexibility, 
muscular strength, and endurance. Individual exercise programs must be 
modified to be consistent with the needs of each participating Tactical 
Response Team member, armed response person, and guard and consistent 
with the environments in which they must be prepared to perform their 
duties. Individuals who exceed 4 months without being assessed for 
general fitness due to excused time off from work must be assessed 
within 15 calendar days of returning to duty as a

[[Page 506]]

Tactical Response Team member, armed response person, or guard.
    (iii) Within 30 days prior to participation in the physical fitness 
training program, the licensee shall give Tactical Response Team 
members, armed response personnel, and guards a medical examination 
including a determination and written certification by a licensed 
physician that there are no medical contraindications, as disclosed by 
the medical examination, to participation in the physical fitness 
training program.
    (iv) Licensees may temporarily waive an individual's participation 
in the physical fitness training program on the advice of the licensee's 
examining physician, during which time the individual may not be 
assigned duties as a Tactical Response Team member.
    (v) Guards whose duties are to staff the central or secondary alarm 
station and those who control exit or entry portals are exempt from the 
physical fitness training program specified in paragraph (b)(10) of this 
section, provided that they are not assigned temporary response guard 
duties.
    (11) In addition to the physical fitness demonstration contained in 
paragraph I.C of Appendix B of this part, Tactical Response Team 
members, armed response personnel, and guards shall meet or exceed the 
requirements in paragraphs (b)(11)(i) through (b)(11)(v) of this 
section, except as provided in paragraph (b)(11)(vi) of this section, 
initially and at least once every 12 months thereafter.
    (i) For Tactical Response Team members the criteria are a 1-mile run 
in 8 minutes and 30 seconds or less and a 40-yard dash starting from a 
prone position in 8 seconds or less. For armed response personnel and 
guards that are not members of the Tactical Response Team the criteria 
are a one-half mile run in 4 minutes and 40 seconds or less and a 40-
yard dash starting from a prone position in 8.5 seconds or less. The 
test may be taken in ordinary athletic attire under the supervision of 
licensee designated personnel. The licensee shall retain a record of 
each individual's performance for 3 years.
    (ii) Incumbent Tactical Response Team members, armed response 
personnel, and guards shall meet or exceed the qualification criteria 
within 12 months of NRC approval of the licensee's revised Fixed Site 
Physical Protection Plan. New employees hired after the approval date 
shall meet or exceed the qualification criteria prior to assignment as a 
Tactical Response Team member, armed response person, or guard.
    (iii) Tactical Response Team members, armed response personnel, and 
guards shall be given a medical examination including a determination 
and written certification by a licensed physician that there are no 
medical contraindications, as disclosed by the medical examination, to 
participation in the physical fitness performance testing. The medical 
examination must be given within 30 days prior to the first 
administration of the physical fitness performance test, and on an 
annual basis thereafter.
    (iv) The licensee shall place Tactical Response Team members, armed 
response persons, and guards, who do not meet or exceed the 
qualification criteria, in a monitored remedial physical fitness 
training program and relieve them of security duties until they 
satisfactorily meet or exceed the qualification criteria.
    (v) Licensees may temporarily waive the annual performance testing 
for an individual on the advice of the licensee's examining physician, 
during which time the individual may not be assigned duties as a 
Tactical Response Team member.
    (vi) Guards whose duties are to staff the central or secondary alarm 
station and those who control exit or entry portals are exempt from the 
annual performance testing specified in paragraph (b)(11) of this 
section, provided that they are not assigned temporary response guard 
duties.
    (12) The licensee may elect to comply with the requirements of this 
paragraph instead of the requirements of paragraphs (b)(10) and (b)(11) 
of this section. In addition to the physical fitness qualifications of 
paragraph I.C of Appendix B of this part, each licensee subject to the 
requirements of this section shall develop and submit to the NRC for 
approval site specific, content-based, physical fitness performance 
tests which will--when administered to

[[Page 507]]

each Tactical Response Team member, armed response person, or guard--
duplicate the response duties these individuals may need to perform 
during a strenuous tactical engagement.
    (i) The test must be administered to each Tactical Response Team 
member, armed response person, and guard once every 3 months. The test 
must specifically address the physical capabilities needed by armed 
response personnel during a strenuous tactical engagement at the 
licensed facility. Individuals who exceed 3 months without having been 
administered the test due to excused time off from work must be tested 
within 15 calendar days of returning to duty as a Tactical Response Team 
member, armed response person, or guard.
    (ii) Within 30 days before the first administration of the physical 
fitness performance test, and on an annual basis thereafter, Tactical 
Response Team members, armed response personnel, and guards shall be 
given a medical examination including a determination and written 
certification by a licensed physician that there are no medical 
contraindications, as disclosed by the medical examination, to 
participation in the physical fitness performance test.
    (iii) Guards whose duties are to staff the central or secondary 
alarm station and those who control exit or entry portals are exempt 
from the performance test specified in paragraph (b)(12) of this 
section, provided that they are not assigned temporary response guard 
duties.
    (c) Physical barrier subsystems. (1) vital equipment must be located 
only within a vital area, and strategic special nuclear material must be 
stored or processed only in a material access area. Both vital areas and 
material access areas must be located within a protected area so that 
access to vital equipment and to strategic special nuclear material 
requires passage through at least three physical barriers. The perimeter 
of the protected area must be provided with two separated physical 
barriers with an intrusion detection system placed between the two. The 
inner barrier must be positioned and constructed to enhance assessment 
of penetration attempts and to delay attempts at unauthorized exit from 
the protected area. The perimeter of the protected area must also 
incorporate features and structures that prevent forcible vehicle entry. 
More than one vital area or material access area may be located within a 
single protected area.
    (2) The physical barriers at the perimeter of the protected area 
shall be separated from any other barrier designated as a physical 
barrier for a vital area or material access area within the protected 
area.
    (3) Isolation zones shall be maintained in outdoor areas adjacent to 
the physical barrier at the perimeter of the protected area and shall be 
large enough to permit observation of the activities of people on either 
side of that barrier in the event of its penetration. If parking 
facilities are provided for employees or visitors, they shall be located 
outside the isolation zone and exterior to the protected area.
    (4) Isolation zones and all exterior areas within the protected area 
shall be provided with illumination sufficient for the monitoring and 
observation requirements of paragraphs (c)(3), (e)(8), (h)(4) and (h)(6) 
of this section, but not less than 0.2 footcandle measured horizontally 
at ground level.
    (5) Strategic special nuclear material, other than alloys, fuel 
elements or fuel assemblies, shall:
    (i) Be stored in a vault when not undergoing processing if the 
material can be used directly in the manufacture of a nuclear explosive 
device. Vaults used to protect such material shall be capable of 
preventing entry to stored SSNM by a single action in a forced entry 
attempt, except as such single action would both destroy the barrier and 
render contained SSNM incapable of being removed, and shall provide 
sufficient delay to prevent removal of stored SSNM prior to arrival of 
response personnel capable of neutralizing the design basis threat 
stated in Sec. 73.1.
    (ii) Be stored in tamper-indicating containers;
    (iii) Be processed only in material access areas constructed with 
barriers that provide significant delay to penetration; and

[[Page 508]]

    (iv) Be kept in locked compartments or locked process equipment 
while undergoing processing except when personally attended.
    (6) Enriched uranium scrap (enriched to 20% or greater) in the form 
of small pieces, cuttings, chips, solutions or in other forms which 
result from a manufacturing process, contained in 30 gallon or larger 
containers with a uranium-235 content of less than 0.25 grams per liter, 
may be stored within a locked and separately fenced area within a larger 
protected area provided that the storage area fence is no closer than 25 
feet to the perimeter of the protected area. The storage area when 
unoccupied shall be protected by a guard or watchman who shall patrol at 
intervals not exceeding 4 hours, or by intrusion alarms.
    (d) Access control subsystems and procedures. (1) A numbered picture 
badge identification subsystem shall be used for all individuals who are 
authorized access to protected areas without escort. An individual not 
employed by the licensee but who requires frequent and extended access 
to protected, material access, or vital areas may be authorized access 
to such areas without escort provided that he receives a picture badge 
upon entrance into the protected area and returns the badge upon exit 
from the protected area, and that the badge indicates, (i) Non-
employee--no escort required; (ii) areas to which access is authorized 
and (iii) the period for which access has been authorized. Badges shall 
be displayed by all individuals while inside the protected areas.
    (2) Unescorted access to vital areas, material access areas and 
controlled access areas shall be limited to individuals who are 
authorized access to the material and equipment in such areas, and who 
require such access to perform their duties. Access to material access 
areas shall include at least two individuals. Authorization for such 
individuals shall be indicated by the issuance of specially coded 
numbered badges indicating vital areas, material access areas, and 
controlled access areas to which access is authorized. No activities 
other than those which require access to strategic special nuclear 
material or to equipment used in the processing, use, or storage of 
strategic special nuclear material, or necessary maintenance, shall be 
permitted within a material access area.
    (3) The licensee shall establish and follow written procedures that 
will permit access control personnel to identify those vehicles that are 
authorized and those materials that are not authorized entry to 
protected, material access, and vital areas. The licensee shall retain a 
copy of the current procedures as a record until the Commission 
terminates each license for which the procedures were developed and, if 
any portion of the procedures is superseded, retain the superseded 
material for three years after each change.
    (4)(i) The licensee shall control all points of personnel and 
vehicle access into a protected area. Identification and search of all 
individuals for firearms, explosives, and incendiary devices must be 
made and authorization must be checked at these points except for 
Federal, State, and local law enforcement personnel on official duty and 
United States Department of Energy couriers engaged in the transport of 
special nuclear material. The search function for detection of firearms, 
explosives, and incendiary devices must be accomplished through the use 
of detection equipment capable of detecting both firearms and 
explosives. The individual responsible for the last access control 
function (controlling admission to the protected area) shall be isolated 
within a structure with bullet resisting walls, doors, ceiling, floor, 
and windows.
    (ii) When the licensee has cause to suspect that an individual is 
attempting to introduce firearms, explosives, or incendiary devices into 
a protected area, the licensee shall conduct a physical pat-down search 
of that individual. Whenever firearms or explosives detection equipment 
at a portal is out of service or not operating satisfactorily, the 
licensee shall conduct a physical pat-down search of all persons who 
would otherwise have been subject to search using the equipment.
    (5) At the point of personnel and vehicle access into a protected 
area, all hand-carried packages except those carried by individuals 
exempted from personal search under the provisions of

[[Page 509]]

paragraph (d)(4)(i) of this part must be searched for firearms, 
explosives, and incendiary devices.
    (6) All packages and material for delivery into a protected area 
must be checked for proper identification and authorization and searched 
for firearms, explosives, and incendiary devices prior to admittance 
into the protected area, except those Commission-approved delivery and 
inspection activities specifically designated by the licensee to be 
carried out within material access, vital, or protected areas for 
reasons of safety, security, or operational necessity.
    (7) All vehicles, except United States Department of Energy vehicles 
engaged in transporting special nuclear material and emergency vehicles 
under emergency conditions, shall be searched for firearms, explosives, 
and incendiary devices prior to entry into the protected area. Vehicle 
areas to be searched shall include the cab, engine compartment, 
undercarriage, and cargo area.
    (8) All vehicles, except designated licensee vehicles, requiring 
entry into the protected area shall be escorted by a member of the 
security organization while within the protected area, and to the extent 
practicable shall be off-loaded in an area that is not adjacent to a 
vital area. Designated licensee vehicles shall be limited in their use 
to onsite plant functions and shall remain in the protected area except 
for operational, maintenance, security and emergency purposes. The 
licensee shall exercise positive control over all such designated 
vehicles to assure that they are used only by authorized persons and for 
authorized purposes.
    (9) The licensee shall control all points of personnel and vehicle 
access to material access areas, vital areas, and controlled access 
areas. At least two armed guards trained in accordance with the 
provisions contained in paragraph (b)(7) of this section and appendix B 
of this part shall be posted at each material access area control point 
whenever in use. Identification and authorization of personnel and 
vehicles must be verified at the material access area control point. 
Prior to entry into a material access area, packages must be searched 
for firearms, explosives, and incendiary devices. All vehicles, 
materials and packages, including trash, wastes, tools, and equipment 
exiting from a material access area must be searched for concealed 
strategic special nuclear material by a team of at least two individuals 
who are not authorized access to that material access area. Each 
individual exiting a material access area shall undergo at least two 
separate searches for concealed strategic special nuclear material. For 
individuals exiting an area that contains only alloyed or encapsulated 
strategic special nuclear material, the second search may be conducted 
in a random manner.
    (10) Before exiting from a material access area, containers of 
contaminated wastes must be drum scanned and tamper sealed by at least 
two individuals, working and recording their findings as a team, who do 
not have access to material processing and storage areas. The licensee 
shall retain the records of these findings for three years after the 
record is made.
    (11) Strategic special nuclear material being prepared for shipment 
offsite, including product, samples and scrap, shall be packed and 
placed in sealed containers in the presence of at least two individuals 
working as a team who shall verify and certify the content of each 
shipping container through the witnessing of gross weight measurements 
and nondestructive assay, and through the inspection of tamper seal 
integrity and associated seal records.
    (12) Areas used for preparing strategic special nuclear material for 
shipment and areas used for packaging and screening trash and wastes 
shall be controlled access areas and shall be separated from processing 
and storage areas.
    (13) Individuals not permitted by the licensee to enter protected 
areas without escort must be escorted by a watchman or other individual 
designated by the licensee while in a protected area and must be badged 
to indicate that an escort is required. In addition, the individual 
shall be required to register his or her name, date, time,

[[Page 510]]

purpose of visit and employment affiliation, citizenship, and name of 
the individual to be visited in a log. The licensee shall retain each 
log as a record for three years after the last entry is made in the log.
    (14) All keys, locks, combinations and related equipment used to 
control access to protected, material access, vital, and controlled 
access areas shall be controlled to reduce the probability of 
compromise. Whenever there is evidence that a key, lock, combination, or 
related equipment may have been compromised it shall be changed. Upon 
termination of employment of any employee, keys, locks, combinations, 
and related equipment to which that employee had access, shall be 
changed.
    (15) The licensee may not announce or otherwise communicate to its 
employees or site contractors the arrival or presence of an NRC 
safeguards inspector unless specifically requested to do so by the NRC 
safeguards inspector.
    (e) Detection, surveillance and alarm subsystems and procedures. (1) 
The licensee shall provide an intrusion alarm subsystem with a 
capability to detect penetration through the isolation zone and to 
permit response action.
    (2) All emergency exits in each protected, material access, and 
vital area shall be locked to prevent entry from the outside and alarmed 
to provide local visible and audible alarm annunciation.
    (3) All unoccupied vital areas and material access areas shall be 
locked and protected by an intrusion alarm subsystem which will alarm 
upon the entry of a person anywhere into the area, upon exit from the 
area, and upon movement of an individual within the area, except that 
for process material access areas only the location of the strategic 
special nuclear material within the area is required to be so alarmed. 
Vaults and process areas that contain strategic special nuclear material 
that has not been alloyed or encapsulated shall also be under the 
surveillance of closed circuit television that is monitored in both 
alarm stations. Additionally, means shall be employed which require that 
an individual other than an alarm station operator be present at or have 
knowledge of access to such unoccupied vaults or process areas.
    (4) All manned access control points in the protected area barrier, 
all security patrols and guard stations within the protected area, and 
both alarm stations shall be provided with duress alarms.
    (5) All alarms required pursuant to this section shall annunciate in 
a continuously manned central alarm station located within the protected 
area and in at least one other independent continuously manned onsite 
station not necessarily within the protected area, so that a single act 
cannot remove the capability of calling for assistance or responding to 
an alarm. The alarm stations shall be controlled access areas and their 
walls, doors, ceiling, floor, and windows shall be bullet-resisting. The 
central alarm station shall be located within a building so that the 
interior of the central alarm station is not visible from the perimeter 
of the protected area. This station may not contain any operational 
activities that would interfere with the execution of the alarm response 
function.
    (6) All alarms required by this section shall remain operable from 
independent power sources in the event of the loss of normal power. 
Switchover to standby power shall be automatic and shall not cause false 
alarms on annunciator modules.
    (7) All alarm devices including transmission lines to annunciators 
shall be tamper indicating and self-checking e.g., an automatic 
indication shall be provided when a failure of the alarm system or a 
component occurs, when there is an attempt to compromise the system, or 
when the system is on standby power. The annunciation of an alarm at the 
alarm stations shall indicate the type of alarm (e.g., intrusion alarm, 
emergency exit alarm, etc.) and location. The status of all alarms and 
alarm zones shall be indicated in the alarm stations.
    (8) All exterior areas within the protected area shall be monitored 
or periodically checked to detect the presence of unauthorized persons, 
vehicles, materials, or unauthorized activities.
    (9) Methods to observe individuals within material access areas to 
assure

[[Page 511]]

that strategic special nuclear material is not moved to unauthorized 
locations or in an unauthorized manner shall be provided and used on a 
continuing basis.
    (f) Communication subsystems. (1) Each guard, watchman, or armed 
response individual on duty shall be capable of maintaining continuous 
communication with an individual in each continuously manned alarm 
station required by paragraph (e)(5) of this section, who shall be 
capable of calling for assistance from other guards, watchmen, and armed 
response personnel and from law enforcement authorities.
    (2) Each alarm station required by paragraph (e)(5) of this section 
shall have both conventional telephone service and radio or microwave 
transmitted two-way voice communication, either directly or through an 
intermediary, for the capability of communication with the law 
enforcement authorities.
    (3) Non-portable communications equipment controlled by the licensee 
and required by this section shall remain operable from independent 
power sources in the event of the loss of normal power.
    (g) Test and maintenance programs. The licensee shall have a test 
and maintenance program for intrusion alarms, emergency exit alarms, 
communications equipment, physical barriers, and other physical 
protection related devices and equipment used pursuant to this section 
that shall provide for the following:
    (1) Tests and inspections during the installation and construction 
of physical protection related subsystems and components to assure that 
they comply with their respective design criteria and performance 
specifications.
    (2) Preoperational tests and inspections of physical protection 
related subsystems and components to demonstrate their effectiveness and 
availability with respect to their respective design criteria and 
performance specifications.
    (3) Operational tests and inspections of physical protection related 
subsystems and components to assure their maintenance in an operable and 
effective condition, including:
    (i) Testing of each intrusion alarm at the beginning and end of any 
period that it is used. If the period of continuous use is longer than 
seven days, the intrusion alarm shall also be tested at least once every 
seven days.
    (ii) Testing of communications equipment required for communications 
onsite, including duress alarms, for performance not less frequently 
than once at the beginning of each security personnel work shift. 
Communications equipment required for communications offsite shall be 
tested for performance not less than once a day.
    (4) Preventive maintenance programs shall be established for 
physical protection related subsystems and components to assure their 
continued maintenance in an operable and effective condition.
    (5) All physical protection related subsystems and components shall 
be maintained in operable condition. The licensee shall develop and 
employ corrective action procedures and compensatory measures to assure 
that the effectiveness of the physical protection system is not reduced 
by failure or other contingencies affecting the operation of the 
security related equipment or structures. Repairs and maintenance shall 
be performed by at least two individuals working as a team who have been 
trained in the operation and performance of the equipment. The security 
organization shall be notified before and after service is performed and 
shall conduct performance verification tests after the service has been 
completed.
    (6) The security program must be reviewed at least every 12 months 
by individuals independent of both security program management and 
personnel who have direct responsibility for implementation of the 
security program. The security program review must include an audit of 
security procedures and practices, an evaluation of the effectiveness of 
the physical protection system, an audit of the physical protection 
system testing and maintenance program, and an audit of commitments 
established for response by local law enforcement authorities. The 
results and recommendations of the security program review, and any 
actions taken, must be documented in a report to the licensee's plant 
manager and to corporate management at least one

[[Page 512]]

level higher than that having responsibility for the day-to-day plant 
operations. These reports must be maintained in an auditable form, 
available for inspection for a period of 3 years.
    (h) Contingency and response plans and procedures. (1) The licensee 
shall establish, maintain, and follow an NRC-approved safeguards 
contingency plan for responding to threats, thefts, and radiological 
sabotage related to the strategic special nuclear material and nuclear 
facilities subject to the provisions of this section. Safeguards 
contingency plans must be in accordance with the criteria in appendix C 
to this part, ``Licensee Safeguards Contingency Plans.'' Contingency 
plans must include, but not limited to, the response requirements listed 
in paragraphs (h)(2) through (h)(5) of this section. The licensee shall 
retain the current safeguards contingency plan as a record until the 
Commission terminates the license and, if any portion of the plan is 
superseded, retain that superseded portion for 3 years after the 
effective date of change.
    (2) The licensee shall establish and document response arrangements 
that have been made with local law enforcement authorities. The licensee 
shall retain documentation of the current arrangements as a record until 
the Commission terminates each license requiring the arrangements and, 
if any arrangement is superseded, retain the superseded material for 
three years after each change.
    (3) A Tactical Response Team consisting of a minimum of five (5) 
members must be available at the facility to fulfill assessment and 
response requirements. In addition, a force of guards or armed response 
personnel also must be available to provide assistance as necessary. The 
size and availability of the additional force must be determined on the 
basis of site-specific considerations that could affect the ability of 
the total onsite response force to engage and impede the adversary force 
until offsite assistance arrives. The rationale for the total number and 
availabiliy of onsite armed response personnel must be included in the 
physical protection plans submitted to the Commission for approval.
    (4) Upon detection of abnormal presence or activity of persons or 
vehicles within an isolation zone, a protected area, a material access 
area, or a vital area, or upon evidence or indication of intrusion into 
a protected area, a material access area, or a vital area, the licensee 
security organization shall:
    (i) Determine whether or not a threat exists,
    (ii) Assess the extent of the threat, if any,
    (iii) Take immediate concurrent measures to neutralize the threat 
by:
    (A) Requiring responding guards or other armed response personnel to 
interpose themselves between vital areas and material access areas and 
any adversary attempting entry for purposes of radiological sabotage or 
theft of strategic special nuclear material and to intercept any person 
exiting with special nuclear material, and
    (B) Informing local law enforcement agencies of the threat and 
requesting assistance.
    (5) The licensee shall instruct every guard and all armed response 
personnel to prevent or impede acts of radiological sabotage or theft of 
strategic special nuclear material by using force sufficient to counter 
the force directed at him including the use of deadly force when the 
guard or other armed response person has a reasonable belief that it is 
necessary in self-defense or in the defense of others.
    (6) To facilitate initial response to detection of penetration of 
the protected area and assessment of the existence of a threat, a 
capability of observing the isolation zones and the physical barrier at 
the perimeter of the protected area shall be provided, preferably by 
means of closed circuit television or by other suitable means which 
limit exposure of responding personnel to possible attack.
    (7) Alarms occurring within unoccupied vaults and unoccupied 
material access areas containing unalloyed or unencapsulated strategic 
special nuclear material shall be assessed by at least two security 
personnel using closed circuit television (CCTV) or other remote means.
    (8) Alarms occurring within unoccupied material access areas that 
contain only alloyed or encapsulated strategic

[[Page 513]]

special nuclear material shall be assessed as in paragraph (h)(7) of 
this section or by at least two security personnel who shall undergo a 
search before exiting the material access area.
    (i) Implementation schedule for revisions to physical protection 
plans. (1) By November 28, 1994, each licensee shall submit a revised 
Fixed Site Physical Protection Plan to the NRC for approval. The revised 
plan must describe how the licensee will comply with the requirements of 
paragraphs (b)(10) and (b)(11) of this section or the requirements of 
(b)(12) of this section. Revised plans must be mailed to the Director, 
Division of Fuel Cycle Safety, Safeguards, and Environmental Review, 
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555.
    (2) Each licensee shall implement the approved plan pursuant to 
paragraphs (b)(10) and (b)(11) of this section or (b)(12) of this 
section within 1 year after NRC approval of the revised Fixed Site 
Physical Protection Plan.

[44 FR 68194, Nov. 28, 1979, as amended at 53 FR 19258, May 27, 1988; 53 
FR 23383, June 22, 1988; 53 FR 45452, Nov. 10, 1988; 57 FR 33430, July 
29, 1992; 58 FR 29522, May 21, 1993; 58 FR 45784, Aug. 31, 1993; 59 FR 
38348, July 28, 1994; 79 FR 75741, Dec. 19, 2014]



Sec. 73.50  Requirements for physical protection of licensed 
activities.

    Each licensee who is not subject to Sec. 73.51, but who possesses, 
uses, or stores formula quantities of strategic special nuclear material 
that are not readily separable from other radioactive material and which 
have total external radiation dose rates in excess of 100 rems per hour 
at a distance of 3 feet from any accessible surfaces without intervening 
shielding other than at nuclear reactor facility licensed under parts 50 
or 52 of this chapter, shall comply with the following:
    (a) Physical security organization. (1) The licensee shall establish 
a security organization, including guards, to protect his facility 
against radiological sabotage and the special nuclear material in his 
possession against theft.
    (2) At least one supervisor of the security organization shall be on 
site at all times.
    (3) The licensee shall establish, maintain, and follow written 
security procedures that document the structure of the security 
organization and detail the duties of guards, watchmen, and other 
individuals responsible for security. The licensee shall retain a copy 
of the current procedures as a record until the Commission terminates 
each license for which the procedures were developed and, if any portion 
of the procedures is superseded, retain the superseded material for 
three years after each change.
    (4) The licensee may not permit an individual to act as a guard, 
watchman, armed response person, or other member of the security 
organization unless the individual has been trained, equipped, and 
qualified to perform each assigned security job duty in accordance with 
appendix B, ``General Criteria for Security Personnel,'' to this part. 
Upon the request of an authorized representative of the Commission, the 
licensee shall demonstrate the ability of the physical security 
personnel to carry out their assigned duties and responsibilities. Each 
guard, watchman, armed response person, and other member of the security 
organization shall requalify in accordance with appendix B to this part 
at least every 12 months. This requalification must be documented. The 
licensee shall retain the documentation of each requalification as a 
record for three years after the requalification.
    (b) Physical barriers. (1) The licensee shall locate vital equipment 
only within a vital area, which, in turn, shall be located within a 
protected area such that access to vital equipment requires passage 
through at least two physical barriers. More than one vital area may be 
within a single protected area.
    (2) The licensee shall locate material access areas only within 
protected areas such that access to the material access area requires 
passage through at least two physical barriers. More than one material 
access area may be within a single protected area.
    (3) The physical barrier at the perimeter of the protected area 
shall be separated from any other barrier designated as a physical 
barrier within the protected area, and the intervening space monitored 
or periodically

[[Page 514]]

checked to detect the presence of persons or vehicles so that the 
facility security organization can respond to suspicious activity or to 
the breaching of any physical barrier.
    (4) An isolation zone shall be maintained around the physical 
barrier at the perimeter of the protected area and any part of a 
building used as part of that physical barrier. The isolation zone shall 
be monitored to detect the presence of individuals or vehicles within 
the zone so as to allow response by armed members of the license 
security organization to be initiated at the time of penetration of the 
protected area. Parking facilities, both for employees and visitors, 
shall be located outside the isolation zone.
    (5) Isolation zones and clear areas between barriers shall be 
provided with illumination sufficient for the monitoring required by 
paragraphs (b) (3) and (4) of this section, but not less than 0.2 foot 
candles.
    (c) Access requirements. The licensee shall control all points of 
personnel and vehicle access into a protected area, including shipping 
or receiving areas, and into each vital area. Identification of 
personnel and vehicles shall be made and authorization shall be checked 
at such points.
    (1) At the point of personnel and vehicle access into a protected 
area, all individuals, except employees who possess a NRC or United 
States Department of Energy access authorization, and all hand-carried 
packages shall be searched for devices such as firearms, explosives, and 
incendiary devices, or other items which could be used for radiological 
sabotage. The search shall be conducted either by a physical search or 
by the use of equipment capable of detecting such devices. Employees who 
possess an NRC or Department of Energy access authorization shall be 
searched at random intervals. Subsequent to search, drivers of delivery 
and service vehicles shall be escorted at all times while within the 
protection area.
    (2) All packages being delivered into the protected area shall be 
checked for proper identification and authorization. Packages other than 
hand-carried packages shall be searched at random intervals.
    (3) A picture badge identification system shall be used for all 
individuals who are authorized access to protected areas without escort.
    (4) Access to vital areas and material access areas shall be limited 
to individuals who are authorized access to vital equipment or special 
nuclear material and who require such access to perform their duties. 
Authorization for such individuals shall be provided by the issuance of 
specially coded numbered badges indicating vital areas and material 
access areas to which access is authorized. Unoccupied vital areas and 
material access areas shall be protected by an active intrusion alarm 
system.
    (5) Individuals not employed by the licensee must be escorted by a 
watchman, or other individual designated by the licensee, while in a 
protected area and must be badged to indicate that an escort is 
required. In addition, the licensee shall require that each individual 
not employed by the licensee register his or her name, date, time, 
purpose of visit, employment affiliation, citizenship, name and badge 
number of the escort, and name of the individual to be visited. The 
licensee shall retain the register of information for three years after 
the last entry is made in the register. Except for a driver of a 
delivery or service vehicle, an individual not employed by the licensee 
who requires frequent and extended access to a protected area or a vital 
area need not be escorted if the individual is provided with a picture 
badge, which the individual must receive upon entrance into the 
protected area and return each time he or she leaves the protected area, 
that indicates--
    (i) Nonemployee-no escort required,
    (ii) Areas to which access is authorized, and
    (iii) The period for which access has been authorized.
    (6) No vehicles used primarily for the conveyance of individuals 
shall be permitted within a protected area except under emergency 
conditions.
    (7) Keys, locks, combinations, and related equipment shall be 
controlled to minimize the possibility of compromise and promptly 
changed whenever there

[[Page 515]]

is evidence that they have been compromised. Upon termination of 
employment of any employee, keys, locks, combinations, and related 
equipment to which that employee had access shall be changed.
    (d) Detection aids. (1) All alarms required pursuant to this part 
shall annunciate in a continuously manned central alarm station located 
within the protected area and in at least one other continuously manned 
station, not necessarily within the protected area, such that a single 
act cannot remove the capability of calling for assistance or otherwise 
responding to an alarm. All alarms shall be self-checking and tamper 
indicating. The annunciation of an alarm at the onsite central alarm 
station shall indicate the type of alarm (e.g., intrusion alarm, 
emergency exit alarm, etc.) and location. All intrusion alarms, 
emergency exit alarms, alarm systems, and line supervisory systems shall 
at minimum meet the performance and reliability levels indicated by GSA 
Interim Federal Specification W-A-00450 B (GSA-FSS). The GSA Interim 
Federal Specification has been approved for incorporation by reference 
by the Director of the Federal Register. A copy of the material is 
available for inspection at the NRC Library, 11545 Rockville Pike, 
Rockville, Maryland 20852-2738.
    (2) All emergency exits in each protected area and each vital area 
shall be alarmed.
    (e) Communication requirements. (1) Each guard or watchman on duty 
shall be capable of maintaining continuous communication with an 
individual in a continuously manned central alarm station within the 
protected area, who shall be capable of calling for assistance from 
other guards and watchmen and from local law enforcement authorities.
    (2) The alarm stations required by paragraph (d)(1) of this section 
shall have conventional telephone service for communication with the law 
enforcement authorities as described in paragraph (e)(1) of this 
section.
    (3) To provide the capability of continuous communication, two-way 
radio voice communication shall be established in addition to 
conventional telephone service between local law enforcement authorities 
and the facility and shall terminate at the facility in a continuously 
manned central alarm station within the protected area.
    (4) All communications equipment, including offsite equipment, shall 
remain operable from independent power sources in the event of loss of 
primary power.
    (f) Testing and maintenance. Each licensee shall test and maintain 
intrusion alarms, emergency alarms, communications equipment, physical 
barriers, and other security related devices or equipment utilized 
pursuant to this section as follows:
    (1) All alarms, communications equipment, physical barriers, and 
other security related devices or equipment shall be maintained in 
operable and effective condition.
    (2) Each intrusion alarm shall be functionally tested for 
operability and required performance at the beginning and end of each 
interval during which it is used for security, but not less frequently 
than once every seven (7) days.
    (3) Communications equipment shall be tested for operability and 
performance not less frequently than once at the beginning of each 
security personnel work shift.
    (g) Response requirement. (1) The licensee shall establish, 
maintain, and follow an NRC-approved safeguards contingency plan for 
responding to threats, thefts, and radiological sabotage related to the 
special nuclear material and nuclear facilities subject to the 
provisions of this section. Safeguards contingency plans must be in 
accordance with the criteria in appendix C to this part, ``Licensee 
Safeguards Contingency Plans.'' The licensee shall retain the current 
safeguards contingency plan as a record until the Commission terminates 
the license and, if any portion of the plan is superseded, retain the 
superseded portion for 3 years after the effective date of the change.
    (2) The licensee shall establish and document liaison with law 
enforcement authorities. The licensee shall retain the documentation of 
the current liaison as a record until the Commission terminates each 
license for which the

[[Page 516]]

liaison was developed and, if any portion of the liaison documentation 
is superseded, retain the superseded material for three years after each 
change.
    (3) Upon detection of abnormal presence or activity of persons or 
vehicles within an isolation zone, a protected area, a material access 
area, or a vital area; or upon evidence or indication of intrusion into 
a protected area, material access area, or vital area, the licensee 
security organization shall:
    (i) Determine whether or not a threat exists,
    (ii) Assess the extent of the threat, if any, and
    (iii) Take immediate concurrent measures to neutralize the threat, 
by:
    (A) Requiring responding guards to interpose themselves between 
material access areas and vital areas and any adversary attempting entry 
for the purpose of theft of special nuclear material or radiological 
sabotage and to intercept any person exiting with special nuclear 
material, and,
    (B) Informing local law enforcement agencies of the threat and 
requesting assistance.
    (4) The licensee shall instruct every guard to prevent or impede 
attempted acts of theft or radiological sabotage by using force 
sufficient to counter the force directed at him including deadly force 
when the guard has a reasonable belief it is necessary in self-defense 
or in the defense of others.
    (h) Each licensee shall establish, maintain, and follow an NRC-
approved training and qualifications plan outlining the processes by 
which guards, watchmen, armed response persons, and other members of the 
security organization will be selected, trained, equipped, tested, and 
qualified to ensure that these individuals meet the requirements of 
paragraph (a)(4) of this section.

(Sec. 161i, Pub. L. 83-703, 68 Stat. 948, Pub. L. 93-377, 88 Stat. 475; 
secs. 201, 204(b)(1), Pub. L. 93-438, 88 Stat. 1242-1243, 1245, Pub. L. 
94-79, 89 Stat. 413 (42 U.S.C. 2201, 5841, 5844))

[38 FR 35430, Dec. 28, 1973, as amended at 42 FR 64103, Dec. 22, 1977; 
43 FR 11965, Mar. 23, 1978; 43 FR 37426, Aug. 23, 1978; 44 FR 68198, 
Nov. 28, 1979; 53 FR 19259, May 27, 1988; 57 FR 33430, July 29, 1992; 57 
FR 61787, Dec. 29, 1992; 59 FR 50689, Oct. 5, 1994; 63 FR 26962, May 15, 
1998; 72 FR 49561, Aug. 28, 2007]



Sec. 73.51  Requirements for the physical protection of stored spent
nuclear fuel and high-level radioactive waste.

    (a) Applicability. Notwithstanding the provisions of Sec. Sec. 
73.20, 73.50, or 73.67, the physical protection requirements of this 
section apply to each licensee that stores spent nuclear fuel and high-
level radioactive waste pursuant to paragraphs (a)(1)(i), (ii), and (2) 
of this section. This includes--
    (1) Spent nuclear fuel and high-level radioactive waste stored under 
a specific license issued pursuant to part 72 of this chapter:
    (i) At an independent spent fuel storage installation (ISFSI) or
    (ii) At a monitored retrievable storage (MRS) installation; or
    (2) Spent nuclear fuel and high-level radioactive waste at a 
geologic repository operations area (GROA) licensed pursuant to part 60 
or 63 of this chapter;
    (b) General performance objectives. (1) Each licensee subject to 
this section shall establish and maintain a physical protection system 
with the objective of providing high assurance that activities involving 
spent nuclear fuel and high-level radioactive waste do not constitute an 
unreasonable risk to public health and safety.
    (2) To meet the general objective of paragraph (b)(1) of this 
section, each licensee subject to this section shall meet the following 
performance capabilities.
    (i) Store spent nuclear fuel and high-level radioactive waste only 
within a protected area;
    (ii) Grant access to the protected area only to individuals who are 
authorized to enter the protected area;
    (iii) Detect and assess unauthorized penetration of, or activities 
within, the protected area;
    (iv) Provide timely communication to a designated response force 
whenever necessary; and
    (v) Manage the physical protection organization in a manner that 
maintains its effectiveness.
    (3) The physical protection system must be designed to protect 
against loss of control of the facility that could

[[Page 517]]

be sufficient to cause a radiation exposure exceeding the dose as 
described in Sec. 72.106 of this chapter.
    (c) Plan retention. Each licensee subject to this section shall 
retain a copy of the effective physical protection plan as a record for 
3 years or until termination of the license for which procedures were 
developed.
    (d) Physical protection systems, components, and procedures. A 
licensee shall comply with the following provisions as methods 
acceptable to NRC for meeting the performance capabilities of Sec. 
73.51(b)(2). The Commission may, on a specific basis and upon request or 
on its own initiative, authorize other alternative measures for the 
protection of spent fuel and high-level radioactive waste subject to the 
requirements of this section, if after evaluation of the specific 
alternative measures, it finds reasonable assurance of compliance with 
the performance capabilities of paragraph (b)(2) of this section.
    (1) Spent nuclear fuel and high-level radioactive waste must be 
stored only within a protected area so that access to this material 
requires passage through or penetration of two physical barriers, one 
barrier at the perimeter of the protected area and one barrier offering 
substantial penetration resistance. The physical barrier at the 
perimeter of the protected area must be as defined in Sec. 73.2. 
Isolation zones, typically 20 feet wide each, on both sides of this 
barrier, must be provided to facilitate assessment. The barrier offering 
substantial resistance to penetration may be provided by an approved 
storage cask or building walls such as those of a reactor or fuel 
storage building.
    (2) Illumination must be sufficient to permit adequate assessment of 
unauthorized penetrations of or activities within the protected area.
    (3) The perimeter of the protected area must be subject to continual 
surveillance and be protected by an active intrusion alarm system which 
is capable of detecting penetrations through the isolation zone and that 
is monitored in a continually staffed primary alarm station and in one 
additional continually staffed location. The primary alarm station must 
be located within the protected area; have bullet-resisting walls, 
doors, ceiling, and floor; and the interior of the station must not be 
visible from outside the protected area. A timely means for assessment 
of alarms must also be provided. Regarding alarm monitoring, the 
redundant location need only provide a summary indication that an alarm 
has been generated.
    (4) The protected area must be monitored by daily random patrols.
    (5) A security organization with written procedures must be 
established. The security organization must include sufficient personnel 
per shift to provide for monitoring of detection systems and the conduct 
of surveillance, assessment, access control, and communications to 
assure adequate response. Members of the security organization must be 
trained, equipped, qualified, and requalified to perform assigned job 
duties in accordance with appendix B to part 73, sections I.A, (1) (a) 
and (b), B(1)(a), and the applicable portions of II.
    (6) Documented liaison with a designated response force or local law 
enforcement agency (LLEA) must be established to permit timely response 
to unauthorized penetration or activities.
    (7) A personnel identification system and a controlled lock system 
must be established and maintained to limit access to authorized 
individuals.
    (8) Redundant communications capability must be provided between 
onsite security force members and designated response force or LLEA.
    (9) All individuals, vehicles, and hand-carried packages entering 
the protected area must be checked for proper authorization and visually 
searched for explosives before entry.
    (10) Written response procedures must be established and maintained 
for addressing unauthorized penetration of, or activities within, the 
protected area including Category 5, ``Procedures,'' of appendix C to 
part 73. The licensee shall retain a copy of response procedures as a 
record for 3 years or until termination of the license for which the 
procedures were developed. Copies of superseded material must be 
retained for 3 years after each change or until termination of the 
license.

[[Page 518]]

    (11) All detection systems and supporting subsystems must be tamper 
indicating with line supervision. These systems, as well as 
surveillance/assessment and illumination systems, must be maintained in 
operable condition. Timely compensatory measures must be taken after 
discovery of inoperability, to assure that the effectiveness of the of 
the security system is not reduced.
    (12) The physical protection program must be reviewed once every 24 
months by individuals independent of both physical protection program 
management and personnel who have direct responsibility for 
implementation of the physical protection program. The physical 
protection program review must include an evaluation of the 
effectiveness of the physical protection system and a verification of 
the liaison established with the designated response force or LLEA.
    (13) The following documentation must be retained as a record for 3 
years after the record is made or until termination of the license. 
Duplicate records to those required under Sec. 72.180 of part 72 and 
Sec. 73.71 of this part need not be retained under the requirements of 
this section:
    (i) A log of individuals granted access to the protected area;
    (ii) Screening records of members of the security organization;
    (iii) A log of all patrols;
    (iv) A record of each alarm received, identifying the type of alarm, 
location, date and time when received, and disposition of the alarm; and
    (v) The physical protection program review reports.
    (e) A licensee that operates a GROA is exempt from the requirements 
of this section for that GROA after permanent closure of the GROA.

[63 FR 26962, May 15, 1998, as amended at 63 FR 49414, Sept. 16, 1998; 
66 FR 55816, Nov. 2, 2001]



Sec. 73.54  Protection of digital computer and communication systems
and networks.

    By November 23, 2009 each licensee currently licensed to operate a 
nuclear power plant under part 50 of this chapter shall submit, as 
specified in Sec. 50.4 and Sec. 50.90 of this chapter, a cyber 
security plan that satisfies the requirements of this section for 
Commission review and approval. Each submittal must include a proposed 
implementation schedule. Implementation of the licensee's cyber security 
program must be consistent with the approved schedule. Current 
applicants for an operating license or combined license who have 
submitted their applications to the Commission prior to the effective 
date of this rule must amend their applications to include a cyber 
security plan consistent with this section.
    (a) Each licensee subject to the requirements of this section shall 
provide high assurance that digital computer and communication systems 
and networks are adequately protected against cyber attacks, up to and 
including the design basis threat as described in Sec. 73.1.
    (1) The licensee shall protect digital computer and communication 
systems and networks associated with:
    (i) Safety-related and important-to-safety functions;
    (ii) Security functions;
    (iii) Emergency preparedness functions, including offsite 
communications; and
    (iv) Support systems and equipment which, if compromised, would 
adversely impact safety, security, or emergency preparedness functions.
    (2) The licensee shall protect the systems and networks identified 
in paragraph (a)(1) of this section from cyber attacks that would:
    (i) Adversely impact the integrity or confidentiality of data and/or 
software;
    (ii) Deny access to systems, services, and/or data; and
    (iii) Adversely impact the operation of systems, networks, and 
associated equipment.
    (b) To accomplish this, the licensee shall:
    (1) Analyze digital computer and communication systems and networks 
and identify those assets that must be protected against cyber attacks 
to satisfy paragraph (a) of this section,
    (2) Establish, implement, and maintain a cyber security program for 
the protection of the assets identified in paragraph (b)(1) of this 
section; and

[[Page 519]]

    (3) Incorporate the cyber security program as a component of the 
physical protection program.
    (c) The cyber security program must be designed to:
    (1) Implement security controls to protect the assets identified by 
paragraph (b)(1) of this section from cyber attacks;
    (2) Apply and maintain defense-in-depth protective strategies to 
ensure the capability to detect, respond to, and recover from cyber 
attacks;
    (3) Mitigate the adverse affects of cyber attacks; and
    (4) Ensure that the functions of protected assets identified by 
paragraph (b)(1) of this section are not adversely impacted due to cyber 
attacks.
    (d) As part of the cyber security program, the licensee shall:
    (1) Ensure that appropriate facility personnel, including 
contractors, are aware of cyber security requirements and receive the 
training necessary to perform their assigned duties and 
responsibilities.
    (2) Evaluate and manage cyber risks.
    (3) Ensure that modifications to assets, identified by paragraph 
(b)(1) of this section, are evaluated before implementation to ensure 
that the cyber security performance objectives identified in paragraph 
(a)(1) of this section are maintained.
    (4) Conduct cyber security event notifications in accordance with 
the provisions of Sec. 73.77.
    (e) The licensee shall establish, implement, and maintain a cyber 
security plan that implements the cyber security program requirements of 
this section.
    (1) The cyber security plan must describe how the requirements of 
this section will be implemented and must account for the site-specific 
conditions that affect implementation.
    (2) The cyber security plan must include measures for incident 
response and recovery for cyber attacks. The cyber security plan must 
describe how the licensee will:
    (i) Maintain the capability for timely detection and response to 
cyber attacks;
    (ii) Mitigate the consequences of cyber attacks;
    (iii) Correct exploited vulnerabilities; and
    (iv) Restore affected systems, networks, and/or equipment affected 
by cyber attacks.
    (f) The licensee shall develop and maintain written policies and 
implementing procedures to implement the cyber security plan. Policies, 
implementing procedures, site-specific analysis, and other supporting 
technical information used by the licensee need not be submitted for 
Commission review and approval as part of the cyber security plan but 
are subject to inspection by NRC staff on a periodic basis.
    (g) The licensee shall review the cyber security program as a 
component of the physical security program in accordance with the 
requirements of Sec. 73.55(m), including the periodicity requirements.
    (h) The licensee shall retain all records and supporting technical 
documentation required to satisfy the requirements of this section as a 
record until the Commission terminates the license for which the records 
were developed, and shall maintain superseded portions of these records 
for at least three (3) years after the record is superseded, unless 
otherwise specified by the Commission.

[74 FR 13970, Mar. 27, 2009, as amended at 80 FR 67275, Nov. 2, 2015]



Sec. 73.55  Requirements for physical protection of licensed 
activities in nuclear power reactors against radiological sabotage.

    (a) Introduction. (1) By March 31, 2010, each nuclear power reactor 
licensee, licensed under 10 CFR part 50, shall implement the 
requirements of this section through its Commission-approved Physical 
Security Plan, Training and Qualification Plan, Safeguards Contingency 
Plan, and Cyber Security Plan referred to collectively hereafter as 
``security plans.'' Current applicants for an operating license under 10 
CFR part 50, or combined license under 10 CFR part 52 who have submitted 
their applications to the Commission prior to the effective date of this 
rule must amend their applications to include security plans consistent 
with this section.

[[Page 520]]

    (2) The security plans must identify, describe, and account for 
site-specific conditions that affect the licensee's capability to 
satisfy the requirements of this section.
    (3) The licensee is responsible for maintaining the onsite physical 
protection program in accordance with Commission regulations through the 
implementation of security plans and written security implementing 
procedures.
    (4) Applicants for an operating license under the provisions of part 
50 of this chapter or holders of a combined license under the provisions 
of part 52 of this chapter, shall implement the requirements of this 
section before fuel is allowed onsite (protected area).
    (5) The Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 2, 
holding a current construction permit under the provisions of part 50 of 
this chapter, shall meet the revised requirements in paragraphs (a) 
through (r) of this section as applicable to operating nuclear power 
reactor facilities.
    (6) Applicants for an operating license under the provisions of part 
50 of this chapter, or holders of a combined license under the 
provisions of part 52 of this chapter that do not reference a standard 
design certification or reference a standard design certification issued 
after May 26, 2009 shall meet the requirement of Sec. 73.55(i)(4)(iii).
    (b) General performance objective and requirements. (1) The licensee 
shall establish and maintain a physical protection program, to include a 
security organization, which will have as its objective to provide high 
assurance that activities involving special nuclear material are not 
inimical to the common defense and security and do not constitute an 
unreasonable risk to the public health and safety.
    (2) To satisfy the general performance objective of paragraph (b)(1) 
of this section, the physical protection program must protect against 
the design basis threat of radiological sabotage as stated in Sec. 
73.1.
    (3) The physical protection program must be designed to prevent 
significant core damage and spent fuel sabotage. Specifically, the 
program must:
    (i) Ensure that the capabilities to detect, assess, interdict, and 
neutralize threats up to and including the design basis threat of 
radiological sabotage as stated in Sec. 73.1, are maintained at all 
times.
    (ii) Provide defense-in-depth through the integration of systems, 
technologies, programs, equipment, supporting processes, and 
implementing procedures as needed to ensure the effectiveness of the 
physical protection program.
    (4) The licensee shall analyze and identify site-specific 
conditions, including target sets, that may affect the specific measures 
needed to implement the requirements of this section and shall account 
for these conditions in the design of the physical protection program.
    (5) Upon the request of an authorized representative of the 
Commission, the licensee shall demonstrate the ability to meet 
Commission requirements through the implementation of the physical 
protection program, including the ability of armed and unarmed personnel 
to perform assigned duties and responsibilities required by the security 
plans and licensee procedures.
    (6) The licensee shall establish, maintain, and implement a 
performance evaluation program in accordance with appendix B to this 
part, to demonstrate and assess the effectiveness of armed responders 
and armed security officers to implement the licensee's protective 
strategy.
    (7) The licensee shall establish, maintain, and implement an access 
authorization program in accordance with Sec. 73.56 and shall describe 
the program in the Physical Security Plan.
    (8) The licensee shall establish, maintain, and implement a cyber 
security program in accordance with Sec. 73.54.
    (9) The licensee shall establish, maintain, and implement an insider 
mitigation program and shall describe the program in the Physical 
Security Plan.
    (i) The insider mitigation program must monitor the initial and 
continuing trustworthiness and reliability of individuals granted or 
retaining unescorted access authorization to a protected or vital area, 
and implement

[[Page 521]]

defense-in-depth methodologies to minimize the potential for an insider 
to adversely affect, either directly or indirectly, the licensee's 
capability to prevent significant core damage and spent fuel sabotage.
    (ii) The insider mitigation program must contain elements from:
    (A) The access authorization program described in Sec. 73.56;
    (B) The fitness-for-duty program described in part 26 of this 
chapter;
    (C) The cyber security program described in Sec. 73.54; and
    (D) The physical protection program described in this section.
    (10) The licensee shall use the site corrective action program to 
track, trend, correct and prevent recurrence of failures and 
deficiencies in the physical protection program.
    (11) Implementation of security plans and associated procedures must 
be coordinated with other onsite plans and procedures to preclude 
conflict during both normal and emergency conditions.
    (c) Security plans. (1) Licensee security plans must describe:
    (i) How the licensee will implement requirements of this section 
through the establishment and maintenance of a security organization, 
the use of security equipment and technology, the training and 
qualification of security personnel, the implementation of predetermined 
response plans and strategies, and the protection of digital computer 
and communication systems and networks.
    (ii) Site-specific conditions that affect how the licensee 
implements Commission requirements.
    (2) Protection of security plans. The licensee shall protect the 
security plans and other security-related information against 
unauthorized disclosure in accordance with the requirements of Sec. 
73.21.
    (3) Physical Security Plan. The licensee shall establish, maintain, 
and implement a Physical Security Plan which describes how the 
performance objective and requirements set forth in this section will be 
implemented.
    (4) Training and Qualification Plan. The licensee shall establish, 
maintain, and implement, and follow a Training and Qualification Plan 
that describes how the criteria set forth in appendix B, section VI, to 
this part, ``Nuclear Power Reactor Training and Qualification Plan for 
Personnel Performing Security Program Duties,'' will be implemented.
    (5) Safeguards Contingency Plan. The licensee shall establish, 
maintain, and implement a Safeguards Contingency Plan that describes how 
the criteria set forth in appendix C, section II, to this part, 
``Nuclear Power Plant Safeguards Contingency Plans,'' will be 
implemented.
    (6) Cyber Security Plan. The licensee shall establish, maintain, and 
implement a Cyber Security Plan that describes how the criteria set 
forth in Sec. 73.54 ``Protection of Digital Computer and Communication 
systems and Networks'' of this part will be implemented.
    (7) Security implementing procedures. (i) The licensee shall have a 
management system to provide for the development, implementation, 
revision, and oversight of security procedures that implement Commission 
requirements and the security plans.
    (ii) Implementing procedures must document the structure of the 
security organization and detail the types of duties, responsibilities, 
actions, and decisions to be performed or made by each position of the 
security organization.
    (iii) The licensee shall:
    (A) Provide a process for the written approval of implementing 
procedures and revisions by the individual with overall responsibility 
for the security program.
    (B) Ensure that revisions to security implementing procedures 
satisfy the requirements of this section.
    (iv) Implementing procedures need not be submitted to the Commission 
for approval, but are subject to inspection by the Commission.
    (d) Security organization. (1) The licensee shall establish and 
maintain a security organization that is designed, staffed, trained, 
qualified, and equipped to implement the physical protection program in 
accordance with the requirements of this section.
    (2) The security organization must include:
    (i) A management system that provides oversight of the onsite 
physical protection program.

[[Page 522]]

    (ii) At least one member, onsite and available at all times, who has 
the authority to direct the activities of the security organization and 
who is assigned no other duties that would interfere with this 
individual's ability to perform these duties in accordance with the 
security plans and the licensee protective strategy.
    (3) The licensee may not permit any individual to implement any part 
of the physical protection program unless the individual has been 
trained, equipped, and qualified to perform their assigned duties and 
responsibilities in accordance with appendix B, section VI, to this part 
and the Training and Qualification Plan. Non-security personnel may be 
assigned duties and responsibilities required to implement the physical 
protection program and shall:
    (i) Be trained through established licensee training programs to 
ensure each individual is trained, qualified, and periodically re-
qualified to perform assigned duties.
    (ii) Be properly equipped to perform assigned duties.
    (iii) Possess the knowledge, skills, and abilities, to include 
physical attributes such as sight and hearing, required to perform their 
assigned duties and responsibilities.
    (e) Physical barriers. Each licensee shall identify and analyze 
site-specific conditions to determine the specific use, type, function, 
and placement of physical barriers needed to satisfy the physical 
protection program design requirements of Sec. 73.55(b).
    (1) The licensee shall:
    (i) Design, construct, install and maintain physical barriers as 
necessary to control access into facility areas for which access must be 
controlled or denied to satisfy the physical protection program design 
requirements of paragraph (b) of this section.
    (ii) Describe in the physical security plan, physical barriers, 
barrier systems, and their functions within the physical protection 
program.
    (2) The licensee shall retain, in accordance with Sec. 73.70, all 
analyses and descriptions of the physical barriers and barrier systems 
used to satisfy the requirements of this section, and shall protect 
these records in accordance with the requirements of Sec. 73.21.
    (3) Physical barriers must:
    (i) Be designed and constructed to:
    (A) Protect against the design basis threat of radiological 
sabotage;
    (B) Account for site-specific conditions; and
    (C) Perform their required function in support of the licensee 
physical protection program.
    (ii) Provide deterrence, delay, or support access control.
    (iii) Support effective implementation of the licensee's protective 
strategy.
    (4) Consistent with the stated function to be performed, openings in 
any barrier or barrier system established to meet the requirements of 
this section must be secured and monitored to prevent exploitation of 
the opening.
    (5) Bullet resisting physical barriers. The reactor control room, 
the central alarm station, and the location within which the last access 
control function for access to the protected area is performed, must be 
bullet-resisting.
    (6) Owner controlled area. The licensee shall establish and maintain 
physical barriers in the owner controlled area as needed to satisfy the 
physical protection program design requirements of Sec. 73.55(b).
    (7) Isolation zone. (i) An isolation zone must be maintained in 
outdoor areas adjacent to the protected area perimeter barrier. The 
isolation zone shall be:
    (A) Designed and of sufficient size to permit observation and 
assessment of activities on either side of the protected area barrier;
    (B) Monitored with intrusion detection equipment designed to satisfy 
the requirements of Sec. 73.55(i) and be capable of detecting both 
attempted and actual penetration of the protected area perimeter barrier 
before completed penetration of the protected area perimeter barrier; 
and
    (C) Monitored with assessment equipment designed to satisfy the 
requirements of Sec. 73.55(i) and provide real-time and play-back/
recorded video images of the detected activities before and after each 
alarm annunciation.
    (ii) Obstructions that could prevent the licensee's capability to 
meet the

[[Page 523]]

observation and assessment requirements of this section must be located 
outside of the isolation zone.
    (8) Protected area. (i) The protected area perimeter must be 
protected by physical barriers that are designed and constructed to:
    (A) Limit access into the protected area to only those personnel, 
vehicles, and materials required to perform official duties;
    (B) Channel personnel, vehicles, and materials to designated access 
control portals; and
    (C) Be separated from any other barrier designated as a vital area 
physical barrier, unless otherwise identified in the Physical Security 
Plan.
    (ii) Penetrations through the protected area barrier must be secured 
and monitored in a manner that prevents or delays, and detects the 
exploitation of any penetration.
    (iii) All emergency exits in the protected area must be alarmed and 
secured by locking devices that allow prompt egress during an emergency 
and satisfy the requirements of this section for access control into the 
protected area.
    (iv) Where building walls or roofs comprise a portion of the 
protected area perimeter barrier, an isolation zone is not necessary 
provided that the detection and, assessment requirements of this section 
are met, appropriate barriers are installed, and the area is described 
in the security plans.
    (v) All exterior areas within the protected area, except for areas 
that must be excluded for safety reasons, must be periodically checked 
to detect and deter unauthorized personnel, vehicles, and materials.
    (9) Vital areas. (i) Vital equipment must be located only within 
vital areas, which must be located within a protected area so that 
access to vital equipment requires passage through at least two physical 
barriers, except as otherwise approved by the Commission and identified 
in the security plans.
    (ii) The licensee shall protect all vital area access portals and 
vital area emergency exits with intrusion detection equipment and 
locking devices that allow rapid egress during an emergency and satisfy 
the vital area entry control requirements of this section.
    (iii) Unoccupied vital areas must be locked and alarmed.
    (iv) More than one vital area may be located within a single 
protected area.
    (v) At a minimum, the following shall be considered vital areas:
    (A) The reactor control room;
    (B) The spent fuel pool;
    (C) The central alarm station; and
    (D) The secondary alarm station in accordance with Sec. 
73.55(i)(4)(iii).
    (vi) At a minimum, the following shall be located within a vital 
area:
    (A) The secondary power supply systems for alarm annunciation 
equipment; and
    (B) The secondary power supply systems for non-portable 
communications equipment.
    (10) Vehicle control measures. Consistent with the physical 
protection program design requirements of Sec. 73.55(b), and in 
accordance with the site-specific analysis, the licensee shall establish 
and maintain vehicle control measures, as necessary, to protect against 
the design basis threat of radiological sabotage vehicle bomb assault.
    (i) Land vehicles. Licensees shall:
    (A) Design, construct, install, and maintain a vehicle barrier 
system, to include passive and active barriers, at a stand-off distance 
adequate to protect personnel, equipment, and systems necessary to 
prevent significant core damage and spent fuel sabotage against the 
effects of the design basis threat of radiological sabotage land vehicle 
bomb assault.
    (B) Periodically check the operation of active vehicle barriers and 
provide a secondary power source, or a means of mechanical or manual 
operation in the event of a power failure, to ensure that the active 
barrier can be placed in the denial position to prevent unauthorized 
vehicle access beyond the required standoff distance.
    (C) Provide periodic surveillance and observation of vehicle 
barriers and barrier systems adequate to detect indications of tampering 
and degradation or to otherwise ensure that each vehicle barrier and 
barrier system is able to satisfy the intended function.
    (D) Where a site has rail access to the protected area, install a 
train derailer, remove a section of track, or restrict access to 
railroad sidings and provide

[[Page 524]]

periodic surveillance of these measures.
    (ii) Waterborne vehicles. Licensees shall:
    (A) Identify areas from which a waterborne vehicle must be 
restricted, and where possible, in coordination with local, State, and 
Federal agencies having jurisdiction over waterway approaches, deploy 
buoys, markers, or other equipment.
    (B) In accordance with the site-specific analysis, provide periodic 
surveillance and observation of waterway approaches and adjacent areas.
    (f) Target sets. (1) The licensee shall document and maintain the 
process used to develop and identify target sets, to include the site-
specific analyses and methodologies used to determine and group the 
target set equipment or elements.
    (2) The licensee shall consider cyber attacks in the development and 
identification of target sets.
    (3) Target set equipment or elements that are not contained within a 
protected or vital area must be identified and documented consistent 
with the requirements in Sec. 73.55(f)(1) and be accounted for in the 
licensee's protective strategy.
    (4) The licensee shall implement a process for the oversight of 
target set equipment and systems to ensure that changes to the 
configuration of the identified equipment and systems are considered in 
the licensee's protective strategy. Where appropriate, changes must be 
made to documented target sets.
    (g) Access controls. (1) Consistent with the function of each 
barrier or barrier system, the licensee shall control personnel, 
vehicle, and material access, as applicable, at each access control 
point in accordance with the physical protection program design 
requirements of Sec. 73.55(b).
    (i) To accomplish this, the licensee shall:
    (A) Locate access control portals outside of, or concurrent with, 
the physical barrier system through which it controls access.
    (B) Equip access control portals with locking devices, intrusion 
detection equipment, and surveillance equipment consistent with the 
intended function.
    (C) Provide supervision and control over the badging process to 
prevent unauthorized bypass of access control equipment located at or 
outside of the protected area.
    (D) Limit unescorted access to the protected area and vital areas, 
during non-emergency conditions, to only those individuals who require 
unescorted access to perform assigned duties and responsibilities.
    (E) Assign an individual the responsibility for the last access 
control function (controlling admission to the protected area) and 
isolate the individual within a bullet-resisting structure to assure the 
ability of the individual to respond or summon assistance.
    (ii) Where vehicle barriers are established, the licensee shall:
    (A) Physically control vehicle barrier portals to ensure only 
authorized vehicles are granted access through the barrier.
    (B) Search vehicles and materials for contraband or other items 
which could be used to commit radiological sabotage in accordance with 
paragraph (h) of this section.
    (C) Observe search functions to ensure a response can be initiated 
if needed.
    (2) Before granting access into the protected area, the licensee 
shall:
    (i) Confirm the identity of individuals.
    (ii) Verify the authorization for access of individuals, vehicles, 
and materials.
    (iii) Confirm, in accordance with industry shared lists and 
databases that individuals are not currently denied access to another 
licensed facility.
    (iv) Search individuals, vehicles, and materials in accordance with 
paragraph (h) of this section.
    (3) Vehicles in the protected area. (i) The licensee shall exercise 
control over all vehicles inside the protected area to ensure that they 
are used only by authorized persons and for authorized purposes.
    (ii) Vehicles inside the protected area must be operated by an 
individual authorized unescorted access to the area, or must be escorted 
by an individual as required by paragraph (g)(8) of this section.

[[Page 525]]

    (iii) Vehicle use inside the protected area must be limited to plant 
functions or emergencies, and keys must be removed or the vehicle 
otherwise disabled when not in use.
    (iv) Vehicles transporting hazardous materials inside the protected 
area must be escorted by an armed member of the security organization.
    (4) Vital areas. (i) Licensees shall control access into vital areas 
consistent with access authorization lists.
    (ii) In response to a site-specific credible threat or other 
credible information, implement a two-person (line-of-sight) rule for 
all personnel in vital areas so that no one individual is permitted 
access to a vital area.
    (5) Emergency conditions. (i) The licensee shall design the access 
control system to accommodate the potential need for rapid ingress or 
egress of authorized individuals during emergency conditions or 
situations that could lead to emergency conditions.
    (ii) To satisfy the design criteria of paragraph (g)(5)(i) of this 
section during emergency conditions, the licensee shall implement 
security procedures to ensure that authorized emergency personnel are 
provided prompt access to affected areas and equipment.
    (6) Access control devices. (i) The licensee shall control all keys, 
locks, combinations, passwords and related access control devices used 
to control access to protected areas, vital areas and security systems 
to reduce the probability of compromise. To accomplish this, the 
licensee shall:
    (A) Issue access control devices only to individuals who have 
unescorted access authorization and require access to perform official 
duties and responsibilities.
    (B) Maintain a record, to include name and affiliation, of all 
individuals to whom access control devices have been issued, and 
implement a process to account for access control devices at least 
annually.
    (C) Implement compensatory measures upon discovery or suspicion that 
any access control device may have been compromised. Compensatory 
measures must remain in effect until the compromise is corrected.
    (D) Retrieve, change, rotate, deactivate, or otherwise disable 
access control devices that have been or may have been compromised or 
when a person with access to control devices has been terminated under 
less than favorable conditions.
    (ii) The licensee shall implement a numbered photo identification 
badge system for all individuals authorized unescorted access to the 
protected area and vital areas.
    (A) Identification badges may be removed from the protected area 
only when measures are in place to confirm the true identity and 
authorization for unescorted access of the badge holder before allowing 
unescorted access to the protected area.
    (B) Except where operational safety concerns require otherwise, 
identification badges must be clearly displayed by all individuals while 
inside the protected area and vital areas.
    (C) The licensee shall maintain a record, to include the name and 
areas to which unescorted access is granted, of all individuals to whom 
photo identification badges have been issued.
    (iii) Access authorization program personnel shall be issued 
passwords and combinations to perform their assigned duties and may be 
excepted from the requirement of paragraph (g)(6)(i)(A) of this section 
provided they meet the background requirements of Sec. 73.56.
    (7) Visitors. (i) The licensee may permit escorted access to 
protected and vital areas to individuals who have not been granted 
unescorted access in accordance with the requirements of Sec. 73.56 and 
part 26 of this chapter. The licensee shall:
    (A) Implement procedures for processing, escorting, and controlling 
visitors.
    (B) Confirm the identity of each visitor through physical 
presentation of a recognized identification card issued by a local, 
State, or Federal government agency that includes a photo or contains 
physical characteristics of the individual requesting escorted access.
    (C) Maintain a visitor control register in which all visitors shall 
register their name, date, time, purpose of visit, employment 
affiliation, citizenship, and name of the individual to be visited 
before being escorted into any protected or vital area.

[[Page 526]]

    (D) Issue a visitor badge to all visitors that clearly indicates an 
escort is required.
    (E) Escort all visitors, at all times, while inside the protected 
area and vital areas.
    (F) Deny escorted access to any individual who is currently denied 
access in industry shared data bases.
    (ii) Individuals not employed by the licensee but who require 
frequent or extended unescorted access to the protected area and/or 
vital areas to perform duties and responsibilities required by the 
licensee at irregular or intermittent intervals, shall satisfy the 
access authorization requirements of Sec. 73.56 and part 26 of this 
chapter, and shall be issued a non-employee photo identification badge 
that is easily distinguished from other identification badges before 
being allowed unescorted access to the protected and vital areas. Non-
employee photo identification badges must visually reflect that the 
individual is a non-employee and that no escort is required.
    (8) Escorts. The licensee shall ensure that all escorts are trained 
to perform escort duties in accordance with the requirements of this 
section and site training requirements.
    (i) Escorts shall be authorized unescorted access to all areas in 
which they will perform escort duties.
    (ii) Individuals assigned to visitor escort duties shall be provided 
a means of timely communication with security personnel to summon 
assistance when needed.
    (iii) Individuals assigned to vehicle escort duties shall be trained 
and qualified in accordance with appendix B, section VI, of this part 
and provided a means of continuous communication with security personnel 
to ensure the ability to summon assistance when needed.
    (iv) When visitors are performing work, escorts shall be generally 
knowledgeable of the activities to be performed by the visitor and 
report behaviors or activities that may constitute an unreasonable risk 
to the health and safety of the public and common defense and security, 
including a potential threat to commit radiological sabotage, consistent 
with Sec. 73.56(f)(1).
    (v) Each licensee shall describe visitor to escort ratios for the 
protected area and vital areas in physical security plans. Implementing 
procedures shall provide necessary observation and control requirements 
for all visitor activities.
    (h) Search programs. (1) The objective of the search program is to 
detect, deter, and prevent the introduction of firearms, explosives, 
incendiary devices, or other items which could be used to commit 
radiological sabotage. To accomplish this the licensee shall search 
individuals, vehicles, and materials consistent with the physical 
protection program design requirements in paragraph (b) of this section, 
and the function to be performed at each access control point or portal 
before granting access.
    (2) Owner controlled area searches. (i) Where the licensee has 
established physical barriers in the owner controlled area, the licensee 
shall implement search procedures for access control points in the 
barrier.
    (ii) For each vehicle access control point, the licensee shall 
describe in implementing procedures areas of a vehicle to be searched, 
and the items for which the search is intended to detect and prevent 
access. Areas of the vehicle to be searched must include, but are not 
limited to, the cab, engine compartment, undercarriage, and cargo area.
    (iii) Vehicle searches must be performed by at least two (2) trained 
and equipped security personnel, one of which must be armed. The armed 
individual shall be positioned to observe the search process and provide 
immediate response.
    (iv) Vehicle searches must be accomplished through the use of 
equipment capable of detecting firearms, explosives, incendiary devices, 
or other items which could be used to commit radiological sabotage, or 
through visual and physical searches, or both, to ensure that all items 
are identified before granting access.
    (v) Vehicle access control points must be equipped with video 
surveillance equipment that is monitored by an individual capable of 
initiating a response.

[[Page 527]]

    (3) Protected area searches. Licensees shall search all personnel, 
vehicles and materials requesting access to protected areas.
    (i) The search for firearms, explosives, incendiary devices, or 
other items which could be used to commit radiological sabotage shall be 
accomplished through the use of equipment capable of detecting these 
items, or through visual and physical searches, or both, to ensure that 
all items are clearly identified before granting access to protected 
areas. The licensee shall subject all persons except official Federal, 
state, and local law enforcement personnel on official duty to these 
searches upon entry to the protected area. Armed security officers who 
are on duty and have exited the protected area may re-enter the 
protected area without being searched for firearms.
    (ii) Whenever search equipment is out of service, is not operating 
satisfactorily, or cannot be used effectively to search individuals, 
vehicles, or materials, a visual and physical search shall be conducted.
    (iii) When an attempt to introduce firearms, explosives, incendiary 
devices, or other items which could be used to commit radiological 
sabotage has occurred or is suspected, the licensee shall implement 
actions to ensure that the suspect individuals, vehicles, and materials 
are denied access and shall perform a visual and physical search to 
determine the absence or existence of a threat.
    (iv) For each vehicle access portal, the licensee shall describe in 
implementing procedures areas of a vehicle to be searched before access 
is granted. Areas of the vehicle to be searched must include, but are 
not limited to, the cab, engine compartment, undercarriage, and cargo 
area.
    (v) Exceptions to the protected area search requirements for 
materials may be granted for safety or operational reasons provided the 
design criteria of Sec. 73.55(b) are satisfied, the materials are 
clearly identified, the types of exceptions to be granted are described 
in the security plans, and the specific security measures to be 
implemented for excepted items are detailed in site procedures.
    (vi) To the extent practicable, excepted materials must be 
positively controlled, stored in a locked area, and opened at the final 
destination by an individual familiar with the items.
    (vii) Bulk material excepted from the protected area search 
requirements must be escorted by an armed member of the security 
organization to its final destination or to a receiving area where the 
excepted items are offloaded and verified.
    (viii) To the extent practicable, bulk materials excepted from 
search shall not be offloaded adjacent to a vital area.
    (i) Detection and assessment systems. (1) The licensee shall 
establish and maintain intrusion detection and assessment systems that 
satisfy the design requirements of Sec. 73.55(b) and provide, at all 
times, the capability to detect and assess unauthorized persons and 
facilitate the effective implementation of the licensee's protective 
strategy.
    (2) Intrusion detection equipment must annunciate and video 
assessment equipment shall display concurrently, in at least two 
continuously staffed onsite alarm stations, at least one of which must 
be protected in accordance with the requirements of the central alarm 
station within this section.
    (3) The licensee's intrusion detection and assessment systems must 
be designed to:
    (i) Provide visual and audible annunciation of the alarm.
    (ii) Provide a visual display from which assessment of the detected 
activity can be made.
    (iii) Ensure that annunciation of an alarm indicates the type and 
location of the alarm.
    (iv) Ensure that alarm devices to include transmission lines to 
annunciators are tamper indicating and self-checking.
    (v) Provide an automatic indication when the alarm system or a 
component of the alarm system fails, or when the system is operating on 
the backup power supply.
    (vi) Support the initiation of a timely response in accordance with 
the security plans, licensee protective strategy, and associated 
implementing procedures.

[[Page 528]]

    (vii) Ensure intrusion detection and assessment equipment at the 
protected area perimeter remains operable from an uninterruptible power 
supply in the event of the loss of normal power.
    (4) Alarm stations. (i) Both alarm stations required by paragraph 
(i)(2) of this section must be designed and equipped to ensure that a 
single act, in accordance with the design basis threat of radiological 
sabotage defined in Sec. 73.1(a)(1), cannot disable both alarm 
stations. The licensee shall ensure the survivability of at least one 
alarm station to maintain the ability to perform the following 
functions:
    (A) Detect and assess alarms;
    (B) Initiate and coordinate an adequate response to an alarm;
    (C) Summon offsite assistance; and
    (D) Provide command and control.
    (ii) Licensees shall:
    (A) Locate the central alarm station inside a protected area. The 
interior of the central alarm station must not be visible from the 
perimeter of the protected area.
    (B) Continuously staff each alarm station with at least one trained 
and qualified alarm station operator. The alarm station operator must 
not be assigned other duties or responsibilities which would interfere 
with the ability to execute the functions described in Sec. 
73.55(i)(4)(i) of this section.
    (C) Not permit any activities to be performed within either alarm 
station that would interfere with an alarm station operator's ability to 
execute assigned duties and responsibilities.
    (D) Assess and initiate response to all alarms in accordance with 
the security plans and implementing procedures.
    (E) Assess and initiate response to other events as appropriate.
    (F) Ensure that an alarm station operator cannot change the status 
of a detection point or deactivate a locking or access control device at 
a protected or vital area portal, without the knowledge and concurrence 
of the alarm station operator in the other alarm station.
    (G) Ensure that operators in both alarm stations are knowledgeable 
of the final disposition of all alarms.
    (H) Maintain a record of all alarm annunciations, the cause of each 
alarm, and the disposition of each alarm.
    (iii) Applicants for an operating license under the provisions of 
part 50 of this chapter, or holders of a combined license under the 
provisions of part 52 of this chapter, shall construct, locate, protect, 
and equip both the central and secondary alarm stations to the standards 
for the central alarm station contained in this section. Both alarm 
stations shall be equal and redundant, such that all functions needed to 
satisfy the requirements of this section can be performed in both alarm 
stations.
    (5) Surveillance, observation, and monitoring. (i) The physical 
protection program must include surveillance, observation, and 
monitoring as needed to satisfy the design requirements of Sec. 
73.55(b), identify indications of tampering, or otherwise implement the 
site protective strategy.
    (ii) The licensee shall provide continuous surveillance, 
observation, and monitoring of the owner controlled area as described in 
the security plans to detect and deter intruders and ensure the 
integrity of physical barriers or other components and functions of the 
onsite physical protection program. Continuous surveillance, 
observation, and monitoring responsibilities may be performed by 
security personnel during continuous patrols, through use of video 
technology, or by a combination of both.
    (iii) Unattended openings that intersect a security boundary such as 
underground pathways must be protected by a physical barrier and 
monitored by intrusion detection equipment or observed by security 
personnel at a frequency sufficient to detect exploitation.
    (iv) Armed security patrols shall periodically check external areas 
of the protected area to include physical barriers and vital area 
portals.
    (v) Armed security patrols shall periodically inspect vital areas to 
include the physical barriers used at all vital area portals.
    (vi) The licensee shall provide random patrols of all accessible 
areas containing target set equipment.

[[Page 529]]

    (vii) Security personnel shall be trained to recognize obvious 
indications of tampering consistent with their assigned duties and 
responsibilities.
    (viii) Upon detection of tampering, or other threats, the licensee 
shall initiate response in accordance with the security plans and 
implementing procedures.
    (6) Illumination. (i) The licensee shall ensure that all areas of 
the facility are provided with illumination necessary to satisfy the 
design requirements of Sec. 73.55(b) and implement the protective 
strategy.
    (ii) The licensee shall provide a minimum illumination level of 0.2 
foot-candles, measured horizontally at ground level, in the isolation 
zones and appropriate exterior areas within the protected area. 
Alternatively, the licensee may augment the facility illumination system 
by means of low-light technology to meet the requirements of this 
section or otherwise implement the protective strategy.
    (iii) The licensee shall describe in the security plans how the 
lighting requirements of this section are met and, if used, the type(s) 
and application of low-light technology.
    (j) Communication requirements. (1) The licensee shall establish and 
maintain continuous communication capability with onsite and offsite 
resources to ensure effective command and control during both normal and 
emergency situations.
    (2) Individuals assigned to each alarm station shall be capable of 
calling for assistance in accordance with the security plans and the 
licensee's procedures.
    (3) All on-duty security force personnel shall be capable of 
maintaining continuous communication with an individual in each alarm 
station, and vehicle escorts shall maintain continuous communication 
with security personnel. All personnel escorts shall maintain timely 
communication with the security personnel.
    (4) The following continuous communication capabilities must 
terminate in both alarm stations required by this section:
    (i) Radio or microwave transmitted two-way voice communication, 
either directly or through an intermediary, in addition to conventional 
telephone service between local law enforcement authorities and the 
site.
    (ii) A system for communication with the control room.
    (5) Non-portable communications equipment must remain operable from 
independent power sources in the event of the loss of normal power.
    (6) The licensee shall identify site areas where communication could 
be interrupted or cannot be maintained, and shall establish alternative 
communication measures or otherwise account for these areas in 
implementing procedures.
    (k) Response requirements. (1) The licensee shall establish and 
maintain, at all times, properly trained, qualified and equipped 
personnel required to interdict and neutralize threats up to and 
including the design basis threat of radiological sabotage as defined in 
Sec. 73.1, to prevent significant core damage and spent fuel sabotage.
    (2) The licensee shall ensure that all firearms, ammunition, and 
equipment necessary to implement the site security plans and protective 
strategy are in sufficient supply, are in working condition, and are 
readily available for use.
    (3) The licensee shall train each armed member of the security 
organization to prevent or impede attempted acts of radiological 
sabotage by using force sufficient to counter the force directed at that 
person, including the use of deadly force when the armed member of the 
security organization has a reasonable belief that the use of deadly 
force is necessary in self-defense or in the defense of others, or any 
other circumstances as authorized by applicable State or Federal law.
    (4) The licensee shall provide armed response personnel consisting 
of armed responders which may be augmented with armed security officers 
to carry out armed response duties within predetermined time lines 
specified by the site protective strategy.
    (5) Armed responders. (i) The licensee shall determine the minimum 
number of armed responders necessary to satisfy the design requirements 
of Sec. 73.55(b) and implement the protective

[[Page 530]]

strategy. The licensee shall document this number in the security plans.
    (ii) The number of armed responders shall not be less than ten (10).
    (iii) Armed responders shall be available at all times inside the 
protected area and may not be assigned other duties or responsibilities 
that could interfere with their assigned response duties.
    (6) Armed security officers. (i) Armed security officers, designated 
to strengthen onsite response capabilities, shall be onsite and 
available at all times to carry out their assigned response duties.
    (ii) The minimum number of armed security officers designated to 
strengthen onsite response capabilities must be documented in the 
security plans.
    (7) The licensee shall have procedures to reconstitute the 
documented number of available armed response personnel required to 
implement the protective strategy.
    (8) Protective strategy. The licensee shall establish, maintain, and 
implement a written protective strategy in accordance with the 
requirements of this section and part 73, appendix C, Section II. Upon 
receipt of an alarm or other indication of a threat, the licensee shall:
    (i) Determine the existence and level of a threat in accordance with 
pre-established assessment methodologies and procedures.
    (ii) Initiate response actions to interdict and neutralize threats 
in accordance with the requirements of part 73, appendix C, section II, 
the safeguards contingency plan, and the licensee's response strategy.
    (iii) Notify law enforcement agencies (local, State, and Federal law 
enforcement agencies (LLEA)), in accordance with site procedures.
    (9) Law enforcement liaison. To the extent practicable, licensees 
shall document and maintain current agreements with applicable law 
enforcement agencies to include estimated response times and 
capabilities.
    (10) Heightened security. Licensees shall establish, maintain, and 
implement a threat warning system which identifies specific graduated 
protective measures and actions to be taken to increase licensee 
preparedness against a heightened security threat.
    (i) Licensees shall ensure that the specific protective measures and 
actions identified for each threat level are consistent with the 
security plans and other emergency plans and procedures.
    (ii) Upon notification by an authorized representative of the 
Commission, licensees shall implement the specific threat level 
indicated by the Commission representative.
    (l) Facilities using mixed-oxide (MOX) fuel assemblies containing up 
to 20 weight percent plutonium dioxide (PuO2). (1) Commercial nuclear 
power reactors licensed under 10 CFR parts 50 or 52 and authorized to 
use special nuclear material in the form of MOX fuel assemblies 
containing up to 20 weight percent PuO2 shall, in addition to 
meeting the requirements of this section, protect un-irradiated MOX fuel 
assemblies against theft or diversion as described in this paragraph.
    (2) Commercial nuclear power reactors authorized to use MOX fuel 
assemblies containing up to 20 weight percent PuO2 are exempt 
from the requirements of Sec. Sec. 73.20, 73.45, and 73.46 for the 
onsite physical protection of un-irradiated MOX fuel assemblies.
    (3) Administrative controls. (i) The licensee shall describe in the 
security plans the operational and administrative controls to be 
implemented for the receipt, inspection, movement, storage, and 
protection of un-irradiated MOX fuel assemblies.
    (ii) The licensee shall implement the use of tamper-indicating 
devices for un-irradiated MOX fuel assembly transport and shall verify 
their use and integrity before receipt.
    (iii) Upon receipt of un-irradiated MOX fuel assemblies, the 
licensee shall:
    (A) Inspect un-irradiated MOX fuel assemblies for damage.
    (B) Search un-irradiated MOX fuel assemblies for unauthorized 
materials.
    (iv) The licensee may conduct the required inspection and search 
functions simultaneously.
    (v) The licensee shall ensure the proper placement and control of 
un-irradiated MOX fuel assemblies as follows:

[[Page 531]]

    (A) At least one armed security officer shall be present during the 
receipt and inspection of un-irradiated MOX fuel assemblies. This armed 
security officer shall not be an armed responder as required by 
paragraph (k) of this section.
    (B) The licensee shall store un-irradiated MOX fuel assemblies only 
within a spent fuel pool, located within a vital area, so that access to 
the un-irradiated MOX fuel assemblies requires passage through at least 
two physical barriers and the water barrier combined with the additional 
measures detailed in this section.
    (vi) The licensee shall implement a material control and 
accountability program that includes a predetermined and documented 
storage location for each un-irradiated MOX fuel assembly.
    (4) Physical controls. (i) The licensee shall lock, lockout, or 
disable all equipment and power supplies to equipment required for the 
movement and handling of un-irradiated MOX fuel assemblies when movement 
activities are not authorized.
    (ii) The licensee shall implement a two-person, line-of-sight rule 
within the spent fuel pool area whenever control systems or equipment 
required for the movement or handling of un-irradiated MOX fuel 
assemblies must be accessed.
    (iii) The licensee shall conduct random patrols of areas containing 
un-irradiated MOX fuel assemblies to identify indications of tampering 
and ensure the integrity of barriers and locks.
    (iv) Locks, keys, and any other access control device used to secure 
equipment and power sources required for the movement of un-irradiated 
MOX fuel assemblies, or openings to areas containing un-irradiated MOX 
fuel assemblies, must be controlled by the security organization.
    (v) Removal of locks used to secure equipment and power sources 
required for the movement of un-irradiated MOX fuel assemblies or 
openings to areas containing un-irradiated MOX fuel assemblies must 
require approval by both the on-duty security shift supervisor and the 
operations shift manager.
    (A) At least one armed security officer shall be present to observe 
activities involving the movement of un-irradiated MOX fuel assemblies 
before the removal of the locks and providing power to equipment 
required for the movement or handling of un-irradiated MOX fuel 
assemblies.
    (B) At least one armed security officer shall be present at all 
times until power is removed from equipment and locks are secured.
    (C) Security officers shall be knowledgeable of authorized and 
unauthorized activities involving un-irradiated MOX fuel assemblies.
    (5) At least one armed security officer shall be present and shall 
maintain constant surveillance of un-irradiated MOX fuel assemblies when 
the assemblies are not located in the spent fuel pool or reactor.
    (6) The licensee shall maintain at all times the capability to 
detect, assess, interdict and neutralize threats to un-irradiated MOX 
fuel assemblies in accordance with the requirements of this section.
    (7) MOX fuel assemblies containing greater than 20 weight percent 
PuO2. (i) Requests for the use of MOX fuel assemblies 
containing greater than 20 weight percent PuO2 shall be 
reviewed and approved by the Commission before receipt of MOX fuel 
assemblies.
    (ii) Additional measures for the physical protection of un-
irradiated MOX fuel assemblies containing greater than 20 weight percent 
PuO2 shall be determined by the Commission on a case-by-case 
basis and documented through license amendment in accordance with 10 CFR 
50.90.
    (m) Security program reviews. (1) As a minimum the licensee shall 
review each element of the physical protection program at least every 24 
months. Reviews shall be conducted:
    (i) Within 12 months following initial implementation of the 
physical protection program or a change to personnel, procedures, 
equipment, or facilities that potentially could adversely affect 
security.
    (ii) As necessary based upon site-specific analyses, assessments, or 
other performance indicators.
    (iii) By individuals independent of those personnel responsible for 
program management and any individual

[[Page 532]]

who has direct responsibility for implementing the onsite physical 
protection program.
    (2) Reviews of the security program must include, but not limited 
to, an audit of the effectiveness of the physical security program, 
security plans, implementing procedures, cyber security programs, 
safety/security interface activities, the testing, maintenance, and 
calibration program, and response commitments by local, State, and 
Federal law enforcement authorities.
    (3) The results and recommendations of the onsite physical 
protection program reviews, management's findings regarding program 
effectiveness, and any actions taken as a result of recommendations from 
prior program reviews, must be documented in a report to the licensee's 
plant manager and to corporate management at least one level higher than 
that having responsibility for day-to-day plant operations. These 
reports must be maintained in an auditable form and available for 
inspection.
    (4) Findings from onsite physical protection program reviews must be 
entered into the site corrective action program.
    (n) Maintenance, testing, and calibration. (1) The licensee shall:
    (i) Establish, maintain, and implement a maintenance, testing and 
calibration program to ensure that security systems and equipment, 
including secondary and uninterruptible power supplies, are tested for 
operability and performance at predetermined intervals, maintained in 
operable condition, and are capable of performing their intended 
functions.
    (ii) Describe the maintenance, testing and calibration program in 
the physical security plan. Implementing procedures must specify 
operational and technical details required to perform maintenance, 
testing, and calibration activities to include, but not limited to, 
purpose of activity, actions to be taken, acceptance criteria, and the 
intervals or frequency at which the activity will be performed.
    (iii) Identify in procedures the criteria for determining when 
problems, failures, deficiencies, and other findings are documented in 
the site corrective action program for resolution.
    (iv) Ensure that information documented in the site corrective 
action program is written in a manner that does not constitute 
safeguards information as defined in 10 CFR 73.21.
    (v) Implement compensatory measures that ensure the effectiveness of 
the onsite physical protection program when there is a failure or 
degraded operation of security-related components or equipment.
    (2) The licensee shall test each intrusion alarm for operability at 
the beginning and end of any period that it is used for security, or if 
the period of continuous use exceeds seven (7) days. The intrusion alarm 
must be tested at least once every seven (7) days.
    (3) Intrusion detection and access control equipment must be 
performance tested in accordance with the security plans and 
implementing procedures.
    (4) Equipment required for communications onsite must be tested for 
operability not less frequently than once at the beginning of each 
security personnel work shift.
    (5) Communication systems between the alarm stations and each 
control room, and between the alarm stations and local law enforcement 
agencies, to include backup communication equipment, must be tested for 
operability at least once each day.
    (6) Search equipment must be tested for operability at least once 
each day and tested for performance at least once during each seven (7) 
day period.
    (7) A program for testing or verifying the operability of devices or 
equipment located in hazardous areas must be specified in the 
implementing procedures and must define alternate measures to be taken 
to ensure the timely completion of testing or maintenance when the 
hazardous condition or other restrictions are no longer applicable.
    (8) Security equipment or systems shall be tested in accordance with 
the site maintenance, testing and calibration procedures before being 
placed back in service after each repair or inoperable state.

[[Page 533]]

    (o) Compensatory measures. (1) The licensee shall identify criteria 
and measures to compensate for degraded or inoperable equipment, 
systems, and components to meet the requirements of this section.
    (2) Compensatory measures must provide a level of protection that is 
equivalent to the protection that was provided by the degraded or 
inoperable, equipment, system, or components.
    (3) Compensatory measures must be implemented within specific time 
frames necessary to meet the requirements stated in paragraph (b) of 
this section and described in the security plans.
    (p) Suspension of security measures. (1) The licensee may suspend 
implementation of affected requirements of this section under the 
following conditions:
    (i) In accordance with Sec. Sec. 50.54(x) and 50.54(y) of this 
chapter, the licensee may suspend any security measures under this 
section in an emergency when this action is immediately needed to 
protect the public health and safety and no action consistent with 
license conditions and technical specifications that can provide 
adequate or equivalent protection is immediately apparent. This 
suspension of security measures must be approved as a minimum by a 
licensed senior operator before taking this action.
    (ii) During severe weather when the suspension of affected security 
measures is immediately needed to protect the personal health and safety 
of security force personnel and no other immediately apparent action 
consistent with the license conditions and technical specifications can 
provide adequate or equivalent protection. This suspension of security 
measures must be approved, as a minimum, by a licensed senior operator, 
with input from the security supervisor or manager, before taking this 
action.
    (2) Suspended security measures must be reinstated as soon as 
conditions permit.
    (3) The suspension of security measures must be reported and 
documented in accordance with the provisions of Sec. 73.71.
    (q) Records. (1) The Commission may inspect, copy, retain, and 
remove all reports, records, and documents required to be kept by 
Commission regulations, orders, or license conditions, whether the 
reports, records, and documents are kept by the licensee or a 
contractor.
    (2) The licensee shall maintain all records required to be kept by 
Commission regulations, orders, or license conditions, until the 
Commission terminates the license for which the records were developed, 
and shall maintain superseded portions of these records for at least 
three (3) years after the record is superseded, unless otherwise 
specified by the Commission.
    (3) If a contracted security force is used to implement the onsite 
physical protection program, the licensee's written agreement with the 
contractor must be retained by the licensee as a record for the duration 
of the contract.
    (4) Review and audit reports must be maintained and available for 
inspection, for a period of three (3) years.
    (r) Alternative measures. (1) The Commission may authorize an 
applicant or licensee to provide a measure for protection against 
radiological sabotage other than one required by this section if the 
applicant or licensee demonstrates that:
    (i) The measure meets the same performance objectives and 
requirements specified in paragraph (b) of this section; and
    (ii) The proposed alternative measure provides protection against 
radiological sabotage or theft of un-irradiated MOX fuel assemblies, 
equivalent to that which would be provided by the specific requirement 
for which it would substitute.
    (2) The licensee shall submit proposed alternative measure(s) to the 
Commission for review and approval in accordance with Sec. Sec. 50.4 
and 50.90 of this chapter before implementation.
    (3) In addition to fully describing the desired changes, the 
licensee shall submit a technical basis for each proposed alternative 
measure. The basis must include an analysis or assessment that 
demonstrates how the proposed alternative measure provides a level of 
protection that is at least equal to that which would otherwise be 
provided by the specific requirement of this section.

[[Page 534]]

    (4) Alternative vehicle barrier systems. In the case of vehicle 
barrier systems required by Sec. 73.55(e)(10), the licensee shall 
demonstrate that:
    (i) The alternative measure provides protection against the use of a 
vehicle as a means of transportation to gain proximity to vital areas;
    (ii) The alternative measure provides protection against the use of 
a vehicle as a vehicle bomb; and
    (iii) Based on comparison of the costs of the alternative measures 
to the costs of meeting the Commission's requirements using the 
essential elements of 10 CFR 50.109, the costs of fully meeting the 
Commission's requirements are not justified by the protection that would 
be provided.

[74 FR 13971, Mar. 27, 2009, as amended at 77 FR 39909, July 6, 2012]



Sec. 73.56  Personnel access authorization requirements for nuclear
power plants.

    (a) Introduction. (1) By March 31, 2010, each nuclear power reactor 
licensee, licensed under 10 CFR part 50, shall implement the 
requirements of this section through revisions to its Commission-
approved Physical Security Plan.
    (2) The licensee shall establish, implement and maintain its access 
authorization program in accordance with the requirements of this 
section.
    (3) Each applicant for an operating license under the provisions of 
part 50 of this chapter, and each holder of a combined license under the 
provisions of part 52 of this chapter, shall implement the requirements 
of this section before fuel is allowed on site (protected area).
    (4) The licensee or applicant may accept, in part or whole, an 
access authorization program implemented by a contractor or vendor to 
satisfy appropriate elements of the licensee's access authorization 
program in accordance with the requirements of this section. Only a 
licensee shall grant an individual unescorted access. Licensees and 
applicants shall certify individuals' unescorted access authorization 
and are responsible to maintain, deny, terminate, or withdraw unescorted 
access authorization.
    (b) Applicability. (1) The following individuals shall be subject to 
an access authorization program:
    (i) Any individual to whom a licensee intends to grant unescorted 
access to nuclear power plant protected or vital areas or any individual 
for whom a licensee or an applicant intends to certify unescorted access 
authorization;
    (ii) Any individual whose duties and responsibilities permit the 
individual to take actions by electronic means, either on site or 
remotely, that could adversely impact the licensee's or applicant's 
operational safety, security, or emergency preparedness;
    (iii) Any individual who has responsibilities for implementing a 
licensee's or applicant's protective strategy, including, but not 
limited to, armed security force officers, alarm station operators, and 
tactical response team leaders; and
    (iv) The licensee or applicant access authorization program 
reviewing official or contractor or vendor access authorization program 
reviewers.
    (2) Other individuals, at the licensee's or applicant's discretion, 
including employees of a contractor or a vendor who are designated in 
access authorization program procedures, are subject to an access 
authorization program that meets the requirements of this section.
    (c) General performance objective. The licensee's or applicant's 
access authorization program must provide high assurance that the 
individuals who are specified in paragraph (b)(1), and, if applicable, 
paragraph (b)(2) of this section are trustworthy and reliable, such that 
they do not constitute an unreasonable risk to public health and safety 
or the common defense and security, including the potential to commit 
radiological sabotage.
    (d) Background investigation. In order to grant an individual 
unescorted access to the protected area or vital area of a nuclear power 
plant or certify an individual unescorted access authorization, 
licensees, applicants and contractors or vendors shall ensure that the 
individual has been subject to a background investigation. The 
background investigation must include, but is not limited to, the 
following elements:
    (1) Informed consent. Licensees, applicants, and contractors or 
vendors shall

[[Page 535]]

not initiate any element of a background investigation without the 
informed and signed consent of the subject individual. This consent 
shall include authorization to share personal information with 
appropriate entities. The licensee or applicant to whom the individual 
is applying for unescorted access and unescorted access authorization, 
respectively, or the contractors or vendors supporting the licensee or 
applicant shall inform the individual of his or her right to review 
information collected to assure its accuracy, and provide the individual 
with an opportunity to correct any inaccurate or incomplete information 
that is developed by licensees, applicants, or contractors or vendors 
about the individual.
    (i) The subject individual may withdraw his or her consent at any 
time. Licensees, applicants, and contractors or vendors shall inform the 
individual that:
    (A) Withdrawal of his or her consent will remove the individual's 
application for access authorization under the licensee's or applicant's 
access authorization program or contractor or vendor access 
authorization program; and
    (B) Other licensees and applicants shall have access to information 
documenting the withdrawal. Additionally, the contractors or vendors may 
have the same access to the information, if such information is 
necessary for assisting licensees or applicants complying with 
requirements set forth in this section.
    (ii) If an individual withdraws his or her consent, licensees, 
applicants, and contractors or vendors may not initiate any elements of 
the background investigation that were not in progress at the time the 
individual withdrew his or her consent, but shall complete any 
background investigation elements that are in progress at the time 
consent is withdrawn. The licensee or applicant shall record the status 
of the individual's application for unescorted access or unescorted 
access authorization, respectively. Contractors or vendors may record 
the status of the individual's application for unescorted access or 
unescorted access authorization for licensees or applicants. 
Additionally, licensees, applicants, or contractors or vendors shall 
collect and maintain the individual's application for unescorted access 
or unescorted access authorization; his or her withdrawal of consent for 
the background investigation; the reason given by the individual for the 
withdrawal; and any pertinent information collected from the background 
investigation elements that were completed. This information must be 
shared with other licensees in accordance with paragraph (o)(6) of this 
section.
    (iii) Licensees, applicants, and contractors or vendors shall 
inform, in writing, any individual who is applying for unescorted access 
or unescorted access authorization that the following actions are 
sufficient cause for denial or unfavorable termination of unescorted 
access or unescorted access authorization status:
    (A) Refusal to provide a signed consent for the background 
investigation;
    (B) Refusal to provide, or the falsification of, any personal 
history information required under this section, including the failure 
to report any previous denial or unfavorable termination of unescorted 
access or unescorted access authorization;
    (C) Refusal to provide signed consent for the sharing of personal 
information with other licensees, applicants, or the contractor or 
vendors under paragraph (d)(4)(v) of this section; or
    (D) Failure to report any arrests or legal actions specified in 
paragraph (g) of this section.
    (2) Personal history disclosure. (i) Any individual who is applying 
for unescorted access or unescorted access authorization shall disclose 
the personal history information that is required by the licensee's or 
applicant's access authorization program, including any information that 
may be necessary for the reviewing official to make a determination of 
the individual's trustworthiness and reliability.
    (ii) Licensees, applicants, and contractors or vendors shall not 
require an individual to disclose an administrative withdrawal of 
unescorted access or unescorted access authorization under the 
requirements of Sec. 73.56(g), (h)(7), or (i)(1)(v) of this section. 
However, the

[[Page 536]]

individual must disclose this information if the individual's unescorted 
access or unescorted access authorization is administratively withdrawn 
at the time he or she is seeking unescorted access or unescorted access 
authorization, or the individual's unescorted access or unescorted 
access authorization was subsequently denied or terminated unfavorably 
by a licensee, applicant, or contractor or vendor.
    (3) Verification of true identity. Licensees, applicants, and 
contractors or vendors shall verify the true identity of an individual 
who is applying for unescorted access or unescorted access authorization 
in order to ensure that the applicant is the person that he or she has 
claimed to be. At a minimum, licensees, applicants, and contractors or 
vendors shall validate that the social security number that the 
individual has provided is his or hers, and, in the case of foreign 
nationals, validate the claimed non-immigration status that the 
individual has provided is correct. In addition, licensees and 
applicants shall also determine whether the results of the 
fingerprinting required under Sec. 73.57 confirm the individual's 
claimed identity, if such results are available.
    (4) Employment history evaluation. Licensees, applicants, and 
contractors or vendors shall ensure that an employment history 
evaluation has been completed on a best effort basis, by questioning the 
individual's present and former employers, and by determining the 
activities of the individual while unemployed.
    (i) For the claimed employment period, the individual must provide 
the reason for any termination, eligibility for rehire, and other 
information that could reflect on the individual's trustworthiness and 
reliability.
    (ii) If the claimed employment was military service the individual 
shall provide a characterization of service, reason for separation, and 
any disciplinary actions that could affect a trustworthiness and 
reliability determination.
    (iii) If education is claimed in lieu of employment, the individual 
shall provide any information related to the claimed education that 
could reflect on the individual's trustworthiness and reliability and, 
at a minimum, verify that the individual was registered for the classes 
and received grades that indicate that the individual participated in 
the educational process during the claimed period.
    (iv) If a previous employer, educational institution, or any other 
entity with which the individual claims to have been engaged fails to 
provide information or indicates an inability or unwillingness to 
provide information within 3 business days of the request, the licensee, 
applicant, or contractor or vendor shall:
    (A) Document this refusal or unwillingness in the licensee's, 
applicant's, or contractor's or vendor's record of the investigation; 
and
    (B) Obtain a confirmation of employment, educational enrollment and 
attendance, or other form of engagement claimed by the individual from 
at least one alternate source that has not been previously used.
    (v) When any licensee, applicant, contractor, or vendor is seeking 
the information required for an unescorted access or unescorted access 
authorization decision under this section and has obtained a signed 
release from the subject individual authorizing the disclosure of such 
information, other licensees, applicants, contractors and vendors shall 
make available the personal or access authorization information 
requested regarding the denial or unfavorable termination of unescorted 
access or unescorted access authorization.
    (vi) In conducting an employment history evaluation, the licensee, 
applicant, contractor, or vendor may obtain information and documents by 
electronic means, including, but not limited to, telephone, facsimile, 
or e-mail. Licensees, applicants, contractors, or vendors shall make a 
record of the contents of the telephone call and shall retain that 
record, and any documents or electronic files obtained electronically, 
in accordance with paragraph (o) of this section.
    (5) Credit history evaluation. Licensees, applicants, contractors 
and vendors shall ensure that the full credit history of any individual 
who is applying for unescorted access or unescorted access authorization 
is evaluated. A

[[Page 537]]

full credit history evaluation must include, but is not limited to, an 
inquiry to detect potential fraud or misuse of social security numbers 
or other financial identifiers, and a review and evaluation of all of 
the information that is provided by a national credit-reporting agency 
about the individual's credit history. For individuals including foreign 
nationals and United States citizens who have resided outside the United 
States and do not have established credit history that covers at least 
the most recent seven years in the United States, the licensee, 
applicant, contractor or vendor must document all attempts to obtain 
information regarding the individual's credit history and financial 
responsibility from some relevant entity located in that other country 
or countries.
    (6) Character and reputation evaluation. Licensees, applicants, 
contractors, and vendors shall ascertain the character and reputation of 
an individual who has applied for unescorted access or unescorted access 
authorization by conducting reference checks. Reference checks may not 
be conducted with any person who is known to be a close member of the 
individual's family, including but not limited to, the individual's 
spouse, parents, siblings, or children, or any individual who resides in 
the individual's permanent household. The reference checks must focus on 
the individual's reputation for trustworthiness and reliability.
    (7) Criminal history review. The licensee's or applicant's reviewing 
official shall evaluate the entire criminal history record of an 
individual who is applying for unescorted access or unescorted access 
authorization to determine whether the individual has a record of 
criminal activity that may adversely impact his or her trustworthiness 
and reliability. A criminal history record must be obtained in 
accordance with the requirements of Sec. 73.57. For individuals who do 
not have or are not expected to have unescorted access, a criminal 
history record of the individual shall be obtained in accordance with 
the requirements set forth in paragraph (k)(1)(ii) of this section.
    (e) Psychological assessment. In order to assist in determining an 
individual's trustworthiness and reliability, licensees, applicants, 
contractors or vendors shall ensure that a psychological assessment has 
been completed before the individual is granted unescorted access or 
certified unescorted access authorization. Individuals who are applying 
for initial unescorted access or unescorted access authorization, or who 
have not maintained unescorted access or unescorted access authorization 
for greater than 365 days, shall be subject to a psychological 
assessment. The psychological assessment must be designed to evaluate 
the possible adverse impact of any noted psychological characteristics 
on the individual's trustworthiness and reliability.
    (1) A licensed psychologist or psychiatrist with the appropriate 
training and experience shall conduct the psychological assessment.
    (2) The psychological assessment must be conducted in accordance 
with the applicable ethical principles for conducting such assessments 
established by the American Psychological Association or American 
Psychiatric Association.
    (3) At a minimum, the psychological assessment must include the 
administration and interpretation of a standardized, objective, 
professionally-accepted psychological test that provides information to 
identify indications of disturbances in personality or psychopathology 
that may have adverse implications for an individual's trustworthiness 
and reliability. A psychiatrist or psychologist specified in paragraph 
(e) of this section shall establish the predetermined thresholds for 
each scale, in accordance with paragraph (e)(2) of this section, that 
must be applied in interpreting the results of the psychological test to 
determine whether an individual must be interviewed by a licensed 
psychiatrist or psychologist, under Sec. 73.56(e)(4)(i) of this 
section.
    (4) The psychological assessment must include a clinical interview:
    (i) If an individual's scores on the psychological test in paragraph 
(e)(3) of this section identify indications of disturbances in 
personality or psychopathology that may have implications for an 
individual's trustworthiness and reliability; or
    (ii) If the individual is a member of the population that performs 
one or

[[Page 538]]

more job functions that are critical to the safe and secure operation of 
the licensee's facility, as defined in paragraph (i)(1)(v)(B) of this 
section.
    (5) In the course of conducting a psychological assessment for those 
individuals who are specified in paragraph (h) of this section for 
initial unescorted access or unescorted access authorization category, 
if the licensed psychologist or psychiatrist identifies or discovers any 
information, including a medical condition, that could adversely impact 
the individual's fitness for duty or trustworthiness and reliability, 
the licensee, applicant, or contractor or vendor shall ensure that the 
psychologist or psychiatrist contact appropriate medical personnel to 
obtain further information as need for a determination. The results of 
the evaluation and a recommendation shall be provided to the licensee's 
or applicant's reviewing official.
    (6) During psychological reassessments, if the licensed psychologist 
or psychiatrist identifies or discovers any information, including a 
medical condition, that could adversely impact the fitness for duty or 
trustworthiness and reliability of those individuals who are currently 
granted unescorted access or certified unescorted access authorization 
status, he or she shall inform (1) the reviewing official of the 
discovery within 24 hours of the discovery and (2) the medical personnel 
designated in the site implementing procedures, who shall ensure that an 
appropriate evaluation of the possible medical condition is conducted 
under the requirements of part 26 of this chapter. The results of the 
evaluation and a recommendation shall be provided to the licensee's or 
applicant's reviewing official.
    (f) Behavioral observation. (1) Licensee and applicant access 
authorization programs must include a behavioral observation program 
that is designed to detect behaviors or activities that may constitute 
an unreasonable risk to the health and safety of the public and common 
defense and security, including a potential threat to commit 
radiological sabotage. Licensees, applicants and contractors or vendors 
must ensure that the individuals specified in paragraph (b)(1) and, if 
applicable, (b)(2) of this section are subject to behavioral 
observation.
    (2) Each person subject to the behavior observation program shall be 
responsible for communicating to the licensee or applicant observed 
behaviors of individuals subject to the requirements of this section. 
Such behaviors include any behavior of individuals that may adversely 
affect the safety or security of the licensee's facility or that may 
constitute an unreasonable risk to the public health and safety or the 
common defense and security, including a potential threat to commit 
radiological sabotage.
    (i) Licensees, applicants, and contractors or vendors shall ensure 
that individuals who are subject to this section also successfully 
complete initial behavioral observation training and requalification 
behavior observation training as required in paragraphs (f)(2)(ii) and 
(iii) of this section.
    (ii) Behavioral observation training must be:
    (A) Completed before the licensee grants unescorted access or 
certifies unescorted access authorization or an applicant certifies 
unescorted access authorization, as defined in paragraph (h)(4)(ii) of 
this section,
    (B) Current before the licensee grants unescorted access update or 
reinstatement or licensee or applicant certifies unescorted access 
authorization reinstatement as defined in paragraph (h)(4)(ii) of this 
section, and
    (C) Maintained in a current status during any period of time an 
individual possesses unescorted access or unescorted access 
authorization in accordance with paragraph (f)(2)(iv) of this section.
    (iii) For initial behavioral observation training, individuals shall 
demonstrate completion by passing a comprehensive examination that 
addresses the knowledge and abilities necessary to detect behavior or 
activities that have the potential to constitute an unreasonable risk to 
the health and safety of the public and common defense and security, 
including a potential threat to commit radiological sabotage. Remedial 
training and re-testing are required for individuals who fail to 
satisfactorily complete the examination.

[[Page 539]]

    (iv) Individuals shall complete refresher training on a nominal 12-
month frequency, or more frequently where the need is indicated. 
Individuals may take and pass a comprehensive examination that meets the 
requirements of paragraph (f)(2)(iii) of this section in lieu of 
completing annual refresher training.
    (v) Initial and refresher training may be delivered using a variety 
of media, including, but not limited to, classroom lectures, required 
reading, video, or computer-based training systems. The licensee, 
applicant, or contractor or vendor shall monitor the completion of 
training.
    (3) Individuals who are subject to an access authorization program 
under this section shall at a minimum, report any concerns arising from 
behavioral observation, including, but not limited to, concerns related 
to any questionable behavior patterns or activities of others to the 
reviewing official, his or her supervisor, or other management personnel 
designated in their site procedures. The recipient of the report shall, 
if other than the reviewing official, promptly convey the report to the 
reviewing official, who shall reassess the reported individual's 
unescorted access or unescorted access authorization status. The 
reviewing official shall determine the elements of the reassessment 
based on the accumulated information of the individual. If the reviewing 
official has a reason to believe that the reported individual's 
trustworthiness or reliability is questionable, the reviewing official 
shall either administratively withdraw or terminate the individual's 
unescorted access or unescorted access authorization while completing 
the re-evaluation or investigation. If the reviewing official determines 
from the information provided that there is cause for additional action, 
the reviewing official may inform the supervisor of the reported 
individual.
    (g) Self-reporting of legal actions. (1) Any individual who has 
applied for unescorted access or unescorted access authorization or is 
maintaining unescorted access or unescorted access authorization under 
this section shall promptly report to the reviewing official, his or her 
supervisor, or other management personnel designated in site procedures 
any legal action(s) taken by a law enforcement authority or court of law 
to which the individual has been subject that could result in 
incarceration or a court order or that requires a court appearance, 
including but not limited to an arrest, an indictment, the filing of 
charges, or a conviction, but excluding minor civil actions or 
misdemeanors such as parking violations or speeding tickets. The 
recipient of the report shall, if other than the reviewing official, 
promptly convey the report to the reviewing official. On the day that 
the report is received, the reviewing official shall evaluate the 
circumstances related to the reported legal action(s) and re-determine 
the reported individual's unescorted access or unescorted access 
authorization status.
    (2) The licensee or applicant shall inform the individual of this 
obligation, in writing, prior to granting unescorted access or 
certifying unescorted access authorization.
    (h) Granting unescorted access and certifying unescorted access 
authorization. Licensees and applicants shall implement the requirements 
of this paragraph for granting or certifying initial or reinstated 
unescorted access or unescorted access authorization. The investigatory 
information collected to satisfy the requirements of this section for 
individuals who are being considered for unescorted access or unescorted 
access authorization shall be valid for a trustworthiness and 
reliability determination by a licensee or applicant for 30 calendar 
days.
    (1) Determination basis. (i) The licensee's or applicant's reviewing 
official shall determine whether to grant, certify, deny, unfavorably 
terminate, maintain, or administratively withdraw an individual's 
unescorted access or unescorted access authorization status, based on an 
evaluation of all of the information required by this section.
    (ii) The licensee's or applicant's reviewing official may not grant 
unescorted access or certify unescorted access authorization status to 
an individual until all of the information required by this section has 
been evaluated by the reviewing official and the reviewing official has 
determined that

[[Page 540]]

the accumulated information supports a determination of the individual's 
trustworthiness and reliability. However, the reviewing official may 
deny or terminate unescorted access or unescorted access authorization 
of any individual based on disqualifying information even if not all the 
information required by this section has been collected or evaluated.
    (2) Unescorted access for NRC-certified personnel. Licensees and 
applicants shall grant unescorted access to any individual who has been 
certified by the Nuclear Regulatory Commission as suitable for such 
access.
    (3) Access denial. Licensees or applicants may not permit an 
individual, who is identified as having an access-denied status by 
another licensee subject to this section, or has an access authorization 
status other than favorably terminated, to enter any nuclear power plant 
protected area or vital area, under escort or otherwise, or take actions 
by electronic means that could adversely impact the licensee's or 
applicant's safety, security, or emergency response or their facilities, 
under supervision or otherwise, except upon completion of the initial 
unescorted access authorization process.
    (4) Granting unescorted access and certifying unescorted access 
authorization--(i) Initial unescorted access or unescorted access 
authorization. In satisfying the requirements of paragraph (h)(1) of 
this section, for individuals who have never held unescorted access or 
unescorted access authorization status or whose unescorted access or 
unescorted access authorization status has been interrupted for a period 
of 3 years or more, the licensee, applicant, or contractor or vendor 
shall satisfy the requirements of paragraphs (d), (e), (f), and (g) of 
this section. In meeting requirements set forth in paragraph (d)(4) of 
this section, the licensee, applicant, or contractor or vendor shall 
evaluate the 3 years before the date on which the application for 
unescorted access was submitted, or since the individual's eighteenth 
birthday, whichever is shorter. For the 1-year period preceding the date 
upon which the individual applies for unescorted access or unescorted 
access authorization, the licensee, applicant or contractor or vendor 
shall ensure that the employment history evaluation is conducted with 
every employer, regardless of the length of employment. For the 
remaining 2-year period, the licensee, applicant, or contractor or 
vendor shall ensure that the employment history evaluation is conducted 
with the employer by whom the individual claims to have been employed 
the longest within each calendar month.
    (ii) Interruption of unescorted access or unescorted access 
authorization. In satisfying the requirements of paragraph (h)(1) of 
this section, for individuals who have previously been granted 
unescorted access or unescorted access authorization, but whose access 
had been terminated under favorable conditions, licensees, applicants or 
contractors or vendors shall satisfy the requirements of paragraphs (d), 
(e), (f), and (g) of this section, with consideration of the specific 
requirements for periods of interruption described below in paragraphs 
(h)(4)(ii)(A) or (h)(4)(ii)(B) of this section, as applicable. However, 
for individuals whose unescorted access or unescorted access 
authorization was interrupted for less than or equal to 30 calendar 
days, licensees, applicants, or contractors or vendors must only satisfy 
the requirements set forth in paragraphs (d)(1), (d)(2), and (d)(3) of 
this section. The applicable periods of interruption are determined by 
the number of calendar days between the day after the individual's 
access was terminated and the day upon which the individual applies for 
unescorted access or unescorted access authorization.
    (A) Update of unescorted access or unescorted access authorization. 
For individuals whose last unescorted access or unescorted access 
authorization status has been interrupted for more than 30 calendar days 
but less than or equal to 365 calendar days, the licensee, applicant or 
contractor or vendor shall complete the individual's employment history 
evaluation in accordance with the requirements of paragraph (d)(4) of 
this section, within 5 business days after reinstatement. The licensee, 
applicant, or contractor or vendor shall ensure that the employment 
history evaluation has been conducted with the employer by whom the 
individual

[[Page 541]]

claims to have been employed the longest within the calendar month. 
However, if the employment history evaluation is not completed within 5 
business days of reinstatement due to circumstances that are outside of 
the licensee's, applicant's, or contractor's or vendor's control and the 
licensee or applicant, contractor or vendor is not aware of any 
potentially disqualifying information regarding the individual within 
the past 5 years, the licensee may extend the individual's unescorted 
access an additional 5 business days. If the employment history 
evaluation is not completed within this extended 5 business days, the 
licensee shall administratively withdraw unescorted access and complete 
the employment history evaluation in accordance with Sec. 73.56(d)(4) 
of this section. For re-certification of unescorted access 
authorization, prior to re-certification of unescorted access 
authorization status of an individual, the licensee or applicant shall 
complete all the elements stated above including drug screening and 
employment evaluation.
    (B) Reinstatement of unescorted access or unescorted access 
authorization. For individuals whose last unescorted access or 
unescorted access authorization status has been interrupted for greater 
than 365 calendar days but fewer than 3 years the licensee, applicant or 
contractor or vendor shall evaluate the period of time since the 
individual last held unescorted access or unescorted access 
authorization status, up to and including the day the individual applies 
for re-instated unescorted access authorization. For the 1-year period 
preceding the date upon which the individual applies for unescorted 
access authorization, the licensee, applicant, or contractor or vendor 
shall ensure that the employment history evaluation is conducted with 
every employer, regardless of the length of employment. For the 
remaining period, the licensee, applicant or contractor or vendor shall 
ensure that the employment history evaluation is conducted with the 
employer by whom the individual claims to have been employed the longest 
within each calendar month. In addition, the individual shall be subject 
to the psychological assessment required in Sec. 73.56(e).
    (5) Accepting unescorted access authorization from other access 
authorization programs. Licensees who are seeking to grant unescorted 
access or certify unescorted access authorization or applicants who are 
seeking to certify unescorted access authorization to an individual who 
is subject to another access authorization program or another access 
authorization program that complies with this section may rely on those 
access authorization programs or access authorization program elements 
to comply with the requirements of this section. However, the licensee 
who is seeking to grant unescorted access or the licensee or applicant 
who is seeking to certify unescorted access authorization shall ensure 
that the program elements to be accepted have been maintained consistent 
with the requirements of this section by the other access authorization 
program.
    (6) Information sharing. To meet the requirements of this section, 
licensees, applicants, and contractors or vendors may rely upon the 
information that other licensees, applicants, and contractors or vendors 
who are also subject to this section, have gathered about individuals 
who have previously applied for unescorted access or unescorted access 
authorization, and developed about individuals during periods in which 
the individuals maintained unescorted access or unescorted access 
authorization status.
    (i) Maintaining unescorted access or unescorted access 
authorization.
    (1) Individuals may maintain unescorted access or unescorted access 
authorization status under the following conditions:
    (i) The individual remains subject to a behavioral observation 
program that complies with the requirements of Sec. 73.56(f) of this 
section.
    (ii) The individual successfully completes behavioral observation 
refresher training or testing on the nominal 12-month frequency required 
in Sec. 73.56(f)(2)(ii) of this section.
    (iii) The individual complies with the licensee's or applicant's 
access authorization program policies and procedures to which he or she 
is subject, including the self-reporting of legal actions responsibility 
specified in paragraph (g) of this section.

[[Page 542]]

    (iv) The individual is subject to an annual (within 365 calendar 
days) supervisory review conducted in accordance with the requirements 
of the licensee's or applicant's behavioral observation program. The 
individual shall be subject to a supervisory interview in accordance 
with the requirements of the licensee's or applicant's behavioral 
observation program, if the supervisor does not have the frequent 
interaction with the individual throughout the review period needed to 
form an informed and reasonable opinion regarding the individual's 
behavior, trustworthiness, and reliability.
    (v) The licensee's or applicant's reviewing official determines that 
the individual continues to be trustworthy and reliable. This 
determination must, at a minimum, be based on the following:
    (A) A criminal history update and credit history re-evaluation for 
any individual with unescorted access. The criminal history update and 
credit history re-evaluation must be completed within 5 years of the 
date on which these elements were last completed.
    (B) For individuals who perform one or more of the job functions 
described in this paragraph, the trustworthiness and reliability 
determination must be based on a criminal history update and credit 
history re-evaluation within three years of the date on which these 
elements were last completed, or more frequently, based on job 
assignment as determined by the licensee or applicant, and a 
psychological re-assessment within 5 years of the date on which this 
element was last completed:
    (1) Individuals who have extensive knowledge of defensive strategies 
and design and/or implementation of the plant's defense strategies, 
including--
    (i) Site security supervisors;
    (ii) Site security managers;
    (iii) Security training instructors; and
    (iv) Corporate security managers;
    (2) Individuals in a position to grant an applicant unescorted 
access or unescorted access authorization, including site access 
authorization managers;
    (3) Individuals assigned a duty to search for contraband or other 
items that could be used to commit radiological sabotage (i.e., weapons, 
explosives, incendiary devices);
    (4) Individuals who have access, extensive knowledge, or 
administrative control over plant digital computer and communication 
systems and networks as identified in Sec. 73.54, including--
    (i) Plant network systems administrators;
    (ii) IT personnel who are responsible for securing plant networks; 
or
    (5) Individuals qualified for and assigned duties as: armed security 
officers, armed responders, alarm station operators, response team 
leaders, and armorers as defined in the licensee's or applicant's 
Physical Security Plan; and reactor operators, senior reactor operators 
and non-licensed operators. Non-licensed operators include those 
individuals responsible for the operation of plant systems and 
components, as directed by a reactor operator or senior reactor 
operator. A non-licensed operator also includes individuals who monitor 
plant instrumentation and equipment and principally perform their duties 
outside of the control room.
    (C) The criminal history update and the credit history re-evaluation 
shall be completed within 30 calendar days of each other.
    (vi) If the criminal history update, credit history re-evaluation, 
psychological re-assessment, if required, and supervisory review and 
interview, if applicable, have not been completed and the information 
evaluated by the reviewing official within the time frame specified 
under paragraph (v) of this section, the licensee or applicant shall 
administratively withdraw the individual's unescorted access or 
unescorted access authorization until these requirements have been met.
    (2) If an individual who has unescorted access or unescorted access 
authorization status is not subject to an access authorization program 
that meets the requirements of this part for more than 30 continuous 
days, then the licensee or applicant shall terminate the individual's 
unescorted access or unescorted access authorization status

[[Page 543]]

and the individual shall meet the requirements in this section, as 
applicable, to regain unescorted access or unescorted access 
authorization.
    (j) Access to vital areas. Licensees or applicants shall establish, 
implement, and maintain a list of individuals who are authorized to have 
unescorted access to specific nuclear power plant vital areas during 
non-emergency conditions. The list must include only those individuals 
who have a continued need for access to those specific vital areas in 
order to perform their duties and responsibilities. The list must be 
approved by a cognizant licensee or applicant manager or supervisor who 
is responsible for directing the work activities of the individual who 
is granted unescorted access to each vital area, and updated and re-
approved no less frequently than every 31 days.
    (k) Trustworthiness and reliability of background screeners and 
access authorization program personnel. Licensees, applicants, and 
contractors or vendors shall ensure that any individual who collects, 
processes, or has access to personal information that is used to make 
unescorted access or unescorted access authorization determinations 
under this section has been determined to be trustworthy and reliable.
    (1) Background screeners. Licensees, applicants, and contractors or 
vendors who rely on individuals who are not directly under their control 
to collect and process information that will be used by a reviewing 
official to make unescorted access or unescorted access authorization 
determinations shall ensure that a trustworthiness and reliability 
evaluation of such individuals has been completed to support a 
determination that such individuals are trustworthy and reliable. At a 
minimum, the following checks are required:
    (i) Verify the individual's true identity as specified in paragraph 
(d)(3) of this section;
    (ii) A local criminal history review and evaluation based on 
information obtained from an appropriate State or local court or agency 
in which the individual resided;
    (iii) A credit history review and evaluation;
    (iv) An employment history review and evaluation covering the past 3 
years; and
    (v) An evaluation of character and reputation.
    (2) Access authorization program personnel. Licensees, applicants, 
and contractors or vendors shall ensure that any individual who 
evaluates personal information for the purpose of processing 
applications for unescorted access or unescorted access authorization, 
including but not limited to a psychologist or psychiatrist who conducts 
psychological assessments under Sec. 73.56(e), has access to the files, 
records, and personal information associated with individuals who have 
applied for unescorted access or unescorted access authorization, or is 
responsible for managing any databases that contain such files, records, 
and personal information has been determined to be trustworthy and 
reliable, as follows:
    (i) The individual is subject to an access authorization program 
that meets the requirements of this section; or
    (ii) The licensee, applicant, and contractor or vendor determines 
that the individual is trustworthy and reliable based upon an evaluation 
that meets the requirements of Sec. 73.56(d)(1) through (d)(6) and (e) 
and either a local criminal history review and evaluation as specified 
in Sec. 73.56(k)(1)(ii) or a criminal history check that meets the 
requirements of Sec. 73.56(d)(7).
    (l) Review procedures. Each licensee and applicant shall include a 
procedure for the notification of individuals who are denied unescorted 
access, unescorted access authorization, or who are unfavorably 
terminated. Additionally, procedures must include provisions for the 
review, at the request of the affected individual, of a denial or 
unfavorable termination of unescorted access or unescorted access 
authorization that may adversely affect employment. The procedure must 
contain a provision to ensure the individual is informed of the grounds 
for the denial or unfavorable termination and allow the individual an 
opportunity to provide additional relevant information and an 
opportunity for an objective review of the information upon which the 
denial or unfavorable termination of

[[Page 544]]

unescorted access or unescorted access authorization was based. The 
procedure must provide for an impartial and independent internal 
management review. Licensees and applicants shall not grant unescorted 
access or certify unescorted access authorization, or permit the 
individual to maintain unescorted access or unescorted access 
authorization during the review process.
    (m) Protection of information. Each licensee, applicant, contractor, 
or vendor shall establish and maintain a system of files and procedures 
to ensure personal information is not disclosed to unauthorized persons.
    (1) Licensees, applicants and contractors or vendors shall obtain 
signed consent from the subject individual that authorizes the 
disclosure of any information collected and maintained under this 
section before disclosing the information, except for disclosures to the 
following individuals:
    (i) The subject individual or his or her representative, when the 
individual has designated the representative in writing for specified 
unescorted access authorization matters;
    (ii) NRC representatives;
    (iii) Appropriate law enforcement officials under court order;
    (iv) A licensee's, applicant's, or contractor's or vendor's 
representatives who have a need to have access to the information in 
performing assigned duties, including determinations of trustworthiness 
and reliability and audits of access authorization programs;
    (v) The presiding officer in a judicial or administrative proceeding 
that is initiated by the subject individual;
    (vi) Persons deciding matters under the review procedures in 
paragraph (k) of this section; or
    (vii) Other persons pursuant to court order.
    (2) All information pertaining to a denial or unfavorable 
termination of the individual's unescorted access or unescorted access 
authorization shall be promptly provided, upon receipt of a written 
request by the subject individual or his or her designated 
representative as designated in writing. The licensee or applicant may 
redact the information to be released to the extent that personal 
privacy information, including the name of the source of the information 
is withheld.
    (3) A contract with any individual or organization who collects and 
maintains personal information that is relevant to an unescorted access 
or unescorted access authorization determination must require that such 
records be held in confidence, except as provided in paragraphs (m)(1) 
through (m)(2) of this section.
    (4) Licensees, applicants, or contractors or vendors and any 
individual or organization who collects and maintains personal 
information on behalf of a licensee, applicant, or contractor or vendor, 
shall establish, implement, and maintain a system and procedures for the 
secure storage and handling of the information collected.
    (n) Audits and corrective action. Each licensee and applicant shall 
be responsible for the continuing effectiveness of the access 
authorization program, including access authorization program elements 
that are provided by the contractors or vendors, and the access 
authorization programs of any of the contractors or vendors that are 
accepted by the licensee or applicant. Each licensee, applicant, and 
contractor or vendor shall ensure that access authorization programs and 
program elements are audited to confirm compliance with the requirements 
of this section and those comprehensive actions are taken to correct any 
non-conformance that is identified.
    (1) Each licensee and applicant shall ensure that its entire access 
authorization program is audited nominally every 24 months. Licensees, 
applicants and contractors or vendors are responsible for determining 
the appropriate frequency, scope, and depth of additional auditing 
activities within the nominal 24-month period based on the review of 
program performance indicators, such as the frequency, nature, and 
severity of discovered problems, personnel or procedural changes, and 
previous audit findings.
    (2) Access authorization program services that are provided to a 
licensee or applicant by contractor or vendor personnel who are off site 
or are not under the direct daily supervision or observation of the 
licensee's or applicant's personnel must be audited by

[[Page 545]]

the licensee or applicant on a nominal 12-month frequency. In addition, 
any access authorization program services that are provided to 
contractors or vendors by subcontractor personnel who are off site or 
are not under the direct daily supervision or observation of the 
contractor's or vendor's personnel must be audited by the licensee or 
applicant on a nominal 12-month frequency.
    (3) Licensee's and applicant's contracts with contractors or vendors 
must reserve the licensee's or applicant's right to audit the 
contractors or vendors and the contractor's or vendor's subcontractors 
providing access authorization program services at any time, including 
at unannounced times, as well as to review all information and 
documentation that is reasonably relevant to the performance of the 
program.
    (4) Licensee's and applicant's contracts with the contractors or 
vendors, and contractors' or vendors' contracts with subcontractors, 
must also require that the licensee or applicant shall be provided 
access to and be permitted to take away copies of any documents or data 
that may be needed to assure that the contractor or vendor and its 
subcontractors are performing their functions properly and that staff 
and procedures meet applicable requirements.
    (5) Audits must focus on the effectiveness of the access 
authorization program or program element(s), as appropriate. At least 
one member of the licensee or applicant audit team shall be a person who 
is knowledgeable of and practiced with meeting the performance 
objectives and requirements of the access authorization program or 
program elements being audited. The individuals performing the audit of 
the access authorization program or program element(s) shall be 
independent from both the subject access authorization programs' 
management and from personnel who are directly responsible for 
implementing the access authorization program or program elements being 
audited.
    (6) The results of the audits, along with any recommendations, must 
be documented in the site corrective action program in accordance with 
Sec. 73.55(b)(10) and reported to senior management having 
responsibility in the area audited and to management responsible for the 
access authorization program. Each audit report must identify conditions 
that are adverse to the proper performance of the access authorization 
program, the cause of the condition(s), and, when appropriate, 
recommended corrective actions, and corrective actions taken. The 
licensee, applicant, or contractor or vendor shall review the audit 
findings and take any additional corrective actions, to include re-
auditing of the deficient areas where indicated, to preclude repetition 
of the condition.
    (7) Licensees and applicants may jointly conduct audits, or may 
accept audits of the contractors or vendors that were conducted by other 
licensees and applicants who are subject to this section, if the audit 
addresses the services obtained from the contractor or vendor by each of 
the sharing licensees and applicants. The contractors or vendors may 
jointly conduct audits, or may accept audits of its subcontractors that 
were conducted by other licensees, applicants, or contractors or vendors 
who are subject to this section, if the audit addresses the services 
obtained from the subcontractor by each of the sharing licensees, 
applicants, and the contractors or vendors.
    (i) Licensees, applicants, and contractors or vendors shall review 
audit records and reports to identify any areas that were not covered by 
the shared or accepted audit and ensure that authorization program 
elements and services upon which the licensee, applicant, or contractor 
or vendor relies are audited, if the program elements and services were 
not addressed in the shared audit.
    (ii) Sharing licensees and applicants need not re-audit the same 
contractor or vendor for the same time. Sharing contractors or vendors 
need not re-audit the same subcontractor for the same time.
    (iii) Sharing licensees, applicants, and contractors or vendors 
shall maintain a copy of the shared audits, including findings, 
recommendations, and corrective actions.
    (o) Records. Licensee, applicants, and contractors or vendors shall 
maintain the records that are required by the

[[Page 546]]

regulations in this section for the period specified by the appropriate 
regulation. If a retention period is not otherwise specified, these 
records must be retained until the Commission terminates the facility's 
license, certificate, or other regulatory approval.
    (1) Records may be stored and archived electronically, provided that 
the method used to create the electronic records meets the following 
criteria:
    (i) Provides an accurate representation of the original records;
    (ii) Prevents unauthorized access to the records;
    (iii) Prevents the alteration of any archived information and/or 
data once it has been committed to storage; and
    (iv) Permits easy retrieval and re-creation of the original records.
    (2) Licensees and applicants who are subject to this section shall 
retain the following records:
    (i) Records of the information that must be collected under 
paragraphs (d) and (e) of this section that results in the granting of 
unescorted access or certifying of unescorted access authorization for 
at least 5 years after the licensee or applicant terminates or denies an 
individual's unescorted access or unescorted access authorization or 
until the completion of all related legal proceedings, whichever is 
later;
    (ii) Records pertaining to denial or unfavorable termination of 
unescorted access or unescorted access authorization and related 
management actions for at least 5 years after the licensee or applicant 
terminates or denies an individual's unescorted access or unescorted 
access authorization or until the completion of all related legal 
proceedings, whichever is later; and
    (iii) Documentation of the granting and termination of unescorted 
access or unescorted access authorization for at least 5 years after the 
licensee or applicant terminates or denies an individual's unescorted 
access or unescorted access authorization or until the completion of all 
related legal proceedings, whichever is later. Contractors or vendors 
may maintain the records that are or were pertinent to granting, 
certifying, denying, or terminating unescorted access or unescorted 
access authorization that they collected for licensees or applicants. If 
the contractors or vendors maintain the records on behalf of a licensee 
or an applicant, they shall follow the record retention requirement 
specified in this section. Upon termination of a contract between the 
contractor and vendor and a licensee or applicant, the contractor or 
vendor shall provide the licensee or applicant with all records 
collected for the licensee or applicant under this chapter.
    (3) Licensees, applicants, and contractors or vendors shall retain 
the following records for at least 3 years or until the completion of 
all related proceedings, whichever is later:
    (i) Records of behavioral observation training conducted under 
paragraph (f)(2) of this section; and
    (ii) Records of audits, audit findings, and corrective actions taken 
under paragraph (n) of this section.
    (4) Licensees, applicants, and contractors or vendors shall retain 
written agreements for the provision of services under this section, for 
three years after termination or completion of the agreement, or until 
completion of all proceedings related to a denial or unfavorable 
termination of unescorted access or unescorted access authorization that 
involved those services, whichever is later.
    (5) Licensees, applicants, and contractors or vendors shall retain 
records of the background investigations, psychological assessments, 
supervisory reviews, and behavior observation program actions related to 
access authorization program personnel, conducted under paragraphs (d) 
and (e) of this section, for the length of the individual's employment 
by or contractual relationship with the licensee, applicant, or the 
contractor or vendor and three years after the termination of 
employment, or until the completion of any proceedings relating to the 
actions of such access authorization program personnel, whichever is 
later.
    (6) Licensees, applicants, and the contractors or vendors who have 
been authorized to add or manipulate data that is shared with licensees 
subject to this section shall ensure that data linked to the information 
about individuals who have applied for

[[Page 547]]

unescorted access or unescorted access authorization, which is specified 
in the licensee's or applicant's access authorization program documents, 
is retained.
    (i) If the shared information used for determining individual's 
trustworthiness and reliability changes or new or additional information 
is developed about the individual, the licensees, applicants, and the 
contractors or vendors that acquire this information shall correct or 
augment the data and ensure it is shared with licensees subject to this 
section. If the changed, additional or developed information has 
implications for adversely affecting an individual's trustworthiness and 
reliability, the licensee, applicant, or the contractor or vendor who 
discovered or obtained the new, additional or changed information, 
shall, on the day of discovery, inform the reviewing official of any 
licensee or applicant access authorization program under which the 
individual is maintaining his or her unescorted access or unescorted 
access authorization status of the updated information.
    (ii) The reviewing official shall evaluate the shared information 
and take appropriate actions, which may include denial or unfavorable 
termination of the individual's unescorted access authorization. If the 
notification of change or updated information cannot be made through 
usual methods, licensees, applicants, and the contractors or vendors 
shall take manual actions to ensure that the information is shared as 
soon as reasonably possible. Records maintained in any database(s) must 
be available for NRC review.
    (7) If a licensee or applicant administratively withdraws an 
individual's unescorted access or unescorted access authorization status 
caused by a delay in completing any portion of the background 
investigation or for a licensee or applicant initiated evaluation, or 
re-evaluation that is not under the individual's control, the licensee 
or applicant shall record this administrative action to withdraw the 
individual's unescorted access or unescorted access authorization with 
other licensees subject to this section. However, licensees and 
applicants shall not document this administrative withdrawal as denial 
or unfavorable termination and shall not respond to a suitable inquiry 
conducted under the provisions of 10 CFR parts 26, a background 
investigation conducted under the provisions of this section, or any 
other inquiry or investigation as denial nor unfavorable termination. 
Upon favorable completion of the background investigation element that 
caused the administrative withdrawal, the licensee or applicant shall 
immediately ensure that any matter that could link the individual to the 
administrative action is eliminated from the subject individual's access 
authorization or personnel record and other records, except if a review 
of the information obtained or developed causes the reviewing official 
to unfavorably terminate or deny the individual's unescorted access.

[74 FR 13979, Mar. 27, 2009, as amended at 77 FR 39909, July 6, 2012, 81 
FR 86910, Dec. 2, 2016]



Sec. 73.57  Requirements for criminal history records checks of 
individuals granted unescorted access to a nuclear power facility,
a non-power reactor, or access to Safeguards Information.

    (a) General. (1) Each licensee who is authorized to engage in an 
activity subject to regulation by the Commission shall comply with the 
requirements of this section.
    (2) Each applicant for a license to engage in an activity subject to 
regulation by the Commission, as well as each entity who has provided 
written notice to the Commission of intent to file an application for 
licensing, certification, permitting, or approval of a product subject 
to regulation by the Commission shall submit fingerprints for those 
individuals who will have access to Safeguards Information.
    (3) Before receiving its operating license under 10 CFR part 50 or 
before the Commission makes its finding under Sec. 52.103(g) of this 
chapter, each applicant for a license to operate a nuclear power reactor 
(including an applicant for a combined license) or a non-power reactor 
may submit fingerprints for those individuals who will require 
unescorted access to the nuclear power facility or non-power reactor 
facility.

[[Page 548]]

    (b) General performance objective and requirements. (1) Except those 
listed in paragraph (b)(2) of this section, each licensee subject to the 
provisions of this section shall fingerprint each individual who is 
permitted unescorted access to the nuclear power facility, the non-power 
reactor facility in accordance with paragraph (g) of this section, or 
access to Safeguards Information. The licensee will then review and use 
the information received from the Federal Bureau of Investigation (FBI) 
and, based on the provisions contained in this section, determine either 
to continue to grant or to deny further unescorted access to the nuclear 
power facility, the non-power reactor facility, or access to Safeguards 
Information for that individual. Individuals who do not have unescorted 
access or access to Safeguards Information shall be fingerprinted by the 
licensee and the results of the criminal history records check shall be 
used before making a determination for granting unescorted access to the 
nuclear power facility, non-power reactor facility, or to Safeguards 
Information.
    (2) Licensees need not fingerprint in accordance with the 
requirements of this section for the following categories:
    (i) For unescorted access to the nuclear power facility or the non-
power reactor facility (but must adhere to provisions contained in 
Sec. Sec. 73.21 and 73.22): NRC employees and NRC contractors on 
official agency business; individuals responding to a site emergency in 
accordance with the provisions of Sec. 73.55(a); offsite emergency 
response personnel who are responding to an emergency at a non-power 
reactor facility; a representative of the International Atomic Energy 
Agency (IAEA) engaged in activities associated with the U.S./IAEA 
Safeguards Agreement at designated facilities who has been certified by 
the NRC; law enforcement personnel acting in an official capacity; 
Federal, State or local government employees who have had equivalent 
reviews of FBI criminal history data; and individuals employed at a 
facility who possess ``Q'' or ``L'' clearances or possess another active 
government granted security clearance (i.e., Top Secret, Secret, or 
Confidential);
    (ii) For access to Safeguards Information only but must adhere to 
provisions contained in Sec. Sec. 73.21, 73.22, and 73.23: the 
categories of individuals specified in 10 CFR 73.59.
    (iii) Any licensee currently processing criminal history requests 
through the FBI pursuant to Executive Order 10450 need not also submit 
such requests to the NRC under this section; and
    (iv) Upon further notice to licensees and without further 
rulemaking, the Commission may waive certain requirements of this 
section on a temporary basis.
    (v) Individuals who have a valid unescorted access authorization to 
a non-power reactor facility on November 7, 2012 are not required to 
undergo a new fingerprint-based criminal history records check pursuant 
to paragraph (g) of this section, until such time that the existing 
authorization expires, is terminated, or is otherwise to be renewed.
    (3) The licensee shall notify each affected individual that the 
fingerprints will be used to secure a review of his/her criminal history 
record, and inform the individual of proper procedures for revising the 
record or including explanation in the record.
    (4) Fingerprinting is not required if the licensee is reinstating 
the unescorted access to the nuclear power facility, the non-power 
reactor facility, or access to Safeguards Information granted an 
individual if:
    (i) The individual returns to the same nuclear power utility or non-
power reactor facility that granted access and such access has not been 
interrupted for a continuous period of more than 365 days; and
    (ii) The previous access was terminated under favorable conditions.
    (5) Fingerprints need not be taken, in the discretion of the 
licensee, if an individual who is an employee of a licensee, contractor, 
manufacturer, or supplier has been granted unescorted access to a 
nuclear power facility, a non-power reactor facility, or to Safeguards 
Information by another licensee, based in part on a criminal history 
records check under this section. The criminal history records check 
file

[[Page 549]]

may be transferred to the gaining licensee in accordance with the 
provisions of paragraph (f)(3) of this section.
    (6) All fingerprints obtained by the licensee under this section 
must be submitted to the Attorney General of the United States through 
the Commission.
    (7) The licensee shall review the information received from the 
Attorney General and consider it in making a determination for granting 
unescorted access to the individual or access to Safeguards Information.
    (8) A licensee shall use the information obtained as part of a 
criminal history records check solely for the purpose of determining an 
individual's suitability for unescorted access to the nuclear power 
facility, the non-power reactor facility, or access to Safeguards 
Information.
    (c) Prohibitions. (1) A licensee may not base a final determination 
to deny an individual unescorted access to the nuclear power facility, 
the non-power reactor facility, or access to Safeguards Information 
solely on the basis of information received from the FBI involving:
    (i) An arrest more than 1 year old for which there is no information 
of the disposition of the case; or
    (ii) An arrest that resulted in dismissal of the charge or an 
acquittal.
    (2) A licensee may not use information received from a criminal 
history check obtained under this section in a manner that would 
infringe upon the rights of any individual under the First Amendment to 
the Constitution of the United States, nor shall the licensee use the 
information in any way which would discriminate among individuals on the 
basis of race, religion, national origin, sex, or age.
    (d) Procedures for processing of fingerprint checks. (1) For the 
purpose of complying with this section, licensees shall, using an 
appropriate method listed in Sec. 73.4, submit to the NRC's Division of 
Facilities and Security, Mail Stop TWB 05B32M, one completed, legible 
standard fingerprint card (Form FD-258, ORIMDNRCOOOZ) or, where 
practicable, other fingerprint records for each individual requiring 
unescorted access to the nuclear power facility, the non-power reactor 
facility, or access to Safeguards Information, to the Director of the 
NRC's Division of Facilities and Security, marked for the attention of 
the Division's Criminal History Check Section. Copies of these forms may 
be obtained by writing the Office of the Chief Information Officer, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, by calling 
301-415-5877, or by email to [email protected]. Guidance on what 
alternative formats might be practicable is referenced in Sec. 73.4. 
The licensee shall establish procedures to ensure that the quality of 
the fingerprints taken results in minimizing the rejection rate of 
fingerprint cards due to illegible or incomplete cards.
    (2) The Commission will review applications for criminal history 
checks for completeness. Any Form FD-258 or other fingerprint record 
containing omissions or evident errors will be returned to the licensee 
for corrections. The fee for processing fingerprint checks includes one 
free resubmission if the initial submission is returned by the FBI 
because the fingerprint impressions cannot be classified. The one free 
resubmission must have the FBI Transaction Control Number reflected on 
the resubmission. If additional submissions are necessary, they will be 
treated as an initial submittal and require a second payment of the 
processing fee. The payment of a new processing fee entitles the 
submitter to an additional free resubmittal, if necessary. Previously 
rejected submissions may not be included with the third submission 
because the submittal will be rejected automatically.
    (3)(i) Fees for the processing of fingerprint checks are due upon 
application. Licensees shall submit payment with the application for the 
processing of fingerprints through corporate check, certified check, 
cashier's check, money order, or electronic payment, made payable to 
``U.S. NRC.'' (For guidance on making electronic payments, contact the 
Security Branch, Division of Facilities and Security, at (301) 415-
7404). Combined payment for multiple applications is acceptable.
    (ii) The application fee is the sum of the user fee charged by the 
FBI for each fingerprint card or other fingerprint record submitted by 
the NRC on

[[Page 550]]

behalf of a licensee, and an administrative processing fee assessed by 
the NRC. The NRC processing fee covers administrative costs associated 
with NRC handling of licensee fingerprint submissions. The Commission 
publishes the amount of the fingerprint records check application fee on 
the NRC public Web site. (To find the current fee amount, go to the 
Electronic Submittals page at http://www.nrc.gov/site-help/e-
submittals.html and see the link for the Criminal History Program.) The 
Commission will directly notify licensees who are subject to this 
regulation of any fee changes.
    (4) The Commission will forward to the submitting licensee all data 
received from the FBI as a result of the licensee's application(s) for 
criminal history checks, to include the FBI fingerprint record.
    (e) Right to correct and complete information. (1) Prior to any 
final adverse determination, the licensee shall make available to the 
individual the contents of records obtained from the FBI for the purpose 
of assuring correct and complete information. Confirmation of receipt by 
the individual of this notification must be maintained by the licensee 
for a period of 1 year from the date of the notification.
    (2) If after reviewing the record, an individual believes that it is 
incorrect or incomplete in any respect and wishes changes, corrections, 
or updating (of the alleged deficiency), or to explain any matter in the 
record, the individual may initiate challenge procedures. These 
procedures include direct application by the individual challenging the 
record to the agency, i.e., law enforcement agency, that contributed the 
questioned information or direct challenge as to the accuracy or 
completeness of any entry on the criminal history record to the 
Assistant Director, Federal Bureau of Investigation Identification 
Division, Washington, DC 20537-9700 as set forth in 28 CFR 16.30 through 
16.34. In the latter case, the FBI then forwards the challenge to the 
agency that submitted the data requesting that agency to verify or 
correct the challenged entry. Upon receipt of an official communication 
directly from the agency that contributed the original information, the 
FBI Identification Division makes any changes necessary in accordance 
with the information supplied by that agency. Licensees must provide at 
least 10 days for an individual to initiate action to challenge the 
results of an FBI criminal history records check after the record being 
made available for his/her review. The licensee may make a final adverse 
determination based upon the criminal history record, if applicable, 
only upon receipt of the FBI's confirmation or correction of the record.
    (3) In addition to the right to obtain records from the FBI in 
paragraph (e)(1) of this section and the right to initiate challenge 
procedures in paragraph (e)(2) of this section, an individual 
participating in an NRC adjudication and seeking to obtain Safeguards 
Information for use in that adjudication may appeal a final adverse 
determination by the NRC Office of Administration to the presiding 
officer of the proceeding. The request may also seek to have the Chief 
Administrative Judge designate an officer other than the presiding 
officer of the proceeding to review the adverse determination.
    (f) Protection of information. (1) Each licensee who obtains a 
criminal history record on an individual under this section shall 
establish and maintain a system of files and procedures for protection 
of the record and the personal information from unauthorized disclosure.
    (2) The licensee may not disclose the record or personal information 
collected and maintained to persons other than the subject individual, 
his/her representative, or to those who have a need to have access to 
the information in performing assigned duties in the process of granting 
or denying unescorted access to the nuclear power facility, the non-
power reactor facility or access to Safeguards Information. No 
individual authorized to have access to the information may re-
disseminate the information to any other individual who does not have a 
need to know.
    (3) The personal information obtained on an individual from a 
criminal history record check may be transferred to another licensee:
    (i) Upon the individual's written request to the licensee holding 
the data

[[Page 551]]

to re-disseminate the information contained in his/her file; and
    (ii) The gaining licensee verifies information such as name, date of 
birth, social security number, sex, and other applicable physical 
characteristics for identification.
    (4) The licensee shall make criminal history records obtained under 
this section available for examination by an authorized representative 
of the NRC to determine compliance with the regulations and laws.
    (5) The licensee shall retain all fingerprint and criminal history 
records received from the FBI, or a copy if the individual's file has 
been transferred, on an individual (including data indicating no record) 
for one year after termination or denial of unescorted access to the 
nuclear power facility, the non-power reactor facility, or access to 
Safeguards Information.
    (g) Fingerprinting requirements for unescorted access for non-power 
reactor licensees. (1) No person shall be permitted unescorted access to 
a non-power reactor facility unless that person has been determined by 
an NRC-approved reviewing official to be trustworthy and reliable based 
on the results of an FBI fingerprint-based criminal history records 
check obtained in accordance with this paragraph. The reviewing official 
is required to have unescorted access in accordance with this section or 
access to Safeguards Information.
    (2) Each non-power reactor licensee subject to the requirements of 
this section shall obtain the fingerprints for a criminal history 
records check for each individual who is seeking or permitted:
    (i) Unescorted access to vital areas of the non-power reactor 
facility; or
    (ii) Unescorted access to special nuclear material in the non-power 
reactor facility provided the individual who is seeking or permitted 
unescorted access possesses the capability and knowledge to make 
unauthorized use of the special nuclear material in the non-power 
reactor facility or to remove the special nuclear material from the non-
power reactor in an unauthorized manner.

[52 FR 6314, Mar. 2, 1987; 52 FR 7821, Mar. 13, 1987]

    Editorial Note: For Federal Register citations affecting Sec. 
73.57, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 73.58  Safety/security interface requirements for nuclear
power reactors.

    (a) Each operating nuclear power reactor licensee with a license 
issued under part 50 or 52 of this chapter shall comply with the 
requirements of this section.
    (b) The licensee shall assess and manage the potential for adverse 
effects on safety and security, including the site emergency plan, 
before implementing changes to plant configurations, facility 
conditions, or security.
    (c) The scope of changes to be assessed and managed must include 
planned and emergent activities (such as, but not limited to, physical 
modifications, procedural changes, changes to operator actions or 
security assignments, maintenance activities, system reconfiguration, 
access modification or restrictions, and changes to the security plan 
and its implementation).
    (d) Where potential conflicts are identified, the licensee shall 
communicate them to appropriate licensee personnel and take compensatory 
and/or mitigative actions to maintain safety and security under 
applicable Commission regulations, requirements, and license conditions.

[74 FR 13987, Mar. 27, 2009]



Sec. 73.59  Relief from fingerprinting, identification and criminal
history records checks and other elements of background checks for 
designated categories of individuals.

    Fingerprinting, and the identification and criminal history records 
checks required by section 149 of the Atomic Energy Act of 1954, as 
amended, and other elements of background checks are not required for 
the following individuals prior to granting access to Safeguards 
Information, including Safeguards Information designated as Safeguards 
Information-Modified Handling as defined in 10 CFR 73.2:
    (a) An employee of the Commission or the Executive Branch of the 
United States government who has undergone

[[Page 552]]

fingerprinting for a prior U.S. government criminal history records 
check;
    (b) A member of Congress;
    (c) An employee of a member of Congress or Congressional committee 
who has undergone fingerprinting for a prior U.S. government criminal 
history records check;
    (d) The Comptroller General or an employee of the Government 
Accountability Office who has undergone fingerprinting for a prior U.S. 
Government criminal history records check;
    (e) The Governor of a State or his or her designated State employee 
representative;
    (f) A representative of a foreign government organization that is 
involved in planning for, or responding to, nuclear or radiological 
emergencies or security incidents who the Commission approves for access 
to Safeguards Information, including Safeguards Information designated 
as Safeguards Information--Modified Handling;
    (g) Federal, State, or local law enforcement personnel;
    (h) State Radiation Control Program Directors and State Homeland 
Security Advisors or their designated State employee representatives;
    (i) Agreement State employees conducting security inspections on 
behalf of the NRC pursuant to an agreement executed under section 274.i. 
of the Atomic Energy Act of 1954, as amended;
    (j) Representatives of the International Atomic Energy Agency (IAEA) 
engaged in activities associated with the U.S./IAEA Safeguards Agreement 
who have been certified by the NRC;
    (k) Any agent, contractor, or consultant of the aforementioned 
persons who has undergone equivalent criminal history records and 
background checks to those required by 10 CFR 73.22(b) or 73.23(b).
    (l) Tribal official or the Tribal official's designated 
representative, and Tribal law enforcement personnel.

[73 FR 63580, Oct. 24, 2008, as amended at 77 FR 34206, June 11, 2012]



Sec. 73.60  Additional requirements for physical protection
at nonpower reactors.

    Each nonpower reactor licensee who, pursuant to the requirements of 
part 70 of this chapter, possesses at any site or contiguous sites 
subject to control by the licensee uranium-235 (contained in uranium 
enriched to 20 percent or more in the U-235 isotope), uranium-233, or 
plutonium, alone or in any combination in a quantity of 5000 grams or 
more computed by the formula, grams = (grams contained U-235) + 2.5 
(grams U-233 + grams plutonium), shall protect the special nuclear 
material from theft or diversion pursuant to the requirements of 
paragraphs 73.67 (a), (b), (c), and (d), in addition to this section, 
except that a licensee is exempt from the requirements of paragraphs 
(a), (b), (c), (d), and (e) of this section to the extent that it 
possesses or uses special nuclear material that is not readily separable 
from other radioactive material and that has a total external radiation 
dose rate in excess of 100 rems per hour at a distance of 3 feet from 
any accessible surface without intervening shielding.
    (a) Access requirements. (1) Special nuclear material shall be 
stored or processed only in a material access area. No activities other 
than those which require access to special nuclear material or equipment 
employed in the process, use, or storage of special nuclear material, 
shall be permitted within a material access area.
    (2) Material access areas shall be located only within a protected 
area to which access is controlled.
    (3) Special nuclear material not in process shall be stored in a 
vault equipped with an intrusion alarm or in a vault-type room, and each 
such vault or vault-type room shall be controlled as a separate material 
access area.
    (4) Enriched uranium scrap in the form of small pieces, cuttings, 
chips, solutions or in other forms which result from a manufacturing 
process, contained in 30-gallon or larger containers, with a uranium-235 
content of less than 0.25 grams per liter, may be stored within a locked 
and separately fenced area which is within a larger protected area 
provided that the storage area is no closer than 25 feet to the

[[Page 553]]

perimeter of the protected area. The storage area when unoccupied shall 
be protected by a guard or watchman who shall patrol at intervals not 
exceeding 4 hours, or by intrusion alarms.
    (5) Admittance to a material access area shall be under the control 
of authorized individuals and limited to individuals who require such 
access to perform their duties.
    (6) Prior to entry into a material access area, packages shall be 
searched for devices such as firearms, explosives, incendiary devices, 
or counterfeit substitute items which could be used for theft or 
diversion of special nuclear material.
    (7) Methods to observe individuals within material access areas to 
assure that special nuclear material is not diverted shall be provided 
and used on a continuing basis.
    (b) Exit requirement. Each individual, package, and vehicle shall be 
searched for concealed special nuclear material before exiting from a 
material access area unless exit is into a contiguous material access 
area. The search may be carried out by a physical search or by use of 
equipment capable of detecting the presence of concealed special nuclear 
material.
    (c) Detection aid requirement. Each unoccupied material access area 
shall be locked and protected by an intrusion alarm on active status. 
All emergency exits shall be continuously alarmed.
    (d) Testing and maintenance. Each licensee shall test and maintain 
intrusion alarms, physical barriers, and other devices utilized pursuant 
to the requirements of this section as follows:
    (1) Intrusion alarms, physical barriers, and other devices used for 
material protection shall be maintained in operable condition.
    (2) Each intrusion alarm shall be inspected and tested for 
operability and required functional performance at the beginning and end 
of each interval during which it is used for material protection, but 
not less frequently than once every seven (7) days.
    (e) Response requirement. Each licensee shall establish, maintain, 
and follow an NRC-approved safeguards contingency plan for responding to 
threats, thefts, and radiological sabotage related to the special 
nuclear material and nuclear facilities subject to the provisions of 
this section. Safeguards contingency plans must be in accordance with 
the criteria in Appendix C to this part, ``Licensee Safeguards 
Contingency Plans.''
    (f) In addition to the fixed-site requirements set forth in this 
section and in Sec. 73.67, the Commission may require, depending on the 
individual facility and site conditions, any alternate or additional 
measures deemed necessary to protect against radiological sabotage at 
nonpower reactors licensed to operate at or above a power level of 2 
megawatts thermal.

[38 FR 35430, Dec. 28, 1973, as amended at 44 FR 68199, Nov. 28, 1979; 
57 FR 33431, July 29, 1992; 58 FR 13700, Mar. 15, 1993]



Sec. 73.61  Relief from fingerprinting and criminal history records 
check for designated categories of individuals permitted unescorted
access to certain radioactive materials or other property.

    Notwithstanding any other provision of the Commission's regulations, 
fingerprinting and the identification and criminal history records 
checks required by section 149 of the Atomic Energy Act of 1954, as 
amended, are not required for the following individuals prior to 
granting unescorted access to radioactive materials or other property 
that the Commission determines by regulation or order to be of such 
significance to the public health and safety or the common defense and 
security as to warrant fingerprinting and background checks:
    (a) An employee of the Commission or of the Executive Branch of the 
U.S. Government who has undergone fingerprinting for a prior U.S. 
Government criminal history check;
    (b) A Member of Congress;
    (c) An employee of a member of Congress or Congressional committee 
who has undergone fingerprinting for a prior U.S. Government criminal 
history check;
    (d) The Governor of a State or his or her designated State employee 
representative;
    (e) Federal, State, or local law enforcement personnel;
    (f) State Radiation Control Program Directors and State Homeland 
Security

[[Page 554]]

Advisors or their designated State employee representatives;
    (g) Agreement State employees conducting security inspections on 
behalf of the NRC pursuant to an agreement executed under section 274.i. 
of the Atomic Energy Act;
    (h) Representatives of the International Atomic Energy Agency (IAEA) 
engaged in activities associated with the U.S./IAEA Safeguards Agreement 
who have been certified by the NRC.

[72 FR 4948, Feb. 2, 2007]

  Physical Protection of Special Nuclear Material of Moderate and Low 
                         Strategic Significance



Sec. 73.67  Licensee fixed site and in-transit requirements for the
physical protection of special nuclear material of moderate and low
strategic significance.

    (a) General performance objectives. (1) Each licensee who possesses, 
uses or transports special nuclear material of moderate or low strategic 
significance shall establish and maintain a physical protection system 
that will achieve the following objectives:
    (i) Minimize the possibilities for unauthorized removal of special 
nuclear material consistent with the potential consequences of such 
actions; and
    (ii) Facilitate the location and recovery of missing special nuclear 
material.
    (2) To achieve these objectives, the physical protection system 
shall provide:
    (i) Early detection and assessment of unauthorized access or 
activities by an external adversary within the controlled access area 
containing special nuclear material;
    (ii) Early detection of removal of special nuclear material by an 
external adversary from a controlled access area;
    (iii) Assure proper placement and transfer of custody of special 
nuclear material; and
    (iv) Respond to indications of an unauthorized removal of special 
nuclear material and then notify the appropriate response forces of its 
removal in order to facilitate its recovery.
    (b)(1) A licensee is exempt from the requirements of this section to 
the extent that he possesses, uses, or transports:
    (i) Special nuclear material which is not readily separable from 
other radioactive material and which has a total external radiation dose 
rate in excess of 100 rems per hour at a distance of 3 feet from any 
accessible surface without intervening shielding, or
    (ii) Sealed plutonium-beryllium neutron sources totaling 500 grams 
or less contained plutonium at any one site or contiguous sites, or
    (iii) Plutonium with an isotopic concentration exceeding 80 percent 
in plutonium-238.
    (2) A licensee who has quantities of special nuclear material 
equivalent to special nuclear material of moderate strategic 
significance distributed over several buildings may, for each building 
which contains a quantity of special nuclear material less than or equal 
to a level of special nuclear material of low strategic significance, 
protect the material in that building under the lower classification 
physical security requirements.
    (c) Each licensee who possesses, uses, transports, or delivers to a 
carrier for transport special nuclear material of moderate strategic 
significance, or 10 kg or more of special nuclear material of low 
strategic significance shall:
    (1) Submit a security plan or an amended security plan describing 
how the licensee will comply with all the requirements of paragraphs 
(d), (e), (f), and (g) of this section, as appropriate, including 
schedules of implementation. The licensee shall retain a copy of the 
effective security plan as a record for three years after the close of 
period for which the licensee possesses the special nuclear material 
under each license for which the original plan was submitted. Copies of 
superseded material must be retained for three years after each change.
    (2) Within 30 days after the plan submitted pursuant to paragraph 
(c)(1) of this section is approved, or when specified by the NRC in 
writing, implement the approved security plan.
    (d) Fixed site requirements for special nuclear material of moderate 
strategic significance. Each licensee who possesses,

[[Page 555]]

stores, or uses quantities and types of special nuclear material of 
moderate strategic significance at a fixed site or contiguous sites, 
except as allowed by paragraph (b)(2) of this section and except those 
who are licensed to operate a nuclear power reactor pursuant to part 50, 
shall:
    (1) Use the material only within a controlled access area which is 
illuminated sufficiently to allow detection and surveillance of 
unauthorized penetration or activities,
    (2) Store the material only within a controlled access area such as 
a vault-type room or approved security cabinet or their equivalent which 
is illuminated sufficiently to allow detection and surveillance of 
unauthorized penetration or activities,
    (3) Monitor with an intrusion alarm or other device or procedures 
the controlled access areas to detect unauthorized penetration or 
activities,
    (4) Conduct screening prior to granting an individual unescorted 
access to the controlled access area where the material is used or 
stored, in order to obtain information on which to base a decision to 
permit such access,
    (5) Develop and maintain a controlled badging and lock system to 
identify and limit access to the controlled access areas to authorized 
individuals,
    (6) Limit access to the controlled access areas to authorized or 
escorted individuals who require such access in order to perform their 
duties,
    (7) Assure that all visitors to the controlled access areas are 
under the constant escort of an individual who has been authorized 
access to the area,
    (8) Establish a security organization or modify the current security 
organization to consist of at least one watchman per shift able to 
assess and respond to any unauthorized penetrations or activities in the 
controlled access areas,
    (9) Provide a communication capability between the security 
organization and appropriate response force,
    (10) Search on a random basis vehicles and packages leaving the 
controlled access areas, and
    (11) Establish and maintain written response procedures for dealing 
with threats of thefts or thefts of these materials. The licensee shall 
retain a copy of the response procedures as a record for the period 
during which the licensee possesses the appropriate type and quantity of 
special nuclear material requiring this record under each license for 
which the original procedures were developed and, for three years 
thereafter. Copies of superseded material must be retained for three 
years after each change.
    (e) In-transit requirements for special nuclear material of moderate 
strategic significance. (1) Each licensee who transports, exports or 
delivers to a carrier for transport special nuclear material of moderate 
strategic significance shall:
    (i) Provide advance notification to the receiver of any planned 
shipments specifying the mode of transport, estimated time of arrival, 
location of the nuclear material transfer point, name of carrier and 
transport identification,
    (ii) Receive confirmation from the receiver prior to the 
commencement of the planned shipment that the receiver will be ready to 
accept the shipment at the planned time and location and acknowledges 
the specified mode of transport,
    (iii) Check the integrity of the container and locks or seals prior 
to shipment, and
    (iv) Arrange for the in-transit physical protection of the materials 
in accordance with the requirements of Sec. 73.67(e)(3) unless the 
receiver is a licensee and has agreed in writing to arrange for the in-
transit physical protection.
    (2) Each licensee who receives special nuclear material of moderate 
strategic significance shall:
    (i) Check the integrity of the containers and seals upon receipt of 
the shipment,
    (ii) Notify the shipper of receipt of the material as required in 
Sec. 74.15 of this chapter, and
    (iii) Arrange for the in-transit physical protection of the material 
in accordance with the requirements of Sec. 73.67(e)(3) unless the 
shipper is a licensee and has agreed in writing to arrange for the in-
transit physical protection.
    (3) Each licensee who arranges for the in-transit physical 
protection of special nuclear material of moderate

[[Page 556]]

strategic significance, or who takes delivery of this material free on 
board (f.o.b.) the point at which it is delivered to a carrier for 
transport shall:
    (i) Arrange for telephone or radio communications between the 
transport and the licensee or its designee: (A) To periodically confirm 
the status of the shipment (B) for notification of any delays in the 
scheduled shipment, and (C) to request appropriate local law enforcement 
agency response in the event of an emergency.
    (ii) Minimize the time that the material is in transit by reducing 
the number and duration of nuclear material transfers and by routing the 
material in the most safe and direct manner,
    (iii) Conduct screening of all licensee employees involved in the 
transportation of the material in order to obtain information on which 
to base a decision to permit them control over the material,
    (iv) Establish and maintain written response procedures for dealing 
with threats of thefts or thefts of this material. The licensee shall 
retain a copy of the current response procedures as a record for three 
years after the close of period for which the licensee possesses the 
special nuclear material under each license for which the original 
procedures were developed and copies of superseded material must be 
retained for three years after each change.
    (v) Make arrangements to be notified immediately of the arrival of 
the shipment at its destination, or of any such shipment that is lost or 
unaccounted for after the estimated time of arrival at its destination, 
and
    (vi) Initiate immediately a trace investigation of any shipment that 
is determined to be lost or unaccounted for after a reasonable time 
beyond the estimated arrival time.
    (vii) Notify the NRC Operations Center \1\ within one hour after the 
discovery of the loss of the shipment and within one hour after recovery 
of or accounting for such lost shipment in accordance with the 
provisions of Sec. 73.71 of this part.
---------------------------------------------------------------------------

    \1\ Commercial telephone number of the NRC Operations Center is 
(301) 816-5100.
---------------------------------------------------------------------------

    (4) Each licensee who arranges the physical protection of strategic 
special nuclear material in quantities of moderate strategic 
significance while in transit or who takes delivery of this material 
free on board (f.o.b.) the point at which it is delivered to a carrier 
for transport shall comply with the requirements of paragraphs (e) (1), 
(2), and (3) of this section. The licensee shall retain each record 
required by paragraphs (e) (1), (2), (3), and (4) (i) and (ii) of this 
section for three years after close of period licensee possesses special 
nuclear material under each license that authorizes these licensee 
activities. Copies of superseded material must be retained for three 
years after each change. In addition, the licensee shall--
    (i) Make all shipments of the material either (A) in dedicated 
transports with no intermediate stops to load or unload other cargo and 
with no carrier or vehicle transfers or temporary storage in-transit, or 
(B) under arrangements whereby the custody of the shipment and all 
custody transfers are acknowledged by signature, and
    (ii) Maintain the material under lock or under the control of an 
individual who has acknowledged acceptance of custody of the material by 
signature.
    (5) Each licensee who exports special nuclear material of moderate 
strategic significance shall comply with the requirements specified in 
paragraphs (c) and (e) (1), (3), and (4) of this section. The licensee 
shall retain each record required by these sections for three years 
after the close of period for which the licensee possesses the special 
nuclear material under each license that authorizes the licensee to 
export this material. Copies of superseded material must be retained for 
three years after each change.
    (6) Each licensee who imports special nuclear material of moderate 
strategic significance shall,
    (i) Comply with the requirements specified in paragraphs (c) and (e) 
(2), (3), and (4) of this section. The licensee shall retain each record 
required by these sections for three years after the close of period for 
which the licensee possesses the special nuclear material under each 
license that authorizes the

[[Page 557]]

licensee to import this material. Copies of superseded material must be 
retained for three years after each change.
    (ii) Notify the exporter who delivered the material to a carrier for 
transport of the arrival of such material.
    (7) If, after receiving advance notice pursuant to Sec. 73.72 from 
a licensee planning to import, export, transport, deliver to a carrier 
for transport in a single shipment, or take delivery at the point where 
it is delivered to a carrier, special nuclear material of moderate 
strategic significance containing in any part strategic special nuclear 
material, it appears to the Commission that two or more shipments of 
special nuclear material of moderate strategic significance, 
constituting in the aggregate an amount equal to or greater than a 
formula quantity of strategic special nuclear material, may be en route 
at the same time, the Commission may order one or more of the shippers 
to delay shipment according to the following provisions:
    (i) The shipper shall provide to the Commission, upon request, such 
additional information regarding a planned shipment as the Commission 
considers pertinent to the decision on whether to delay such shipment.
    (ii) The receiver of each shipment, or the shipper if the receiver 
is not a licensee, shall notify the Director, Division of Security 
Policy, Office of Nuclear Security and Incident Response, by telephone, 
no later than 24 hours after arrival of such shipment at its final 
destination, or after such shipment has left the United States as an 
export, to confirm the integrity of the shipment at the time of receipt 
or exit from the United States.
    (iii) The Commission shall notify the affected shippers no later 
than two days before the scheduled shipment date that a given shipment 
is to be delayed.
    (iv) Shipments of special nuclear material of moderate strategic 
significance which are protected in accordance with the provisions of 
Sec. Sec. 73.20, 73.25, and 73.26 shall not be subject to orders to 
delay shipment nor considered to constitute a portion of an aggregate 
formula quantity of strategic special nuclear material for the purposes 
of determining whether any shipments must delayed.
    (f) Fixed site requirements for special nuclear material of low 
strategic significance. Each licensee who possesses, stores, or uses 
special nuclear material of low strategic significance at a fixed site 
or contiguous sites, except those who are licensed to operate a nuclear 
power reactor pursuant to part 50, shall:
    (1) Store or use the material only within a controlled access area,
    (2) Monitor with an intrusion alarm or other device or procedures 
the controlled access areas to detect unauthorized penetrations or 
activities,
    (3) Assure that a watchman or offsite response force will respond to 
all unauthorized penetrations or activities, and
    (4) Establish and maintain response procedures for dealing with 
threats of thefts or thefts of this material. The licensee shall retain 
a copy of the current response procedures as a record for three years 
after the close of period for which the licensee possesses the special 
nuclear material under each license for which the procedures were 
established. Copies of superseded material must be retained for three 
years after each change.
    (g) In-transit requirements for special nuclear material of low 
strategic significance. (1) Each licensee who transports or who delivers 
to a carrier for transport special nuclear material of low strategic 
significance shall:
    (i) Provide advance notification to the receiver of any planned 
shipments specifying the mode of transport, estimated time of arrival, 
location of the nuclear material transfer point, name of carrier and 
transport identification,
    (ii) Receive confirmation from the receiver prior to commencement of 
the planned shipment that the receiver will be ready to accept the 
shipment at the planned time and location and acknowledges the specified 
mode of transport,
    (iii) Transport the material in a tamper indicating sealed 
container,
    (iv) Check the integrity of the containers and seals prior to 
shipment, and
    (v) Arrange for the in-transit physical protection of the material 
in accordance with the requirements of

[[Page 558]]

Sec. 73.67(g)(3) of this part, unless the receiver is a licensee and 
has agreed in writing to arrange for the in-transit physical protection.
    (2) Each licensee who receives quantities and types of special 
nuclear material of low strategic significance shall:
    (i) Check the integrity of the containers and seals upon receipt of 
the shipment,
    (ii) Notify the shipper of receipt of the material as required in 
Sec. 74.15 of this chapter, and
    (iii) Arrange for the in-transit physical protection of the material 
in accordance with the requirements of Sec. 73.67(g)(3) of this part, 
unless the shipper is a licensee and has agreed in writing to arrange 
for the in-transit physical protection.
    (3) Each licensee, either shipper or receiver, who arranges for the 
physical protection of special nuclear material of low strategic 
significance while in transit or who takes delivery of such material 
free on board (f.o.b.) the point at which it is delivered to a carrier 
for transport shall:
    (i) Establish and maintain response procedures for dealing with 
threats or thefts of this material. The licensee shall retain a copy of 
the current response procedures as a record for three years after the 
close of period for which the licensee possesses the special nuclear 
material under each license for which the procedures were established. 
Copies of superseded material must be retained for three years after 
each change.
    (ii) Make arrangements to be notified immediately of the arrival of 
the shipment at its destination, or of any such shipment that is lost or 
unaccounted for after the estimated time of arrival at its destination, 
and
    (iii) Conduct immediately a trace investigation of any shipment that 
is lost or unaccounted for after the estimated arrival time and notify 
the NRC Operations Center \1\ within one hour after the discovery of the 
loss of the shipment and within one hour after recovery of or accounting 
for such lost shipment in accordance with the provisions of Sec. 73.71 
of this part.
---------------------------------------------------------------------------

    \1\ Commercial telephone number of the NRC Operation Center is (301) 
816-5100.
---------------------------------------------------------------------------

    (4) Each licensee who exports special nuclear material of low 
strategic significance shall comply with the appropriate requirements 
specified in paragraphs (c) and (g) (1) and (3) of this section. The 
licensee shall retain each record required by these sections for three 
years after the close of period for which the licensee possesses the 
special nuclear material under each license that authorizes the licensee 
to export this material. Copies of superseded material must be retained 
for three years after each change.
    (5) Each licensee who imports special nuclear material of low 
strategic significance shall:
    (i) Comply with the requirements specified in paragraphs (c) and (g) 
(2) and (3) of this section and retain each record required by these 
paragraphs for three years after the close of period for which the 
licensee possesses the special nuclear material under each license that 
authorizes the licensee to import this material. Copies of superseded 
material must be retained for three years after each change.
    (ii) Notify the person who delivered the material to a carrier for 
transport of the arrival of such material.

[44 FR 43283, July 24, 1979. Redesignated at 44 FR 68198, Nov. 28, 1979, 
as amended at 45 FR 19215, Mar. 25, 1980; 47 FR 19114, May 4, 1982; 52 
FR 21657, June 9, 1987; 53 FR 19260, May 27, 1988; 57 FR 33431, July 29, 
1992, 59 FR 14087, Mar. 25, 1994; 67 FR 3586, Jan. 25, 2002; 67 FR 
78143, Dec. 23, 2002; 68 FR 14530, Mar. 26, 2003; 68 FR 23575, May 5, 
2003; 73 FR 32463, June 9, 2008; 74 FR 62684, Dec. 1, 2009]

                           Records and Reports



Sec. 73.70  Records.

    Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform provided that the 
copy or microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period. The record may also be stored in electronic media with 
the capability for producing legible, accurate, and complete records 
during the required

[[Page 559]]

retention period. Records such as letters, drawings, specifications, 
must include all pertinent information such as stamps, initials, and 
signatures. The licensee shall maintain adequate safeguards against 
tampering with and loss of records. Each licensee subject to the 
provisions of Sec. Sec. 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 
73.55, or 73.60 shall keep the following records:
    (a) Names and addresses of all individuals who have been designated 
as authorized individuals. The licensee shall retain this record of 
currently designated authorized individuals for the period during which 
the licensee possesses the appropriate type and quantity of special 
nuclear material requiring this record under each license that 
authorizes the activity that is subject to the recordkeeping requirement 
and, for three years thereafter. Copies of superseded material must be 
retained for three years after each change.
    (b) Names, addresses, and badge numbers of all individuals 
authorized to have access to vital equipment or special nuclear 
material, and the vital areas and material access areas to which 
authorization is granted. The licensee shall retain the record of 
individuals currently authorized this access for the period during which 
the licensee possesses the appropriate type and quantity of special 
nuclear material requiring this record under each license that 
authorizes the activity that is subject to the recordkeeping requirement 
and, for three years thereafter. Copies of superseded material must be 
retained for three years after each change.
    (c) A register of visitors, vendors, and other individuals not 
employed by the licensee pursuant to Sec. Sec. 73.46(d)(13), 
73.55(d)(6), or 73.60. The licensee shall retain this register as a 
record, available for inspection, for 3 years after the last entry is 
made in the register.
    (d) A log indicating name, badge number, time of entry, and time of 
exit of all individuals granted access to a vital area except those 
individuals entering or exiting the reactor control room. The licensee 
shall retain this log as a record for three years after the last entry 
is made in the log.
    (e) Documentation of all routine security tours and inspections, and 
of all tests, inspections, and maintenance performed on physical 
barriers, intrusion alarms, communications equipment, and other security 
related equipment used pursuant to the requirements of this part. The 
licensee shall retain the documentation for these events for three years 
from the date of documenting each event.
    (f) A record at each onsite alarm annunciation location of each 
alarm, false alarm, alarm check, and tamper indication that identifies 
the type of alarm, location, alarm circuit, date, and time. In addition, 
details of response by facility guards and watchmen to each alarm, 
intrusion, or other security incident shall be recorded. The license 
shall retain each record for three years after the record is made.
    (g) Shipments of special nuclear material subject to the 
requirements of this part, including names of carriers, major roads to 
be used, flight numbers in the case of air shipments, dates and expected 
times of departure and arrival of shipments, vertification of 
communication equipment on board the transfer vehicle, names of 
individuals who are to communicate with the transport vehicle, container 
seal descriptions and identification, and any other information to 
confirm the means utilized to comply with Sec. Sec. 73.25, 73.26, and 
73.27. This information must be recorded prior to shipment. Information 
obtained during the course of the shipment such as reports of all 
communications, change of shipping plan, including monitor changes, 
trace investigations, and others must also be recorded. The licensee 
shall retain each record about a shipment required by this paragraph (g) 
for three years after the record is made.
    (h) Procedures for controlling access to protected areas and for 
controlling access to keys for locks used to protect special nuclear 
material. The licensee shall retain a copy of the current procedures as 
a record until the Commission terminates each license for which the 
procedures were developed and, if

[[Page 560]]

any portion of the procedure is superseded, retain the superseded 
material for three years after each change.

[53 FR 19261, May 27, 1988, as amended at 57 FR 33431, July 29, 1992]



Sec. 73.71  Reporting of safeguards events.

    (a)(1) Each licensee subject to the provisions of Sec. Sec. 73.25, 
73.26, 73.27(c), 73.37, 73.67(e), or 73.67(g) shall notify the NRC 
Operations Center \3\ within one hour after discovery of the loss of any 
shipment of SNM or spent fuel, and within one hour after recovery of or 
accounting for such lost shipment.
---------------------------------------------------------------------------

    \3\ Commercial telephone number of the NRC Operation Center is (301) 
816-5100.
---------------------------------------------------------------------------

    (2) This notification must be made to the NRC Operations Center via 
the Emergency Notification System, if the licensee is party to that 
system. If the Emergency Notification System is inoperative or 
unavailable, the licensee shall make the required notification via 
commercial telephonic service or other dedicated telephonic system or 
any other methods that will ensure that a report is received by the NRC 
Operations Center within one hour. The exemption of Sec. 73.21(g)(3) 
applies to all telephonic reports required by this section.
    (3) The licensee shall, upon request to the NRC, maintain an open 
and continuous communication channel with the NRC Operations Center.
    (4) The initial telephonic notification must be followed within a 
period of 60 days by a written report submitted to the NRC by an 
appropriate method listed in Sec. 73.4. In addition to the addressees 
specified in Sec. 73.4, the licensee shall also provide one copy of the 
written report addressed to the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response. The report must 
include sufficient information for NRC analysis and evaluation.
    (5) Significant supplemental information which becomes available 
after the initial telephonic notification to the NRC Operations Center 
or after the submission of the written report must be telephonically 
reported to the NRC Operations Center and also submitted in a revised 
written report (with the revisions indicated) to the Regional Office and 
the Document Control Desk. Errors discovered in a written report must be 
corrected in a revised report with revisions indicated. The revised 
report must replace the previous report; the update must be a complete 
entity and not contain only supplementary or revised information. Each 
licensee shall maintain a copy of the written report of an event 
submitted under this section as record for a period of three years from 
the date of the report.
    (b)(1) Each licensee subject to the provisions of Sec. Sec. 73.20, 
73.37, 73.50, 73.51, 73.55, 73.60, or 73.67 shall notify the NRC 
Operations Center within 1 hour of discovery of the safeguards events 
described in paragraph I(a)(1) of appendix G to this part. Licensees 
subject to the provisions of Sec. Sec. 73.20, 73.37, 73.50, 73.51, 
73.55, 73.60, or each licensee possessing strategic special nuclear 
material and subject to Sec. 73.67(d) shall notify the NRC Operations 
Center within 1 hour after discovery of the safeguards events described 
in paragraphs I(a)(2), (a)(3), (b), and (c) of appendix G to this part. 
Licensees subject to the provisions of Sec. Sec. 73.20, 73.37, 73.50, 
73.51, 73.55, or 73.60 shall notify the NRC Operations Center within 1 
hour after discovery of the safeguards events described in paragraph 
I(d) of appendix G to this part.
    (2) This notification must be made in accordance with the 
requirements of paragraphs (a) (2), (3), (4), and (5) of this section.
    (c) Each licensee subject to the provisions of Sec. Sec. 73.20, 
73.37, 73.50, 73.51, 73.55, 73.60, or each licensee possessing SSNM and 
subject to the provisions of Sec. 73.67(d) shall maintain a current log 
and record the safeguards events described in paragraphs II (a) and (b) 
of appendix G to this part within 24 hours of discovery by a licensee 
employee or member of the licensee's contract security organization. The 
licensee shall retain the log of events recorded under this section as a 
record for 3 years after the last entry is made in each log or until 
termination of the license.
    (d) Each licensee shall submit to the Commission the 60-day written 
reports required under the provisions of this section that are of a 
quality that will

[[Page 561]]

permit legible reproduction and processing. If the facility is subject 
to Sec. 50.73 of this chapter, the licensee shall prepare the written 
report on NRC Form 366. If the facility is not subject to Sec. 50.73 of 
this chapter, the licensee shall not use this form but shall prepare the 
written report in letter format. The report must include sufficient 
information for NRC analysis and evaluation.
    (e) Duplicate reports are not required for events that are also 
reportable in accordance with Sec. Sec. 50.72 and 50.73 of this 
chapter.

[52 FR 21658, June 9, 1987; 52 FR 23257, June 18, 1987, as amended at 59 
FR 14087, Mar. 25, 1994; 60 FR 13617, Mar. 14, 1995; 63 FR 26963, May 
15, 1998; 67 FR 3586, Jan. 25, 2002; 68 FR 14530, Mar. 26, 2003; 68 FR 
23575, May 5, 2003; 68 FR 33617, June 5, 2003; 74 FR 62684, Dec. 1, 
2009; 78 FR 29557, May 20, 2013]



Sec. 73.72  Requirement for advance notice of shipment of formula
quantities of strategic special nuclear material, special nuclear
material of moderate strategic significance, or irradiated reactor
fuel.

    (a) A licensee, other than one specified in paragraph (b) of this 
section, who, in a single shipment, plans to deliver to a carrier for 
transport, to take delivery at the point where a shipment is delivered 
to a carrier for transport, to import, to export, or to transport a 
formula quantity of strategic special nuclear material, special nuclear 
material of moderate strategic significance, or irradiated reactor fuel 
\4\ required to be protected in accordance with Sec. 73.37, shall:
---------------------------------------------------------------------------

    \4\ For purposes of 10 CFR 73.72, the terms ``irradiated reactor 
fuel'' as described in 10 CFR 73.37 and ``spent nuclear fuel'' are used 
interchangeably.
---------------------------------------------------------------------------

    (1) Notify in writing the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555, using any appropriate 
method listed in Sec. 73.4 of this part. Classified and safeguards 
notifications shall be sent to the NRC headquarters classified mailing 
address listed in appendix A to this part.
    (2) Assure that the notification will be received at least 10 days 
before transport of the shipment commences at the shipping facility;
    (3) Include the following information in the notification:
    (i) The name(s), address(es), and telephone number(s) of the 
shipper, receiver, and carrier(s);
    (ii) A physical description of the shipment:
    (A) For a shipment other than irradiated fuel, the elements, 
isotopes, enrichment, and quantity;
    (B) For a shipment of irradiated fuel, the physical form, quantity, 
type of reactor, and original enrichment;
    (iii) A listing of the mode(s) of shipment, transfer point(s), and 
route(s) to be used;
    (iv) The estimated time and date that shipment will commence and 
that each country along the route is scheduled to be entered; and
    (v) The estimated time and date of arrival of the shipment at the 
destination;
    (4) The NRC Headquarters Operations Center shall be notified about 
the shipment status by telephone at the phone numbers listed in appendix 
A to this part. Classified and safeguards notifications shall be made by 
secure telephone. The notifications shall take place at the following 
intervals:
    (i) At least 2 days before commencement of the shipment;
    (ii) Two hours before commencement of the shipment; and
    (iii) Once the shipment is received at its destination.
    (5) The NRC Headquarters Operations Center shall be notified by 
telephone of schedule changes of more than 6 hours at the phone numbers 
listed in appendix A to this part. Classified and safeguards 
notifications shall be made by secure telephone.
    (b) A licensee who conducts an on-site transfer of spent nuclear 
fuel that does not travel upon or cross a public highway is exempt from 
the requirements of this section for that transfer.

[52 FR 9653, Mar. 26, 1987, as amended at 53 FR 4111, Feb. 12, 1988; 60 
FR 24552, May 9, 1995; 67 FR 3586, Jan. 25, 2002; 68 FR 58820, Oct. 10, 
2003; 74 FR 62684, Dec. 1, 2009; 78 FR 29557, May 20, 2013]

[[Page 562]]



Sec. 73.73  Requirement for advance notice and protection of export
shipments of special nuclear material of low strategic significance.

    (a) A licensee authorized to export special nuclear material of low 
strategic significance shall:
    (1) Notify in writing the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, using any appropriate 
method listed in Sec. 73.4;
    (2) Assure that the notification will be received at least 10 days 
before transport of the shipment commences at the shipper's facility;
    (3) Include the following information in the notification:
    (i) The name(s), address(es), and telephone number(s) of the 
shipper, receiver, and carrier(s);
    (ii) A physical description of the shipment (the elements, isotopes, 
form, etc.);
    (iii) A listing of the mode(s) of shipment, transfer points, and 
routes to be used;
    (iv) The estimated time and date that shipment will commence and 
that each country along the route is scheduled to be entered; and
    (v) The estimated time and date of arrival of the shipment at the 
destination;
    (4) Assure that during transport outside the United States, the 
shipment will be protected in accordance with Annex I to the Convention 
on the Physical Protection of Nuclear Material (see appendix E of this 
part).
    (b) A licensee who needs to amend a written advance notification 
required by paragraph (a) of this section may notify the NRC 
Headquarters Operations Center by telephone at the numbers listed in 
appendix A to this part.

[52 FR 9653, Mar. 26, 1987, as amended at 53 FR 4112, Feb. 12, 1988; 60 
FR 24553, May 9, 1995; 67 FR 3586, Jan. 25, 2002; 68 FR 58820, Oct. 10, 
2003; 74 FR 62684, Dec. 1, 2009]



Sec. 73.74  Requirement for advance notice and protection of import
shipments of nuclear material from countries that are not party to
the Convention on the Physical Protection of Nuclear Material.

    (a) A licensee authorized to import special nuclear material of low 
strategic significance from a country not a party to the Convention on 
the Physical Protection of Nuclear Material (i.e., not listed in 
appendix F of this part) shall:
    (1) Notify in writing the Director, Division of Security Policy, 
Office of Nuclear Security and Incident Response, using any appropriate 
method listed in Sec. 73.4;
    (2) Assure that the notification will be received at least 10 days 
before transport of the shipment commences at the shipper's facility; 
and
    (3) Include the following information in the notification:
    (i) The name(s), address(es) and telephone number(s) of the shipper, 
receiver, and carrier(s);
    (ii) A physical description of the shipment (the isotopes, 
enrichment, quantity, etc.);
    (iii) A listing of mode(s) of shipment, transfer points, and routes 
to be used;
    (iv) The estimated time and date that shipment will commence and 
that each country along the route is scheduled to be entered; and
    (v) The estimated time and date of arrival of the shipment at the 
destination.
    (b) A licensee who needs to amend a written advance notification 
required by paragraph (a) of this section may notify the NRC 
Headquarters Operations Center by telephone at the numbers listed in 
appendix A to this part.
    (c) A licensee authorized to import from a country not a party to 
the Convention on the Physical Protection of Nuclear Material (i.e., not 
listed in appendix F of this part) a formula quantity of special nuclear 
material, special nuclear material of moderate strategic significance, 
special nuclear material of low strategic significance, or irradiated 
reactor fuel shall assure that during transport outside the United 
States the shipment will be protected in accordance with Annex I to the 
Convention on the Physical Protection of Nuclear Material (see appendix 
E of this part).

[52 FR 9654, Mar. 26, 1987, as amended at 53 FR 4112, Feb. 12, 1988; 60 
FR 24553, May 9, 1995; 67 FR 3586, Jan. 25, 2002; 68 FR 58820, Oct. 10, 
2003; 74 FR 62684, Dec. 1, 2009]



Sec. 73.75  Posting.

    (a) This section applies to:

[[Page 563]]

    (1) Production or utilization facilities;
    (2) High-level waste storage or disposal facilities and independent 
spent fuel storage installations;
    (3) Uranium enrichment, uranium conversion, or nuclear fuel 
fabrication facilities.
    (b)(1) Licensees or certificate holders operating facilities 
described in paragraph (a) of this section that have a protected area 
shall conspicuously post notices at every vehicle and pedestrian 
entrance to the protected area.
    (2) Licensees or certificate holders operating facilities described 
in paragraph (a) of this section that include buildings not within a 
protected area that nonetheless contain special nuclear material, 
byproduct material, or source material shall conspicuously post notices 
at the personnel and vehicle entrances to each such building, except 
with respect to buildings for which no security plan is required under 
this part.
    (3) The required notices must state: ``The willful unauthorized 
introduction of any dangerous weapon, explosive, or other dangerous 
instrument or material likely to produce substantial injury or damage to 
persons or property into or upon these premises is a Federal crime. (42 
U.S.C. 2278a.)''
    (4) Every notice posted under this section must be easily readable 
day and night by both pedestrian and vehicular traffic entering the 
facility or installation.
    (5) These notices may be combined with other notices.
    (c) This section does not apply to facilities that, in addition to 
being regulated by the NRC under a license or certificate of compliance 
issued by the Commission, are also covered by U.S. Department of Energy 
regulations imposing criminal penalties, and associated posting 
requirements, under section 229 of the Atomic Energy Act with respect to 
unauthorized introduction of dangerous weapons, explosives, or other 
dangerous instruments or materials likely to produce substantial injury 
or damage to persons or property.

[74 FR 52674, Oct. 14, 2009]



Sec. 73.77  Cyber security event notifications.

    (a) Each licensee subject to the provisions of Sec. 73.54 shall 
notify the NRC Headquarters Operations Center via the Emergency 
Notification System (ENS), in accordance with paragraph (c) of this 
section:
    (1) Within one hour after discovery of a cyber attack that adversely 
impacted safety-related or important-to-safety functions, security 
functions, or emergency preparedness functions (including offsite 
communications); or that compromised support systems and equipment 
resulting in adverse impacts to safety, security, or emergency 
preparedness functions within the scope of Sec. 73.54.
    (2) Within four hours:
    (i) After discovery of a cyber attack that could have caused an 
adverse impact to safety-related or important-to-safety functions, 
security functions, or emergency preparedness functions (including 
offsite communications); or that could have compromised support systems 
and equipment, which if compromised, could have adversely impacted 
safety, security, or emergency preparedness functions within the scope 
of Sec. 73.54.
    (ii) After discovery of a suspected or actual cyber attack initiated 
by personnel with physical or electronic access to digital computer and 
communication systems and networks within the scope of Sec. 73.54.
    (iii) After notification of a local, State, or other Federal agency 
(e.g., law enforcement, FBI, etc.) of an event related to the licensee's 
implementation of their cyber security program for digital computer and 
communication systems and networks within the scope of Sec. 73.54 that 
does not otherwise require a notification under paragraph (a) of this 
section.
    (3) Within eight hours after receipt or collection of information 
regarding observed behavior, activities, or statements that may indicate 
intelligence gathering or pre-operational planning related to a cyber 
attack against digital computer and communication systems and networks 
within the scope of Sec. 73.54.

[[Page 564]]

    (b) Twenty-four hour recordable events. (1) The licensee shall use 
the site corrective action program to record vulnerabilities, 
weaknesses, failures and deficiencies in their Sec. 73.54 cyber 
security program within twenty-four hours of their discovery.
    (2) The licensee shall use the site corrective action program to 
record notifications made under paragraph (a) of this section within 
twenty-four hours of their discovery.
    (c) Notification process. (1) Each licensee shall make telephonic 
notifications required by paragraph (a) of this section to the NRC 
Headquarters Operations Center via the ENS. If the ENS is inoperative or 
unavailable, the licensee shall make the notification via a commercial 
telephone service or other dedicated telephonic system or any other 
methods that will ensure a report is received by the NRC Headquarters 
Operations Center within the timeframe. Commercial telephone numbers for 
the NRC Headquarters Operations Center are specified in appendix A to 
this part.
    (2) Notifications required by this section that contain Safeguards 
Information may be made to the NRC Headquarters Operations Center 
without using secure communications systems under the exception in Sec. 
73.22(f)(3) for emergency or extraordinary conditions.
    (3) Notifications required by this section that contain Safeguards 
Information and/or classified national security information and/or 
restricted data must be made to the NRC Headquarters Operations Center 
using secure communications systems appropriate to the sensitivity/
classification level of the message. Licensees making these types of 
telephonic notifications must contact the NRC Headquarters Operations 
Center at the commercial numbers specified in appendix A to this part 
and request a transfer to a secure telephone.
    (i) If the licensee's secure communications capability is 
unavailable (e.g., due to the nature of the security event), the 
licensee must provide as much information to the NRC as is required by 
this section, without revealing or discussing any Safeguards Information 
and/or Classified Information, in order to meet the timeliness 
requirements of this section. The licensee must also indicate to the NRC 
that its secure communications capability is unavailable.
    (ii) Licensees using a non-secure communications capability may be 
directed by the NRC Emergency Response management to provide classified 
information to the NRC over the non-secure system, due to the 
significance of the ongoing security event. In such circumstances, the 
licensee must document this direction and any information provided to 
the NRC over a non-secure communications capability in the written 
security follow-up report required in accordance with paragraph (d) of 
this section.
    (4) For events reported under paragraph (a)(1) of this section, the 
NRC may request that the licensee maintain an open and continuous 
communication channel with the NRC Headquarters Operations Center.
    (5) Licensees desiring to retract a previous security event report 
that has been determined to not meet the threshold of a reportable event 
must telephonically notify the NRC Headquarters Operations Center and 
indicate the report being retracted and basis for the retraction.
    (6) Declaration of emergencies. Notifications made to the NRC for 
the declaration of an emergency class shall be performed in accordance 
with Sec. 50.72 of this chapter, as applicable.
    (7) Elimination of duplication. Separate notifications and reports 
are not required for events that are also reportable in accordance with 
Sec. Sec. 50.72 and 50.73 of this chapter. However, these notifications 
should also indicate the applicable Sec. 73.77 reporting criteria.
    (d) Written security follow-up reports. Each licensee making an 
initial telephonic notification of security events to the NRC according 
to the provisions of paragraphs (a)(1), (a)(2)(i), and (a)(2)(ii) of 
this section must also submit a written security follow-up report to the 
NRC within 60 days of the telephonic notification in accordance with 
Sec. 73.4.
    (1) Licensees are not required to submit a written security follow-
up report following a telephonic notification made under Sec. 
73.77(a)(2)(iii) or (a)(3).

[[Page 565]]

    (2) Each licensee shall submit to the NRC written security follow-up 
reports that are of a quality that will permit legible reproduction and 
processing.
    (3) Licensees shall prepare the written security follow-up report on 
NRC Form 366.
    (4) In addition to the addressees specified in Sec. 73.4, the 
licensee shall also provide one copy of the written security follow-up 
report addressed to the Director, Office of Nuclear Security and 
Incident Response, or the Director's designee. Any written security 
follow-up reports containing classified information shall be transmitted 
to the NRC Headquarters' classified mailing address as specified in 
appendix A to this part.
    (5) The written security follow-up report must include sufficient 
information for NRC analysis and evaluation.
    (6) Significant supplemental information which becomes available 
after the initial telephonic notification to the NRC Headquarters 
Operations Center or after the submission of the written security 
follow-up report must be telephonically reported to the NRC Headquarters 
Operations Center under paragraph (c) of this section and also submitted 
in a revised written security follow-up report (with the revisions 
indicated) as required under this section.
    (7) Errors discovered in a written security follow-up report must be 
corrected in a revised written security follow-up report with the 
revision(s) indicated.
    (8) The revised written security follow-up report must replace the 
previous written security follow-up report; the update must be complete 
and not be limited to only supplementary or revised information.
    (9) If the licensee subsequently retracts a telephonic notification 
made under this section as not meeting the threshold of a reportable 
event, and has not yet submitted a written security follow-up report 
then submission of a written security follow-up report is not required.
    (10) If the licensee subsequently retracts a telephonic notification 
made under this section as not meeting the threshold of a reportable 
event after it has submitted a written security follow-up report 
required by this paragraph, then the licensee shall submit a revised 
written security follow-up report in accordance with this paragraph.
    (11) Each written security follow-up report submitted containing 
Safeguards Information or Classified Information must be created, 
stored, marked, labeled, handled, and transmitted to the NRC according 
to the requirements of Sec. Sec. 73.21 and 73.22 or with part 95 of 
this chapter, as applicable.
    (12) Each licensee shall maintain a copy of the written security 
follow-up report of an event submitted under this section as a record 
for a period of three years from the date of the report or until the 
Commission terminates the license for which the records were developed, 
whichever comes first.

[80 FR 67275, Nov. 2, 2015]

                               Enforcement



Sec. 73.80  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended:
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
Section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55078, Nov. 24, 1992]

[[Page 566]]



Sec. 73.81  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 73 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 73 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 73.1, 73.2, 73.3, 73.4, 73.5, 73.6, 73.8, 73.25, 73.45, 
73.75, 73.80, and 73.81.
    (c)(1) No person without authorization may carry, transport, or 
otherwise introduce or cause to be introduced any dangerous weapon, 
explosive, or other dangerous instrument or material likely to produce 
substantial injury or damage to persons or property into or upon a 
protected facility or installation. Willful violations of this provision 
are punishable by the criminal penalties set forth in sections 229b and 
229c of the Atomic Energy Act of 1954, as amended.
    (2) As used in this section:
    (i) ``Protected facility or installation'' means any production or 
utilization facility, high-level waste storage or disposal facility, 
independent spent fuel storage installation, uranium enrichment, uranium 
conversion, or nuclear fuel fabrication facility, but does not include 
those portions of such facilities that are not required under Sec. 
73.75(b) of this part to be identified by notices posted at their 
pedestrian and vehicle entrances, and does not include facilities 
described in Sec. 73.75(c) of this part.
    (ii) ``Without authorization'' means not authorized as part of one's 
official duties to carry the weapon, explosive, or other instrument or 
material;
    (iii) ``Dangerous weapon'' includes any firearm, as defined in 
either 18 U.S.C. 921 or 26 U.S.C. 5845, or dangerous weapon, as defined 
in 18 U.S.C. 930;
    (iv) ``Explosive'' means any explosive as defined in 18 U.S.C. 
844(j).
    (3) An item, such as a dangerous weapon, explosive, or other 
dangerous instrument or material, is considered to have been carried, 
transported, or otherwise introduced or caused to be introduced into or 
upon a protected facility or installation for purposes of paragraph 
(c)(1) of this section once the item has traveled past a notice posted 
pursuant to Sec. 73.75 of this part at a vehicle or pedestrian entrance 
to the protected facility, or once the item has entered the protected 
facility or installation at a location that is not a vehicle or 
pedestrian entrance to the facility, whether such entry is accomplished 
through, over, under, or around a fence, wall, floor, roof, or other 
structural barrier enclosing the protected facility or installation or 
by any other means.
    (4) For all protected facilities or installations that do not 
possess special nuclear material, byproduct material, or source material 
as of the effective date of this rule, this provision shall take effect 
upon receipt of such material at the applicable facility or 
installation.

[57 FR 55079, Nov. 24, 1992, as amended at 74 FR 52674, Oct. 14, 2009]



 Appendix A to Part 73--U.S. Nuclear Regulatory Commission Offices and 
                      Classified Mailing Addresses

----------------------------------------------------------------------------------------------------------------
                                               Address            Telephone (24 hour)             E-Mail
----------------------------------------------------------------------------------------------------------------
NRC Headquarters Operations Center     USNRC, Division of       (301) 816-5100, (301)    [email protected]
                                        Incident Response        951-0550, (301) 816-
                                        Operations,              5151 (fax).
                                        Washington, DC 20555-
                                        0001.

[[Page 567]]

 
Region I: Connecticut, Delaware,       USNRC, Region I, 2100    (610) 337-5000, (800)    RidsRgn1MailCenter@nrc.
 District of Columbia, Maine,           Renaissance Boulevard,   432-1156 TDD: (301)      gov
 Maryland, Massachusetts, New           Suite 100, King of       415-5575.
 Hampshire, New Jersey, New York,       Prussia, PA 19406-2713.
 Pennsylvania, Rhode Island, and
 Vermont
Region II: Alabama, Florida, Georgia,  USNRC, Region II, 245    (404) 997-4000, (800)    RidsRgn2Mail
 Kentucky, North Carolina, Puerto       Peachtree Center         877-8510, TDD: (301)     [email protected]
 Rico, South Carolina, Tennessee,       Avenue, NE., Suite       415-5575.
 Virginia, Virgin Islands, and West     1200, Atlanta, GA
 Virginia                               30303-1257.
Region III: Illinois, Indiana, Iowa,   USNRC, Region III, 2443  (630) 829-9500, (800)    RidsRgn3MailCenter@nrc.
 Michigan, Minnesota, Missouri, Ohio    Warrenville Road,        522-3025, TDD: (301)     gov
 and Wisconsin                          Suite 210, Lisle, IL     415-5575.
                                        60532-4352.
Region IV: Alaska, Arizona, Arkansas,  US NRC, Region IV, 1600  (817) 860-8100, (800)    RidsRgn4MailCenter@nrc.
 California, Colorado, Hawaii, Idaho,   E. Lamar Blvd.,          952-9677, TDD: (301)     gov
 Kansas, Louisiana, Mississippi,        Arlington, TX 76011-     415-5575.
 Montana, Nebraska, Nevada, New         4511.
 Mexico, North Dakota, Oklahoma,
 Oregon, South Dakota, Texas, Utah,
 Washington, Wyoming, and the U.S.
 territories and possessions in the
 Pacific
----------------------------------------------------------------------------------------------------------------


                      Classified Mailing Addresses
------------------------------------------------------------------------
                                                           Address
------------------------------------------------------------------------
NRC Headquarters..................................  U.S. NRC, Caller Box
                                                     2500, Rockville, MD
                                                     20852.
Region I..........................................  U.S. NRC, 475
                                                     Allendale Road,
                                                     King of Prussia, PA
                                                     19406.
Region II.........................................  USNRC, P.O. Box
                                                     56267, Atlanta, GA
                                                     30343.
Region III........................................  USNRC, Region III,
                                                     2443 Warrenville
                                                     Road, Suite 210,
                                                     Lisle, IL 60532-
                                                     4352.
Region IV.........................................  US NRC, Region IV,
                                                     1600 E. Lamar
                                                     Blvd., Arlington,
                                                     TX 76011-4511.
------------------------------------------------------------------------

    I. Classified mail shall be transmitted in accordance with Sec. 
95.39 of this chapter to the appropriate NRC classified mailing address 
listed in this appendix.
    II. Classified documents may be hand delivered to the NRC to the 
appropriate NRC street address listed in this appendix. Hand delivered 
classified documents shall be transmitted in accordance with Sec. 95.39 
of this chapter.

[68 FR 58820, Oct. 10, 2003, as amended at 71 FR 15012, Mar. 27, 2006; 
73 FR 30460, May 28, 2008; 75 FR 21981, Apr. 27, 2010; 76 FR 72086, Nov. 
22, 2011; 77 FR 39909, July 6, 2012; 79 FR 66606, Nov. 10, 2014; 82 FR 
52825, Nov. 15, 2017]



   Sec. Appendix B to Part 73--General Criteria for Security Personnel

                            Table of Contents

Introduction.
Definitions.
Criteria.
I. Employment suitability and qualification.
A. Suitability.
B. Physical and mental qualifications.
C. Medical examination and physical fitness qualifications.
D. Contract security personnel.
E. Physical and medical requalification.
F. Documentation.
II. Training and qualifications.
A. Training requirements.
B. Qualification requirements.
C. Contract personnel.
D. Security knowledge, skills, and abilities.
E. Requalification.
III. Weapons training and qualification.
IV. Weapons qualification and requalification program.
V. Guard, armed response personnel, and armed escort equipment.
A. Fixed site.
B. Transportation.
VI. Nuclear Power Reactor Training and Qualification Plan for Personnel 
Performing Security Program Duties
A. General Requirements and Introduction
B. Employment Suitability and Qualification

[[Page 568]]

C. Duty Training
D. Duty Qualification and Requalification
E. Weapons Training
F. Weapons Qualification and Requalification Program
G. Weapons, Personal Equipment and Maintenance
H. Records
I. Reviews
J. Definitions

                              Introduction

    Applicants and power reactor licensees subject to the requirements 
of Sec. 73.55 shall comply only with the requirements of section VI of 
this appendix. All other licensees, applicants, or certificate holders 
shall comply only with sections I through V of this appendix.
    Security personnel who are responsible for the protection of special 
nuclear material on site or in transit and for the protection of the 
facility or shipment vehicle against radiological sabotage should, like 
other elements of the physical security system, be required to meet 
minimum criteria to ensure that they will effectively perform their 
assigned security-related job duties. In order to ensure that those 
individuals responsible for security are properly equipped and qualified 
to execute the job duties prescribed for them, the NRC has developed 
general criteria that specify security personnel qualification 
requirements.
    These general criteria establish requirements for the selection, 
training, equipping, testing, and qualification of individuals who will 
be responsible for protecting special nuclear materials, nuclear 
facilities, and nuclear shipments.
    When required to have security personnel that have been trained, 
equipped, and qualified to perform assigned security job duties in 
accordance with the criteria in this appendix, the licensee must 
establish, maintain, and follow a plan that shows how the criteria will 
be met. The plan must be submitted to the NRC for approval and must be 
implemented within 30 days after approval by the NRC unless otherwise 
specified by the NRC in writing.

                               Definitions

    Terms defined in parts 50, 70, and 73 of this chapter have the same 
meaning when used in this appendix.

                                Criteria

I. Employment suitability and qualification.
    A. Suitability: 1. Prior to employment, or assignment to the 
security organization, an individual shall meet the following 
suitability criteria:
    a. Educational development--Possess a high school diploma or pass an 
equivalent performance examination designed to measure basic job-related 
mathematical, language, and reasoning skills, ability, and knowledge, 
required to perform security job duties.
    b. Felony convictions--Have no felony convictions involving the use 
of a weapon and no felony convictions that reflect on the individual's 
reliability.
    2. Prior to employment or assignment to the security organization in 
an armed capacity, the individual, in addition to (a) and (b) above, 
must be 21 years of age or older.
    B. Physical and mental qualifications. 1. Physical qualifications:
    a. Individuals whose security tasks and job duties are directly 
associated with the effective implementation of the licensee physical 
security and contingency plans shall have no physical weaknesses or 
abnormalities that would adversely affect their performance of assigned 
security job duties.
    b. In addition to a. above, guards, armed response personnel, armed 
escorts, and central alarm station operators shall successfully pass a 
physical examination administered by a licensed physician. The 
examination shall be designed to measure the individual's physical 
ability to perform assigned security job duties as identified in the 
licensee physical security and contingency plans. Armed personnel shall 
meet the following additional physical requirements:
    (1) Vision: (a) For each individual, distant visual acuity in each 
eye shall be correctable to 20/30 (Snellen or equivalent) in the better 
eye and 20/40 in the other eye with eyeglasses or contact lenses. If 
uncorrected distance vision is not at least 20/40 in the better eye, the 
individual shall carry an extra pair of corrective lenses. Near visual 
acuity, corrected or uncorrected, shall be at least 20/40 in the better 
eye. Field of vision must be at least 70[deg] horizontal meridian in 
each eye. The ability to distinguish red, green, and yellow colors is 
required. Loss of vision in one eye is disqualifying. Glaucoma shall be 
disqualifying, unless controlled by acceptable medical or surgical 
means, provided such medications as may be used for controlling glaucoma 
do not cause undesirable side effects which adversely affect the 
individual's ability to perform assigned security job duties, and 
provided the visual acuity and field of vision requirements stated above 
are met. On-the-job evaluation shall be used for individuals who exhibit 
a mild color vision defect.
    (b) Where corrective eyeglasses are required, they shall be of the 
safety glass type.
    (c) The use of corrective eyeglasses or contact lenses shall not 
interfere with an individual's ability to effectively perform assigned 
security job duties during normal or emergency operations.
    (2) Hearing: (a) Individuals shall have no hearing loss in the 
better ear greater than 30 decibels average at 500 Hz, 1,000 Hz, and 
2,000

[[Page 569]]

Hz with no level greater that 40 decibels at any one frequency (by ISO 
389 ``Standard Reference Zero for the Calibration of Puritone 
Audiometer'' (1975) or ANSI S3.6-1969 (R. 1973) ``Specifications for 
Audiometers''). ISO 389 and ANSI S3.6-1969 have been approved for 
incorporation by reference by the Director of the Federal Register. A 
copy of each standard is available for inspection at the NRC Library, 
11545 Rockville Pike, Rockville, Maryland 20852-2738.
    (b) A hearing aid is acceptable provided suitable testing procedures 
demonstrate auditory acuity equivalent to the above stated requirement.
    (c) The use of a hearing aid shall not decrease the effective 
performance of the individual's assigned security job duties during 
normal or emergency operations.
    (3) Diseases--Individuals shall have no established medical history 
or medical diagnosis of epilepsy or diabetes, or, where such a condition 
exists, the individual shall provide medical evidence that the condition 
can be controlled with proper medication so that the individual will not 
lapse into a coma or unconscious state while performing assigned 
security job duties.
    (4) Addiction--Individuals shall have no established medical history 
or medical diagnosis of habitual alcoholism or drug addiction, or, where 
such a condition has existed, the individual shall provide certified 
documentation of having completed a rehabilitation program which would 
give a reasonable degree of confidence that the individual would be 
capable of performing assigned security job duties.
    (5) Other physical requirements--An individual who has been 
incapacitated due to a serious illness, injury, disease, or operation, 
which could interfere with the effective performance of assigned 
security job duties shall, prior to resumption of such duties, provide 
medical evidence of recovery and ability to perform such security job 
duties.
    2. Mental qualifications: a. Individuals whose security tasks and 
job duties are directly associated with the effective implementation of 
the licensee physical security and contingency plans shall demonstrate 
mental alertness and the capability to exercise good judgment, implement 
instructions, assimilate assigned security tasks, and possess the acuity 
of senses and ability of expression sufficient to permit accurate 
communication by written, spoken, audible, visible, or other signals 
required by assigned job duties.
    b. Armed individuals, and central alarm station operators, in 
addition to meeting the requirement stated in paragraph a. above, shall 
have no emotional instability that would interfere with the effective 
performance of assigned security job duties. The determination shall be 
made by a licensed psychologist or psychiatrist, or physician, or other 
person professionally trained to identify emotional instability.
    c. The licensee shall arrange for continued observation of security 
personnel and for appropriate corrective measures by responsible 
supervisors for indications of emotional instability of individuals in 
the course of performing assigned security job duties. Identification of 
emotional instability by responsible supervisors shall be subject to 
verification by a licensed, trained person.
    C. Medical examinations and physical fitness qualifications--Guards, 
armed response personnel, armed escorts and other armed security force 
members shall be given a medical examination including a determination 
and written certification by a licensed physician that there are no 
medical contraindications as disclosed by the medical examination to 
participation by the individual in physical fitness tests. Subsequent to 
this medical examination, guards, armed response personnel, armed 
escorts and other armed security force members shall demonstrate 
physical fitness for assigned security job duties by performing a 
practical physical exercise program within a specific time period. The 
exercise program performance objectives shall be described in the 
license training and qualifications plan and shall consider job-related 
functions such as strenuous activity, physical exertion, levels of 
stress, and exposure to the elements as they pertain to each 
individual's assigned security job duties for both normal and emergency 
operations. The physical fitness qualification of each guard, armed 
response person, armed escort, and other security force member shall be 
documented and attested to by a licensee security supervisor. The 
licensee shall retain this documentation as a record for three years 
from the date of each qualification.
    D. Contract security personnel--Contract security personnel shall be 
required to meet the suitability, physical, and mental requirements as 
appropriate to their assigned security job duties in accordance with 
section I of this appendix.
    E. Physical requalification--At least every 12 months, central alarm 
station operators shall be required to meet the physical requirements of 
B.1.b of this section, and guards, armed response personnel, and armed 
escorts shall be required to meet the physical requirements of 
paragraphs B.1.b (1) and (2), and C of this section. The licensee shall 
document each individual's physical requalification and shall retain 
this documentation of requalification as a record for three years from 
the date of each requalification.
    F. Documentation--The results of suitability, physical, and mental 
qualifications data and test results must be documented by the licensee 
or the licensee's agent. The licensee or the agent shall retain this 
documentation as a record for three years from

[[Page 570]]

the date of obtaining and recording these results.
    G. Nothing herein authorizes or requires a licensee to investigate 
into or judge the reading habits, political or religious beliefs, or 
attitudes on social, economic, or political issues of any person.

II. Training and qualifications.
    A. Training requirements--Each individual who requires training to 
perform assigned security-related job tasks or job duties as identified 
in the licensee physical security or contingency plans shall, prior to 
assignment, be trained to perform these tasks and duties in accordance 
with the licensee or the licensee's agent's documented training and 
qualifications plan. The licensee or the agent shall maintain 
documentation of the current plan and retain this documentation of the 
plan as a record for three years after the close of period for which the 
licensee possesses the special nuclear material under each license for 
which the plan was developed and, if any portion of the plan is 
superseded, retain the material that is superseded for three years after 
each change.
    B. Qualification requirements--Each person who performs security-
related job tasks or job duties required to implement the licensee 
physical security or contingency plan shall, prior to being assigned to 
these tasks or duties, be qualified in accordance with the licensee's 
NRC-approved training and qualifications plan. The qualifications of 
each individual must be documented and attested by a licensee security 
supervisor. The licensee shall retain this documentation of each 
individual's qualifications as a record for three years after the 
employee ends employment in the security-related capacity and for three 
years after the close of period for which the licensee possesses the 
special nuclear material under each license, and superseded material for 
three years after each change.
    C. Contract personnel--Contract personnel shall be trained, 
equipped, and qualified as appropriate to their assigned security-
related job tasks or job duties, in accordance with sections II, III, 
IV, and V of this appendix. The qualifications of each individual must 
be documented and attested by a licensee security supervisor. The 
licensee shall retain this documentation of each individual's 
qualifications as a record for three years after the employee ends 
employment in the security-related capacity and for three years after 
the close of period for which the licensee possesses the special nuclear 
material under each license, and superseded material for three years 
after each change.
    D. Security knowledge, skills, and abilities--Each individual 
assigned to perform the security related task identified in the licensee 
physical security or contingency plan shall demonstrate the required 
knowledge, skill, and ability in accordance with the specified standards 
for each task as stated in the NRC approved licensee training and 
qualifications plan. The areas of knowledge, skills, and abilities that 
shall be considered in the licensee's training and qualifications plan 
are as follows:
    1. Protection of nuclear facilities, transport vehicles, and special 
nuclear material.
    2. NRC requirements and guidance for physical security at nuclear 
facilities and for transportation.
    3. The private security guard's role in providing physical 
protection for the nuclear industry.
    4. The authority of private guards.
    5. The use of nonlethal weapons.
    6. The use of deadly force.
    7. Power of arrest and authority to detain individuals.
    8. Authority to search individuals and seize property.
    9. Adversary group operations.
    10. Motivation and objectives of adversary groups.
    11. Tactics and force that might be used by adversary groups to 
achieve their objectives.
    12. Recognition of sabotage related devices and equipment that might 
be used against the licensee's facility or shipment vehicle.
    13. Facility security organization and operation.
    14. Types of physical barriers.
    15. Weapons, lock and key control system operation.
    16. Location of SNM and/or vital areas within a facility.
    17. Protected area security and vulnerability.
    18. Types of alarm systems used.
    19. Response and assessment to alarm annunciations and other 
indications of intrusion.
    20. Familiarization with types of special nuclear material 
processed.
    21. General concepts of fixed site security systems.
    22. Vulnerabilities and consequences of theft of special nuclear 
material or radiological sabotage of a facility.
    23. Protection of security system information.
    24. Personal equipment use and operation for normal and contingency 
operations.
    25. Surveillance and assessment systems and techniques.
    26. Communications systems operation, fixed site.
    27. Access control systems and operation for individuals, packages, 
and vehicles.
    28. Contraband detection systems and techniques.
    29. Barriers and other delay systems around material access or vital 
areas.
    30. Exterior and interior alarm systems operation.
    31. Duress alarm operation.
    32. Alarm stations operation.

[[Page 571]]

    33. Response force organization.
    34. Response force mission.
    35. Response force operation.
    36. Response force engagement.
    37. Security command and control system during normal operation.
    38. Security command and control system during contingency 
operation.
    39. Transportation systems security organization and operation.
    40. Types of SNM transport vehicles.
    41. Types of SNM escort vehicles.
    42. Modes of transportation for SNM.
    43. Road transport security system command and control structure.
    44. Use of weapons.
    45. Communications systems operation for transportation, shipment to 
control center and intraconvoy.
    46. Vulnerabilities and consequences of theft of special nuclear 
material or radiological sabotage of a transport vehicle.
    47. Protection of transport system security information.
    48. Control of area around transport vehicle.
    49. Normal convoy techniques and operations.
    50. Familiarization with types of special nuclear materials shipped.
    51. Fixed post station operations.
    52. Access control system operation.
    53. Search techniques and systems for individuals, packages and 
vehicles.
    54. Escort and patrol responsibilities and operation.
    55. Contengency response to confirmed intrusion or attempted 
intrusion.
    56. Security system operation after component failure.
    57. Fixed site security information protection.
    58. Security coordination with local law enforcement agencies.
    59. Security and situation reporting, documentation and report 
writing.
    60. Contingency duties.
    61. Self defense.
    62. Use of and defenses against incapacitating agents.
    63. Security equipment testing.
    64. Contingency procedures.
    65. Night vision devices and systems.
    66. Mechanics of detention.
    67. Basic armed and unarmed defensive tactics.
    68. Response force deployment.
    69. Security alert procedures.
    70. Security briefing procedures.
    71. Response force tactical movement.
    72. Response force withdrawal.
    73. Reponse force use of support fire.
    74. Response to bomb and attack threats.
    75. Response to civil disturbances (e.g., strikes, demonstrators).
    76. Response to confirmed attempted theft of special nuclear 
material and/or radiological sabotage of facilities.
    77. Response to hostage situations.
    78. Site specific armed tactical procedures and operation.
    79. Security response to emergency situations other than security 
incidents.
    80. Basic transportation defensive response tactics.
    81. Armed escort deployment.
    82. Armed escort adversary engagement.
    83. Armed escort formations.
    84. Armed escort use of weapons fire (tactical and combat).
    85. Armed escort and shipment movement under fire.
    86. Tactical convoying techniques and operations.
    87. Armed escort tactical exercises.
    88. Armed escort response to bomb and attack threats.
    89. Verification of shipment documentation and contents.
    90. Continuous surveillance of shipment vehicle.
    91. Normal and contingency operation for shipment mode transfer.
    92. Armed personnel procedures and operation during temporary 
storage between mode transfers of shipments.
    93. Armed escort threat assessment and response.
    94. System for and operation of shipment vehicle lock and key 
control.
    95. Techniques and procedures for isolation of shipment vehicle 
during a contingency situation.
    96. Transportation coordination with local law enforcement agencies.
    97. Procedures for verification of shipment locks and seals.
    98. Transportation security and situation reporting, documentation, 
and report writing.
    99. Procedures for shipment delivery and pickup.
    100. Transportation security system for escort by road, rail, air 
and sea.
    E. Requalification--Security personnel shall be requalified at least 
every 12 months to perform assigned security-related job tasks and 
duties for both normal and contingency operations. Requalification shall 
be in accordance with the NRC-approved licensee training and 
qualifications plan. The results of requalification must be documented 
and attested by a licensee security supervisor. The licensee shall 
retain this documentation of each individual's requalification as a 
record for three years from the date of each requalification.

III. Weapons training.
    A. Guards, armed response personnel and armed escorts requiring 
weapons training to perform assigned security related job tasks or job 
duties shall be trained in accordance

[[Page 572]]

with the licensees' documented weapons training programs. Each 
individual shall be proficient in the use of his assigned weapon(s) and 
shall meet prescribed standards in the following areas:
    1. Mechanical assembly, dissasembly, range penetration capability of 
weapon, and bullseye firing.
    2. Weapons cleaning and storage.
    3. Combat firing, day and night.
    4. Safe weapons handling.
    5. Clearing, loading, unloading, and reloading.
    6. When to draw and point a weapon.
    7. Rapid fire techniques.
    8. Close quarter firing.
    9. Stress firing.
    10. Zeroing assigned weapon(s).

IV. Weapons qualification and requalification program.
    Qualification firing for the handgun and the rifle must be for 
daylight firing, and each individual shall perform night firing for 
familiarization with assigned weapon(s). The results of weapons 
qualification and requalification must be documented by the licensee or 
the licensee's agent. Each individual shall be requalified at least 
every 12 months. The licensee shall retain this documentation of each 
qualification and requalification as a record for three years from the 
date of the qualification or requalification, as appropriate.
    A. Handgun--Guards, armed escorts and armed response personnel shall 
qualify with a revolver or semiautomatic pistol firing the national 
police course, or an equivalent nationally recognized course. Qualifying 
score shall be an accumulated total of 70 percent of the maximum 
obtainable score.
    B. Semiautomatic Rifle--Guards, armed escorts and armed response 
personnel, assigned to use the semiautomatic rifle by the licensee 
training and qualifications plan, shall qualify with a semiautomatic 
rifle by firing the 100-yard course of fire specified in section 17.5(1) 
of the National Rifle Association, High Power Rifle Rules book 
(effective March 15, 1976), \1\ or a nationally recognized equivalent 
course of fire. Targets used shall be as stated in section 17.5 for the 
100-yard course. Time limits for individuals shall be as specified in 
section 8.2 of the NRA rule book, regardless of the course fired. 
Qualifying score shall be an accumulated total of 80 percent of the 
maximum obtainable score.
---------------------------------------------------------------------------

    \1\ Copies of the ``NRA High Power Rifle Rules'' may be examined at, 
or obtained from, the National Rifle Association, 1600 Rhode Island 
Avenue NW., Washington, DC 20036.
---------------------------------------------------------------------------

    C. Shotgun--Guards, armed escorts, and armed response personnel 
assigned to use the 12 gauge shotgun by the licensee training and 
qualifications plan shall qualify with a full choke or improved modified 
choke 12 gauge shotgun firing the following course:

------------------------------------------------------------------------
                                                    No. Rounds
             Range                   Position          \1\      Target 2
------------------------------------------------------------------------
15 yds........................  Hip fire point...            4      B-27
25 yds........................  Shoulder.........            4      B-27
------------------------------------------------------------------------
\1\ The 4 rounds shall be fired at 4 separate targets within 10 seconds
  using 00 gauge (9 pellet) shotgun shells.
\2\ As set forth by the National Rifle Association (NRA) in its official
  rules and regulations, ``NRA Target Manufacturers Index,'' December
  1976. The Index has been approved for incorporation by reference by
  the Director of the Federal Register. A copy of the index is available
  for inspection at the NRC Library, 11545 Rockville Pike, Rockville,
  Maryland 20852-2738.

    To qualify the individual shall be required to place 50 percent of 
all pellets (36 pellets) within the black silhouette.
    D. Requalification--Individuals shall be weapons requalified at 
least every 12 months in accordance with the NRC approved licensee 
training and qualifications plan, and in accordance with the 
requirements stated in A, B, and C of this section.

V. Guard, armed response personnel, and armed escort equipment.
    A. Fixed Site--Fixed site guards and armed response personnel shall 
either be equipped with or have available the following security 
equipment appropriate to the individual's assigned contingency security 
related tasks or job duties as described in the licensee physical 
security and contingency plans:
    1. Semiautomatic rifles with following nominal minimum 
specifications:
    (a) .223 caliber.
    (b) Muzzle velocity, 1980 ft/sec.
    (c) Muzzle energy, 955 foot-pounds.
    (d) Magazine or clip load of 10 rounds.
    (e) Magazine reload, <10 seconds.
    (f) Operable in any environment in which it will be used.
    2. 12 gauge shotguns with the following capabilities:
    (a) 4 round pump or semiautomatic.
    (b) Operable in any environment in which it will be used.
    (c) Full or modified choke.
    3. Semiautomatic pistols or revolvers with the following nominal 
minimum specifications:
    (a) .354 caliber.
    (b) Muzzle energy, 250 foot-pounds.
    (c) Full magazine or cylinder reload capability <6 seconds.
    (d) Muzzle velocity, 850 ft/sec.
    (e) Full cylinder or magazine capacity, 6 rounds.
    (f) Operable in any environment in which it will be used.
    4. Ammunition:
    (a) For each assigned weapon as appropriate to the individual's 
assigned contingency security job duties and as readily available as the 
weapon:
    (1) 18 rounds per handgun.
    (2) 100 rounds per semiautomatic rifle.

[[Page 573]]

    (3) 12 rounds each per shotgun (00 gauge and slug).
    (b) Ammunition available on site--two (2) times the amount stated in 
(a) above for each weapon.
    5. Personal equipment to be readily available for individuals whose 
assigned contingency security job duties, as described in the licensee 
physical security and contingency plans, warrant such equipment:
    (a) Helmet, combat.
    (b) Gas mask, full face.
    (c) Body armor (bullet-resistant vest).
    (d) Flashlights and batteries.
    (e) Baton.
    (f) Handcuffs.
    (g) Ammunition/equipment belt.
    6. Binoculars.
    7. Night vision aids, i.e., hand-fired illumination flares or 
equivalent.
    8. Tear gas or other nonlethal gas.
    9. Duress alarms.
    10. Two-way portable radios (handi-talkie) 2 channels minimum, 1 
operating and 1 emergency.
    B. Transportation--Armed escorts shall either be equipped with or 
have readily available the following security equipment appropriate to 
the individual's assigned contingency security related tasks or job 
duties, as described in the licensee physical security and contingency 
plans:
    1. Semiautomatic rifles with the following nominal minimum 
specifications:
    (a) .223 caliber.
    (b) Muzzle velocity, 1,980 ft/sec.
    (c) Muzzle energy, 955 foot-pounds.
    (d) Magazine or clip of 10 rounds.
    (e) Reload capability, 10 seconds.
    (f) Operable in any environment in which it will be used.
    2. 12 gauge shotguns.
    (a) 4 round pump or semiautomatic.
    (b) Operable in any environment in which it will be used.
    (c) Full or modified choke.
    3. Semiautomatic pistols or revolvers with the following nominal 
minimum specifications:
    (a) .354 caliber.
    (b) Muzzle energy, 250 foot-pounds.
    (c) Full magazine or cylinder reload capability 6 seconds.
    (d) Muzzle velocity, 850 ft/sec.
    (e) Full cylinder or magazine capacity, 6 rounds.
    (f) Operable in any environment in which it will be used.
    4. Ammunition for each shipment.
    (a) For each assigned weapon as appropriate to the individual's 
assigned contingency security job duties and as readily available as the 
weapon:
    (1) 36 rounds per handgun.
    (2) 120 rounds per semiautomatic rifle.
    (3) 12 rounds each per shotgun (00 gauge and slug).
    5. Escort vehicles, bullet resisting, equipped with communications 
systems, red flares, first aid kit, emergency tool kit, tire changing 
equipment, battery chargers for radios (where appropriate, for 
recharging portable radio batteries).
    6. Personal equipment to be readily available for individuals whose 
assigned contingency security job duties, as described in the licensee 
physical security and contingency plans, warrant such equipment:
    (a) Helmet, combat.
    (b) Gas mask, full face.
    (c) Body armor (bullet-resistant vest).
    (d) Flashlights and batteries.
    (e) Baton.
    (f) Ammunition/equipment belt.
    (g) Pager/duress alarms.
    7. Binoculars.
    8. Night vision aids, i.e., hand-fired illumination flares or 
equivalent.
    9. Tear gas or other nonlethal gas.

VI. Nuclear Power Reactor Training and Qualification Plan for Personnel 
          Performing Security Program Duties
    A. General Requirements and Introduction
    1. The licensee shall ensure that all individuals who are assigned 
duties and responsibilities required to prevent significant core damage 
and spent fuel sabotage, implement the Commission-approved security 
plans, licensee response strategy, and implementing procedures, meet 
minimum training and qualification requirements to ensure each 
individual possesses the knowledge, skills, and abilities required to 
effectively perform the assigned duties and responsibilities.
    2. To ensure that those individuals who are assigned to perform 
duties and responsibilities required for the implementation of the 
Commission-approved security plans, licensee response strategy, and 
implementing procedures are properly suited, trained, equipped, and 
qualified to perform their assigned duties and responsibilities, the 
Commission has developed minimum training and qualification requirements 
that must be implemented through a Commission-approved training and 
qualification plan.
    3. The licensee shall establish, maintain, and follow a Commission-
approved training and qualification plan, describing how the minimum 
training and qualification requirements set forth in this appendix will 
be met, to include the processes by which all individuals, will be 
selected, trained, equipped, tested, and qualified.
    4. Each individual assigned to perform security program duties and 
responsibilities required to effectively implement the Commission-
approved security plans, licensee protective strategy, and the licensee 
implementing procedures, shall demonstrate the knowledge, skills, and 
abilities required to effectively perform the assigned duties and 
responsibilities before the individual is assigned the duty or 
responsibility.

[[Page 574]]

    5. The licensee shall ensure that the training and qualification 
program simulates, as closely as practicable, the specific conditions 
under which the individual shall be required to perform assigned duties 
and responsibilities.
    6. The licensee may not allow any individual to perform any security 
function, assume any security duties or responsibilities, or return to 
security duty, until that individual satisfies the training and 
qualification requirements of this appendix and the Commission-approved 
training and qualification plan, unless specifically authorized by the 
Commission.
    7. Annual requirements must be scheduled at a nominal twelve (12) 
month periodicity. Annual requirements may be completed up to three (3) 
months before or three (3) months after the scheduled date. However, the 
next annual training must be scheduled twelve (12) months from the 
previously scheduled date rather than the date the training was actually 
completed.
    B. Employment Suitability and Qualification
    1. Suitability.
    (a) Before employment, or assignment to the security organization, 
an individual shall:
    (1) Possess a high school diploma or pass an equivalent performance 
examination designed to measure basic mathematical, language, and 
reasoning skills, abilities, and knowledge required to perform security 
duties and responsibilities;
    (2) Have attained the age of 21 for an armed capacity or the age of 
18 for an unarmed capacity; and
    (3) Not have any felony convictions that reflect on the individual's 
reliability.
    (4) Individuals in an armed capacity, would not be disqualified from 
possessing or using firearms or ammunition in accordance with applicable 
state or Federal law, to include 18 U.S.C. 922. Licensees shall use 
information that has been obtained during the completion of the 
individual's background investigation for unescorted access to determine 
suitability. Satisfactory completion of a firearms background check for 
the individual under 10 CFR 73.19 of this part will also fulfill this 
requirement.
    (b) The qualification of each individual to perform assigned duties 
and responsibilities must be documented by a qualified training 
instructor and attested to by a security supervisor.
    2. Physical qualifications.
    (a) General physical qualifications.
    (1) Individuals whose duties and responsibilities are directly 
associated with the effective implementation of the Commission-approved 
security plans, licensee protective strategy, and implementing 
procedures, may not have any physical conditions that would adversely 
affect their performance of assigned security duties and 
responsibilities.
    (2) Armed and unarmed individuals assigned security duties and 
responsibilities shall be subject to a physical examination designed to 
measure the individual's physical ability to perform assigned duties and 
responsibilities as identified in the Commission-approved security 
plans, licensee protective strategy, and implementing procedures.
    (3) This physical examination must be administered by a licensed 
health professional with the final determination being made by a 
licensed physician to verify the individual's physical capability to 
perform assigned duties and responsibilities.
    (4) The licensee shall ensure that both armed and unarmed 
individuals who are assigned security duties and responsibilities 
identified in the Commission-approved security plans, the licensee 
protective strategy, and implementing procedures, meet the following 
minimum physical requirements, as required to effectively perform their 
assigned duties.
    (b) Vision.
    (1) For each individual, distant visual acuity in each eye shall be 
correctable to 20/30 (Snellen or equivalent) in the better eye and 20/40 
in the other eye with eyeglasses or contact lenses.
    (2) Near visual acuity, corrected or uncorrected, shall be at least 
20/40 in the better eye.
    (3) Field of vision must be at least 70 degrees horizontal meridian 
in each eye.
    (4) The ability to distinguish red, green, and yellow colors is 
required.
    (5) Loss of vision in one eye is disqualifying.
    (6) Glaucoma is disqualifying, unless controlled by acceptable 
medical or surgical means, provided that medications used for 
controlling glaucoma do not cause undesirable side effects which 
adversely affect the individual's ability to perform assigned security 
duties, and provided the visual acuity and field of vision requirements 
stated previously are met.
    (7) On-the-job evaluation must be used for individuals who exhibit a 
mild color vision defect.
    (8) If uncorrected distance vision is not at least 20/40 in the 
better eye, the individual shall carry an extra pair of corrective 
lenses in the event that the primaries are damaged. Corrective 
eyeglasses must be of the safety glass type.
    (9) The use of corrective eyeglasses or contact lenses may not 
interfere with an individual's ability to effectively perform assigned 
duties and responsibilities during normal or emergency conditions.
    (c) Hearing.

[[Page 575]]

    (1) Individuals may not have hearing loss in the better ear greater 
than 30 decibels average at 500 Hz, 1,000 Hz, and 2,000 Hz with no level 
greater than 40 decibels at any one frequency.
    (2) A hearing aid is acceptable provided suitable testing procedures 
demonstrate auditory acuity equivalent to the hearing requirement.
    (3) The use of a hearing aid may not decrease the effective 
performance of the individual's assigned security duties during normal 
or emergency operations.
    (d) Existing medical conditions.
    (1) Individuals may not have an established medical history or 
medical diagnosis of existing medical conditions which could interfere 
with or prevent the individual from effectively performing assigned 
duties and responsibilities.
    (2) If a medical condition exists, the individual shall provide 
medical evidence that the condition can be controlled with medical 
treatment in a manner which does not adversely affect the individual's 
fitness-for-duty, mental alertness, physical condition, or capability to 
otherwise effectively perform assigned duties and responsibilities.
    (e) Addiction. Individuals may not have any established medical 
history or medical diagnosis of habitual alcoholism or drug addiction, 
or, where this type of condition has existed, the individual shall 
provide certified documentation of having completed a rehabilitation 
program which would give a reasonable degree of confidence that the 
individual would be capable of effectively performing assigned duties 
and responsibilities.
    (f) Other physical requirements. An individual who has been 
incapacitated due to a serious illness, injury, disease, or operation, 
which could interfere with the effective performance of assigned duties 
and responsibilities shall, before resumption of assigned duties and 
responsibilities, provide medical evidence of recovery and ability to 
perform these duties and responsibilities.
    3. Psychological qualifications.
    (a) Armed and unarmed individuals shall demonstrate the ability to 
apply good judgment, mental alertness, the capability to implement 
instructions and assigned tasks, and possess the acuity of senses and 
ability of expression sufficient to permit accurate communication by 
written, spoken, audible, visible, or other signals required by assigned 
duties and responsibilities.
    (b) A licensed psychologist, psychiatrist, or physician trained in 
part to identify emotional instability shall determine whether armed 
members of the security organization and alarm station operators in 
addition to meeting the requirement stated in paragraph (a) of this 
section, have no emotional instability that would interfere with the 
effective performance of assigned duties and responsibilities.
    (c) A person professionally trained to identify emotional 
instability shall determine whether unarmed individuals in addition to 
meeting the requirement stated in paragraph (a) of this section, have no 
emotional instability that would interfere with the effective 
performance of assigned duties and responsibilities.
    4. Medical examinations and physical fitness qualifications.
    (a) Armed members of the security organization shall be subject to a 
medical examination by a licensed physician, to determine the 
individual's fitness to participate in physical fitness tests.
    (1) The licensee shall obtain and retain a written certification 
from the licensed physician that no medical conditions were disclosed by 
the medical examination that would preclude the individual's ability to 
participate in the physical fitness tests or meet the physical fitness 
attributes or objectives associated with assigned duties.
    (b) Before assignment, armed members of the security organization 
shall demonstrate physical fitness for assigned duties and 
responsibilities by performing a practical physical fitness test.
    (1) The physical fitness test must consider physical conditions such 
as strenuous activity, physical exertion, levels of stress, and exposure 
to the elements as they pertain to each individual's assigned security 
duties for both normal and emergency operations and must simulate site 
specific conditions under which the individual will be required to 
perform assigned duties and responsibilities.
    (2) The licensee shall describe the physical fitness test in the 
Commission-approved training and qualification plan.
    (3) The physical fitness test must include physical attributes and 
performance objectives which demonstrate the strength, endurance, and 
agility, consistent with assigned duties in the Commission-approved 
security plans, licensee protective strategy, and implementing 
procedures during normal and emergency conditions.
    (4) The physical fitness qualification of each armed member of the 
security organization must be documented by a qualified training 
instructor and attested to by a security supervisor.
    5. Physical requalification.
    (a) At least annually, armed and unarmed individuals shall be 
required to demonstrate the capability to meet the physical requirements 
of this appendix and the licensee training and qualification plan.
    (b) The physical requalification of each armed and unarmed 
individual must be documented by a qualified training instructor and 
attested to by a security supervisor.
    C. Duty Training
    1. Duty training and qualification requirements. All personnel who 
are assigned to

[[Page 576]]

perform any security-related duty or responsibility shall be trained and 
qualified to perform assigned duties and responsibilities to ensure that 
each individual possesses the minimum knowledge, skills, and abilities 
required to effectively carry out those assigned duties and 
responsibilities.
    (a) The areas of knowledge, skills, and abilities that are required 
to perform assigned duties and responsibilities must be identified in 
the licensee's Commission-approved training and qualification plan.
    (b) Each individual who is assigned duties and responsibilities 
identified in the Commission-approved security plans, licensee 
protective strategy, and implementing procedures shall, before 
assignment:
    (1) Be trained to perform assigned duties and responsibilities in 
accordance with the requirements of this appendix and the Commission-
approved training and qualification plan.
    (2) Meet the minimum qualification requirements of this appendix and 
the Commission-approved training and qualification plan.
    (3) Be trained and qualified in the use of all equipment or devices 
required to effectively perform all assigned duties and 
responsibilities.
    2. On-the-job training.
    (a) The licensee training and qualification program must include on-
the-job training performance standards and criteria to ensure that each 
individual demonstrates the requisite knowledge, skills, and abilities 
needed to effectively carry-out assigned duties and responsibilities in 
accordance with the Commission-approved security plans, licensee 
protective strategy, and implementing procedures, before the individual 
is assigned the duty or responsibility.
    (b) In addition to meeting the requirement stated in paragraph 
C.2.(a) of this appendix, before assignment, individuals (e.g., response 
team leaders, alarm station operators, armed responders, and armed 
security officers designated as a component of the protective strategy) 
assigned duties and responsibilities to implement the Safeguards 
Contingency Plan shall complete a minimum of 40 hours of on-the-job 
training to demonstrate their ability to effectively apply the 
knowledge, skills, and abilities required to effectively perform 
assigned contingency duties and responsibilities in accordance with the 
approved safeguards contingency plan, other security plans, licensee 
protective strategy, and implementing procedures. On-the-job training 
must be documented by a qualified training instructor and attested to by 
a security supervisor.
    (c) On-the-job training for contingency activities and drills must 
include, but is not limited to, hands-on application of knowledge, 
skills, and abilities related to:
    (1) Response team duties.
    (2) Use of force.
    (3) Tactical movement.
    (4) Cover and concealment.
    (5) Defensive positions.
    (6) Fields-of-fire.
    (7) Re-deployment.
    (8) Communications (primary and alternate).
    (9) Use of assigned equipment.
    (10) Target sets.
    (11) Table top drills.
    (12) Command and control duties.
    (13) Licensee Protective Strategy.
    3. Performance Evaluation Program.
    (a) Licensees shall develop, implement and maintain a Performance 
Evaluation Program that is documented in procedures which describes how 
the licensee will demonstrate and assess the effectiveness of their 
onsite physical protection program and protective strategy, including 
the capability of the armed response team to carry out their assigned 
duties and responsibilities during safeguards contingency events. The 
Performance Evaluation Program and procedures shall be referenced in the 
licensee's Training and Qualifications Plan.
    (b) The Performance Evaluation Program shall include procedures for 
the conduct of tactical response drills and force-on-force exercises 
designed to demonstrate and assess the effectiveness of the licensee's 
physical protection program, protective strategy and contingency event 
response by all individuals with responsibilities for implementing the 
safeguards contingency plan.
    (c) The licensee shall conduct tactical response drills and force-
on-force exercises in accordance with Commission-approved security 
plans, licensee protective strategy, and implementing procedures.
    (d) Tactical response drills and force-on-force exercises must be 
designed to challenge the site protective strategy against elements of 
the design basis threat and ensure each participant assigned security 
duties and responsibilities identified in the Commission-approved 
security plans, the licensee protective strategy, and implementing 
procedures demonstrate the requisite knowledge, skills, and abilities.
    (e) Tactical response drills, force-on-force exercises, and 
associated contingency response training shall be conducted under 
conditions that simulate, as closely as practicable, the site-specific 
conditions under which each member will, or may be, required to perform 
assigned duties and responsibilities.
    (f) The scope of tactical response drills conducted for training 
purposes shall be determined by the licensee and must address site-
specific, individual or programmatic elements, and may be limited to 
specific portions of the site protective strategy.
    (g) Each tactical response drill and force-on-force exercise shall 
include a documented

[[Page 577]]

post-exercise critique in which participants identify failures, 
deficiencies or other findings in performance, plans, equipment or 
strategies.
    (h) Licensees shall document scenarios and participants for all 
tactical response drills and annual force-on-force exercises conducted.
    (i) Findings, deficiencies and failures identified during tactical 
response drills and force-on-force exercises that adversely affect or 
decrease the effectiveness of the protective strategy and physical 
protection program shall be entered into the licensee's corrective 
action program to ensure that timely corrections are made to the 
appropriate program areas.
    (j) Findings, deficiencies and failures associated with the onsite 
physical protection program and protective strategy shall be protected 
as necessary in accordance with the requirements of 10 CFR 73.21.
    (k) For the purpose of tactical response drills and force-on-force 
exercises, licensees shall:
    (1) Use no more than the total number of armed responders and armed 
security officers documented in the security plans.
    (2) Minimize the number and effects of artificialities associated 
with tactical response drills and force-on-force exercises.
    (3) Implement the use of systems or methodologies that simulate the 
realities of armed engagement through visual and audible means, and 
reflect the capabilities of armed personnel to neutralize a target 
through the use of firearms.
    (4) Ensure that each scenario used provides a credible, realistic 
challenge to the protective strategy and the capabilities of the 
security response organization.
    (l) The Performance Evaluation Program must be designed to ensure 
that:
    (1) Each member of each shift who is assigned duties and 
responsibilities required to implement the safeguards contingency plan 
and licensee protective strategy participates in at least one (1) 
tactical response drill on a quarterly basis and one (1) force-on-force 
exercise on an annual basis. Force-on-force exercises conducted to 
satisfy the NRC triennial evaluation requirement can be used to satisfy 
the annual force-on-force requirement for the personnel that participate 
in the capacity of the security response organization.
    (2) The mock adversary force replicates, as closely as possible, 
adversary characteristics and capabilities of the design basis threat 
described in 10 CFR 73.1(a)(1), and is capable of exploiting and 
challenging the licensees protective strategy, personnel, command and 
control, and implementing procedures.
    (3) Protective strategies can be evaluated and challenged through 
the conduct of tactical response tabletop demonstrations.
    (4) Drill and exercise controllers are trained and qualified to 
ensure that each controller has the requisite knowledge and experience 
to control and evaluate exercises.
    (5) Tactical response drills and force-on-force exercises are 
conducted safely and in accordance with site safety plans.
    (m) Scenarios.
    (1) Licensees shall develop and document multiple scenarios for use 
in conducting quarterly tactical response drills and annual force-on-
force exercises.
    (2) Licensee scenarios must be designed to test and challenge any 
components or combination of components, of the onsite physical 
protection program and protective strategy.
    (3) Each scenario must use a unique target set or target sets, and 
varying combinations of adversary equipment, strategies, and tactics, to 
ensure that the combination of all scenarios challenges every component 
of the onsite physical protection program and protective strategy to 
include, but not limited to, equipment, implementing procedures, and 
personnel.
    D. Duty Qualification and Requalification
    1. Qualification demonstration.
    (a) Armed and unarmed individuals shall demonstrate the required 
knowledge, skills, and abilities to carry out assigned duties and 
responsibilities as stated in the Commission-approved security plans, 
licensee protective strategy, and implementing procedures.
    (b) This demonstration must include written exams and hands-on 
performance demonstrations.
    (1) Written Exams. The written exams must include those elements 
listed in the Commission-approved training and qualification plan and 
shall require a minimum score of 80 percent to demonstrate an acceptable 
understanding of assigned duties and responsibilities, to include the 
recognition of potential tampering involving both safety and security 
equipment and systems.
    (2) Hands-on Performance Demonstrations. Armed and unarmed 
individuals shall demonstrate hands-on performance for assigned duties 
and responsibilities by performing a practical hands-on demonstration 
for required tasks. The hands-on demonstration must ensure that theory 
and associated learning objectives for each required task are considered 
and each individual demonstrates the knowledge, skills, and abilities 
required to effectively perform the task.
    (3) Annual Written Exam. Armed individuals shall be administered an 
annual written exam that demonstrates the required knowledge, skills, 
and abilities to carry out assigned duties and responsibilities as an 
armed member of the security organization. The annual written exam must 
include those elements listed in the Commission-approved

[[Page 578]]

training and qualification plan and shall require a minimum score of 80 
percent to demonstrate an acceptable understanding of assigned duties 
and responsibilities.
    (c) Upon request by an authorized representative of the Commission, 
any individual assigned to perform any security-related duty or 
responsibility shall demonstrate the required knowledge, skills, and 
abilities for each assigned duty and responsibility, as stated in the 
Commission-approved security plans, licensee protective strategy, or 
implementing procedures.
    2. Requalification.
    (a) Armed and unarmed individuals shall be requalified at least 
annually in accordance with the requirements of this appendix and the 
Commission-approved training and qualification plan.
    (b) The results of requalification must be documented by a qualified 
training instructor and attested by a security supervisor.
    E. Weapons Training
    1. General firearms training.
    (a) Armed members of the security organization shall be trained and 
qualified in accordance with the requirements of this appendix and the 
Commission-approved training and qualification plan.
    (b) Firearms instructors.
    (1) Each armed member of the security organization shall be trained 
and qualified by a certified firearms instructor for the use and 
maintenance of each assigned weapon to include but not limited to, 
marksmanship, assembly, disassembly, cleaning, storage, handling, 
clearing, loading, unloading, and reloading, for each assigned weapon.
    (2) Firearms instructors shall be certified from a national or state 
recognized entity.
    (3) Certification must specify the weapon or weapon type(s) for 
which the instructor is qualified to teach.
    (4) Firearms instructors shall be recertified in accordance with the 
standards recognized by the certifying national or state entity, but in 
no case shall recertification exceed three (3) years.
    (c) Annual firearms familiarization. The licensee shall conduct 
annual firearms familiarization training in accordance with the 
Commission-approved training and qualification plan.
    (d) The Commission-approved training and qualification plan shall 
include, but is not limited to, the following areas:
    (1) Mechanical assembly, disassembly, weapons capabilities and 
fundamentals of marksmanship.
    (2) Weapons cleaning and storage.
    (3) Combat firing, day and night.
    (4) Safe weapons handling.
    (5) Clearing, loading, unloading, and reloading.
    (6) Firing under stress.
    (7) Zeroing duty weapon(s) and weapons sighting adjustments.
    (8) Target identification and engagement.
    (9) Weapon malfunctions.
    (10) Cover and concealment.
    (11) Weapon familiarization.
    (e) The licensee shall ensure that each armed member of the security 
organization is instructed on the use of deadly force as authorized by 
applicable state law.
    (f) Armed members of the security organization shall participate in 
weapons range activities on a nominal four (4) month periodicity. 
Performance may be conducted up to five (5) weeks before, to five (5) 
weeks after, the scheduled date. The next scheduled date must be four 
(4) months from the originally scheduled date.
    F. Weapons Qualification and Requalification Program
    1. General weapons qualification requirements.
    (a) Qualification firing must be accomplished in accordance with 
Commission requirements and the Commission-approved training and 
qualification plan for assigned weapons.
    (b) The results of weapons qualification and requalification must be 
documented and retained as a record.
    2. Tactical weapons qualification. The licensee Training and 
Qualification Plan must describe the firearms used, the firearms 
qualification program, and other tactical training required to implement 
the Commission-approved security plans, licensee protective strategy, 
and implementing procedures. Licensee developed tactical qualification 
and re-qualification courses must describe the performance criteria 
needed to include the site specific conditions (such as lighting, 
elevation, fields-of-fire) under which assigned personnel shall be 
required to carry-out their assigned duties.
    3. Firearms qualification courses. The licensee shall conduct the 
following qualification courses for each weapon used.
    (a) Annual daylight qualification course. Qualifying score must be 
an accumulated total of 70 percent with handgun and shotgun, and 80 
percent with semiautomatic rifle and/or enhanced weapons, of the maximum 
obtainable target score.
    (b) Annual night fire qualification course. Qualifying score must be 
an accumulated total of 70 percent with handgun and shotgun, and 80 
percent with semiautomatic rifle and/or enhanced weapons, of the maximum 
obtainable target score.
    (c) Annual tactical qualification course. Qualifying score must be 
an accumulated total of 80 percent of the maximum obtainable score.
    4. Courses of fire.
    (a) Handgun. Armed members of the security organization, assigned 
duties and responsibilities involving the use of a revolver or 
semiautomatic pistol shall qualify in accordance with standards 
established by a law

[[Page 579]]

enforcement course, or an equivalent nationally recognized course.
    (b) Semiautomatic rifle. Armed members of the security organization, 
assigned duties and responsibilities involving the use of a 
semiautomatic rifle shall qualify in accordance with the standards 
established by a law enforcement course, or an equivalent nationally 
recognized course.
    (c) Shotgun. Armed members of the security organization, assigned 
duties and responsibilities involving the use of a shotgun shall qualify 
in accordance with standards established by a law enforcement course, or 
an equivalent nationally recognized course.
    (d) Enhanced weapons. Armed members of the security organization, 
assigned duties and responsibilities involving the use of any weapon or 
weapons not described previously shall qualify in accordance with 
applicable standards established by a law enforcement course or an 
equivalent nationally recognized course for these weapons.
    5. Firearms requalification.
    (a) Armed members of the security organization shall be re-qualified 
for each assigned weapon at least annually in accordance with Commission 
requirements and the Commission-approved training and qualification 
plan, and the results documented and retained as a record.
    (b) Firearms requalification must be conducted using the courses of 
fire outlined in paragraphs F.2, F.3, and F.4 of this section.
    G. Weapons, Personal Equipment and Maintenance
    1. Weapons. The licensee shall provide armed personnel with weapons 
that are capable of performing the function stated in the Commission-
approved security plans, licensee protective strategy, and implementing 
procedures.
    2. Personal equipment.
    (a) The licensee shall ensure that each individual is equipped or 
has ready access to all personal equipment or devices required for the 
effective implementation of the Commission-approved security plans, 
licensee protective strategy, and implementing procedures.
    (b) The licensee shall provide armed security personnel, required 
for the effective implementation of the Commission-approved Safeguards 
Contingency Plan and implementing procedures, at a minimum, but is not 
limited to, the following:
    (1) Gas mask, full face.
    (2) Body armor (bullet-resistant vest).
    (3) Ammunition/equipment belt.
    (4) Two-way portable radios, 2 channels minimum, 1 operating and 1 
emergency.
    (c) Based upon the licensee protective strategy and the specific 
duties and responsibilities assigned to each individual, the licensee 
should provide, as appropriate, but is not limited to, the following.
    (1) Flashlights and batteries.
    (2) Baton or other non-lethal weapons.
    (3) Handcuffs.
    (4) Binoculars.
    (5) Night vision aids (e.g., goggles, weapons sights).
    (6) Hand-fired illumination flares or equivalent.
    (7) Duress alarms.
    3. Maintenance.
    (a) Firearms maintenance program. Each licensee shall implement a 
firearms maintenance and accountability program in accordance with the 
Commission regulations and the Commission-approved training and 
qualification plan. The program must include:
    (1) Semiannual test firing for accuracy and functionality.
    (2) Firearms maintenance procedures that include cleaning schedules 
and cleaning requirements.
    (3) Program activity documentation.
    (4) Control and accountability (weapons and ammunition).
    (5) Firearm storage requirements.
    (6) Armorer certification.
    H. Records
    1. The licensee shall retain all reports, records, or other 
documentation required by this appendix in accordance with the 
requirements of Sec. 73.55(q).
    2. The licensee shall retain each individual's initial qualification 
record for three (3) years after termination of the individual's 
employment and shall retain each re-qualification record for three (3) 
years after it is superseded.
    3. The licensee shall document data and test results from each 
individual's suitability, physical, and psychological qualification and 
shall retain this documentation as a record for three (3) years from the 
date of obtaining and recording these results.
    I. Reviews
    The licensee shall review the Commission-approved training and 
qualification program in accordance with the requirements of Sec. 
73.55(m).
    J. Definitions
    Terms defined in parts 50, 70, and 73 of this chapter have the same 
meaning when used in this appendix.

[43 FR 37426, Aug. 23, 1978, as amended at 46 FR 2026, Jan. 8, 1981; 53 
FR 405, Jan. 7, 1988; 53 FR 19261, May 27, 1988; 57 FR 33432, July 29, 
1992; 57 FR 61787, Dec. 29, 1992; 59 FR 50689, Oct. 5, 1994; 74 FR 
13987, Mar. 27, 2009; 77 FR 39910, July 6, 2012]



    Sec. Appendix C to Part 73--Licensee Safeguards Contingency Plans

                     I. Safeguards Contingency Plan

    Licensees, applicants, and certificate holders, with the exception 
of those who are subject to the requirements of Sec. 73.55 shall comply 
with the requirements of this section.

[[Page 580]]

                              Introduction

    A licensee safeguards contingency plan is a documented plan to give 
guidance to licensee personnel in order to accomplish specific defined 
objectives in the event of threats, thefts, or radiological sabotage 
relating to special nuclear material or nuclear facilities licensed 
under the Atomic Energy Act of 1954, as amended. An acceptable 
safeguards contingency plan must contain:
    (1) A predetermined set of decisions and actions to satisfy stated 
objectives;
    (2) An identification of the data, criteria, procedures, and 
mechanisms necessary to efficiently implement the decisions; and
    (3) A stipulation of the individual, group, or organizational entity 
responsible for each decision and action.
    The goals of licensee safeguards contingency plans for responding to 
threats, thefts, and radiological sabotage are:
    (1) To organize the response effort at the licensee level;
    (2) To provide predetermined, structured responses by licensees to 
safeguards contingencies;
    (3) To ensure the integration of the licensee response with the 
responses by other entities; and
    (4) To achieve a measurable performance in response capability.
    Licensee safeguards contingency planning should result in organizing 
the licensee's resources in such a way that the participants will be 
identified, their several responsibilities specified, and the responses 
coordinated. The responses should be timely.
    It is important to note that a licensee's safeguards contingency 
plan is intended to be complementary to any emergency plans developed 
under appendix E to part 50 of this chapter, Sec. 52.17 or Sec. 52.79, 
or to Sec. 70.22(i) of this chapter.

                          contents of the plan

    Each licensee safeguards contingency plan shall include five 
categories of information:
1. Background
2. Generic Planning Base
3. Licensee Planning Base
4. Responsibility Matrix
5. Procedures
    Although the implementing procedures (the fifth category of Plan 
information) are the culmination of the planning process, and therefore 
are an integral and important part of the safeguards contingency plan, 
they entail operating details subject to frequent changes. They need not 
be submitted to the Commission for approval, but will be inspected by 
NRC staff on a periodic basis. The licensee is responsible for ensuring 
that the implementing procedures reflect the information in the 
Responsibility Matrix, appropriately summarized and suitably presented 
for effective use by the responding entities.
    The following paragraphs describe the contents of the safeguards 
contingency plan.
    1. Background. Under the following topics, this category of 
information shall identify and define the perceived dangers and 
incidents with which the plan will deal and the general way it will 
handle these:
    a. Perceived Danger--A statement of the perceived danger to the 
security of special nuclear material, licensee personnel, and licensee 
property, including covert diversion of special nuclear material, 
radiological sabotage, and overt attacks. The statement of perceived 
danger should conform with that promulgated by the Nuclear Regulatory 
Commission. (The statement contained in 10 CFR 73.55(a) or subsequent 
Commission statements will suffice.)
    b. Purpose of the Plan--A discussion of the general aims and 
operational concepts underlying implementation of the plan.
    c. Scope of the Plan--A delineation of the types of incidents 
covered in the plan.
    d. Definitions--A list of terms and their definitions used in 
describing operational and technical aspects of the plan.
    2. Generic Planning Base. Under the following topics, this category 
of information shall define the criteria for initiation and termination 
of responses to safeguards contingencies together with the specific 
decisions, actions, and supporting information needed to bring about 
such responses:
    a. Identification of those events that will be used for signaling 
the beginning or aggravation of a safeguards contingency according to 
how they are perceived initially by licensee's personnel. Such events 
may include alarms or other indications signaling penetration of a 
protected area, vital area, or material access area; material control or 
material accounting indications of material missing or unaccounted for; 
or threat indications--either verbal, such as telephoned threats, or 
implied, such as escalating civil disturbances.
    b. Definition of the specific objective to be accomplished relative 
to each identified event. The objective may be to obtain a level of 
awareness about the nature and severity of the safeguards contingency in 
order to prepare for further responses; to establish a level of response 
preparedness; or to successfully nullify or reduce any adverse 
safeguards consequences arising from the contingency.
    3. Licensee Planning Base. This category of information shall 
include the factors affecting contingency planning that are specific for 
each facility or means of transportation. To the extent that the topics 
are treated in adequate detail in the licensee's approved physical 
security plan, they may be incorporated by cross reference to that plan. 
The following topics should be addressed:
    a. Licensee's Organizational Structure for Contingency Responses--A 
delineation of the

[[Page 581]]

organization's chain of command and delegation of authority as these 
apply to safeguards contingencies.
    b. Physical Layout--(i) Fixed Sites--A description of the physical 
structures and their location on the site, and a description of the site 
in relation to nearby town, roads, and other environmental features 
important to the effective coordination of response operations. 
Particular emphasis should be placed on main and alternate entry routes 
for law-enforcement assistance forces and the location of control points 
for marshalling and coordinating response activities.
    (ii) Transportation--A description of the vehicles, shipping routes, 
preplanned alternate routes, and related features.
    c. Safeguards Systems Hardware--A description of the physical 
security and accounting system hardware that influence how the licensee 
will respond to an event. Examples of systems to be discussed are 
communications, alarms, locks, seals, area access, armaments, and 
surveillance.
    d. Law Enforcement Assistance--A listing of available local law 
enforcement agencies and a description of their response capabilities 
and their criteria for response; and a discussion of working agreements 
or arrangements for communicating with these agencies.
    e. Policy Constraints and Assumptions--A discussion of State laws, 
local ordinances, and company policies and practices that govern 
licensee response to incidents. Examples that may be discussed include:
Use of deadly force;
Use of employee property;
Use of off-duty employees;
Site security jurisdictional boundaries.
    f. Administrative and Logistical Considerations--Descriptions of 
licensee practices that may have an influence on the response to 
safeguards contingency events. The considerations shall include a 
description of the procedures that will be used for ensuring that all 
equipment needed to effect a successful response to a safeguards 
contingency will be easily accessible, in good working order, and in 
sufficient supply to provide redundancy in case of equipment failure.
    4. Responsibility Matrix. This category of information consists of 
detailed identification of the organizational entities responsible for 
each decision and action associated with specific responses to 
safeguards contingencies. For each initiating event, a tabulation shall 
be made for each response entity depicting the assignment of 
responsibilities for all decisions and actions to be taken in response 
to the initiating event. (Not all entities will have assigned 
responsibilities for any given initiating event.) The tabulations in the 
Responsibility Matrix shall provide an overall picture of the response 
actions and their interrelationships. Safeguards responsibilities shall 
be assigned in a manner that precludes conflict in duties or 
responsibilities that would prevent the execution of the plan in any 
safeguards contingency.
    5. Procedures. In order to aid execution of the detailed plan as 
developed in the Responsibility Matrix, this category of information 
shall detail the actions to be taken and decisions to be made by each 
member or unit of the organization as planned in the Responsibility 
Matrix.

                            Audit and Review

    (1) For nuclear facilities subject to the requirements of Sec. 
73.46, the licensee shall provide for a review of the safeguards 
contingency plan at intervals not to exceed 12 months. For nuclear power 
reactor licensees subject to the requirements of Sec. 73.55, the 
licensee shall provide for a review of the safeguards contingency plan 
either:
    (i) At intervals not to exceed 12 months, or
    (ii) As necessary, based on an assessment by the licensee against 
performance indicators, and as soon as reasonably practicable after a 
change occurs in personnel, procedures, equipment, or facilities that 
potentially could adversely affect security, but no longer than 12 
months after the change. In any case, each element of the safeguards 
contingency plan must be reviewed at least every 24 months.
    (2) A licensee subject to the requirements of either Sec. 73.46 or 
Sec. 73.55 shall ensure that the review of the safeguards contingency 
plan is by individuals independent of both security program management 
and personnel who have direct responsibility for implementation of the 
security program. The review must include an audit of safeguards 
contingency procedures and practices, and an audit of commitments 
established for response by local law enforcement authorities.
    (3) The licensee shall document the results and the recommendations 
of the safeguards contingency plan review, management findings on 
whether the safeguards contingency plan is currently effective, and any 
actions taken as a result of recommendations from prior reviews in a 
report to the licensee's plant manager and to corporate management at 
least one level higher than that having responsibility for the day-to-
day plant operation. The report must be maintained in an auditable form, 
available for inspection for a period of 3 years.

          II. Nuclear Power Plant Safeguards Contingency Plans

                             A. Introduction

    The safeguards contingency plan is a documented plan that describes 
how licensee personnel implement their physical protection program to 
defend against threats to their facility, up to and including the design 
basis threat of radiological sabotage. The goals of licensee safeguards 
contingency plans are:

[[Page 582]]

    (1) To organize the response effort at the licensee level;
    (2) To provide predetermined, structured response by licensees to 
safeguards contingencies;
    (3) To ensure the integration of the licensee response by other 
entities; and
    (4) To achieve a measurable performance in response capability.
    Licensee safeguards contingency planning should result in organizing 
the licensee's resources in such a way that the participants will be 
identified, their responsibilities specified, and the responses 
coordinated. The responses should be timely, and include personnel who 
are trained and qualified to respond in accordance with a documented 
training and qualification program.
    The evaluation, validation, and testing of this portion of the 
program shall be conducted in accordance with appendix B, section VI of 
this part, Nuclear Power Reactor Training and Qualification Plan for 
Personnel Performing Security Program Duties. The licensee's safeguards 
contingency plan is intended to maintain effectiveness during the 
implementation of emergency plans developed under appendix E to part 50 
of this chapter.

                         B. Contents of the Plan

    Each safeguards contingency plan shall include five (5) categories 
of information:
    (1) Background.
    (2) Generic planning base.
    (3) Licensee planning base.
    (4) Responsibility matrix.
    (5) Implementing procedures.
    Although the implementing procedures (the fifth category of plan 
information) are the culmination of the planning process, and are an 
integral and important part of the safeguards contingency plan, they 
entail operating details subject to frequent changes. They need not be 
submitted to the Commission for approval, but are subject to inspection 
by NRC staff on a periodic basis.
    1. Background. This category of information shall identify the 
perceived dangers and incidents that the plan will address and a general 
description of how the response is organized.
    a. Perceived Danger--Consistent with the design basis threat 
specified in Sec. 73.1(a)(1), licensees shall identify and describe the 
perceived dangers, threats, and incidents against which the safeguards 
contingency plan is designed to protect.
    b. Purpose of the Plan--Licensees shall describe the general goals, 
objectives and operational concepts underlying the implementation of the 
approved safeguards contingency plan.
    c. Scope of the Plan--A delineation of the types of incidents 
covered by the plan.
    (i) How the onsite response effort is organized and coordinated to 
effectively respond to a safeguards contingency event.
    (ii) How the onsite response for safeguards contingency events has 
been integrated in other site emergency response procedures.
    d. Definitions--A list of terms and their definitions used in 
describing operational and technical aspects of the approved safeguards 
contingency plan.
    2. Generic Planning Base. Licensees shall define the criteria for 
initiation and termination of responses to security events to include 
the specific decisions, actions, and supporting information needed to 
respond to each type of incident covered by the approved safeguards 
contingency plan. To achieve this result the generic planning base must:
    a. Identify those events that will be used for signaling the 
beginning or aggravation of a safeguards contingency event according to 
how they are perceived initially by licensee's personnel. Licensees 
shall ensure detection of unauthorized activities and shall respond to 
all alarms or other indications signaling a security event, such as 
penetration of a protected area, vital area, or unauthorized barrier 
penetration (vehicle or personnel); tampering, bomb threats, or other 
threat warnings--either verbal, such as telephoned threats, or implied, 
such as escalating civil disturbances.
    b. Define the specific objective to be accomplished relative to each 
identified safeguards contingency event. The objective may be to obtain 
a level of awareness about the nature and severity of the safeguards 
contingency to prepare for further responses; to establish a level of 
response preparedness; or to successfully nullify or reduce any adverse 
safeguards consequences arising from the contingency.
    c. Identify the data, criteria, procedures, mechanisms and 
logistical support necessary to achieve the objectives identified.
    3. Licensee Planning Base. This category of information shall 
include factors affecting safeguards contingency planning that are 
specific for each facility. To the extent that the topics are treated in 
adequate detail in the licensee's approved physical security plan, they 
may be incorporated by reference in the Safeguards Contingency Plan. The 
following topics must be addressed:
    a. Organizational Structure. The safeguards contingency plan must 
describe the organization's chain of command and delegation of authority 
during safeguards contingency events, to include a general description 
of how command and control functions will be coordinated and maintained.
    b. Physical Layout. The safeguards contingency plan must include a 
site map depicting the physical structures located on the site, 
including onsite independent spent fuel storage installations, and a 
description of the

[[Page 583]]

structures depicted on the map. Plans must also include a description 
and map of the site in relation to nearby towns, transportation routes 
(e.g., rail, water, and roads), pipelines, airports, hazardous material 
facilities, and pertinent environmental features that may have an effect 
upon coordination of response activities. Descriptions and maps must 
indicate main and alternate entry routes for law enforcement or other 
offsite response and support agencies and the location for marshaling 
and coordinating response activities.
    c. Safeguards Systems. The safeguards contingency plan must include 
a description of the physical security systems that support and 
influence how the licensee will respond to an event in accordance with 
the design basis threat described in Sec. 73.1(a). The licensee's 
description shall begin with onsite physical protection measures 
implemented at the outermost facility perimeter, and must move inward 
through those measures implemented to protect target set equipment.
    (i) Physical security systems and security systems hardware to be 
discussed include security systems and measures that provide defense-in-
depth, such as physical barriers, alarm systems, locks, area access, 
armaments, surveillance, and communications systems.
    (ii) The specific structure of the security response organization to 
include the total number of armed responders and armed security officers 
documented in the approved security plans as a component of the 
protective strategy and a general description of response capabilities 
shall also be included in the safeguards contingency plan.
    (iii) Licensees shall ensure that individuals assigned duties and 
responsibilities to implement the safeguards contingency plan are 
trained and qualified in those duties according to the Commission 
approved security plans, and the performance evaluation program.
    (iv) Armed responders shall be available to respond from designated 
areas inside the protected area at all times and may not be assigned any 
other duties or responsibilities that could interfere with assigned 
armed response team duties and responsibilities.
    (v) Licensees shall develop, implement, and maintain a written 
protective strategy to be documented in procedures that describe in 
detail the physical protection measures, security systems and deployment 
of the armed response team relative to site specific conditions, to 
include but not be limited to, facility layout, and the location of 
target set equipment and elements. The protective strategy should 
support the general goals, operational concepts, and performance 
objectives identified in the licensee's safeguards contingency plan. The 
protective strategy shall:
    (1) Be designed to meet the performance requirements and objectives 
of Sec. 73.55(a) through (k).
    (2) Identify predetermined actions, areas of responsibility and 
timelines for the deployment of armed personnel.
    (3) Contain measures that limit the exposure of security personnel 
to possible attack, including incorporation of bullet resisting 
protected positions.
    (4) Contain a description of the physical security systems and 
measures that provide defense-in-depth such as physical barriers, alarm 
systems, locks, area access, armaments, surveillance, and communications 
systems.
    (5) Describe the specific structure and responsibilities of the 
armed response organization to include:
    The authorized minimum number of armed responders, available at all 
times inside the protected area.
    The authorized minimum number of armed security officers, available 
onsite at all times.
    The total number of armed responders and armed security officers 
documented in the approved security plans as a component of the 
protective strategy.
    (6) Provide a command and control structure, to include response by 
off-site law enforcement agencies, which ensures that decisions and 
actions are coordinated and communicated in a timely manner to 
facilitate response.
    d. Law Enforcement Assistance. Provide a listing of available law 
enforcement agencies and a general description of their response 
capabilities and their criteria for response and a discussion of working 
agreements or arrangements for communicating with these agencies.
    e. Policy Constraints and Assumptions. The safeguards contingency 
plan shall contain a discussion of State laws, local ordinances, and 
company policies and practices that govern licensee response to 
incidents and must include, but is not limited to, the following.
    (i) Use of deadly force.
    (ii) Recall of off-duty employees.
    (iii) Site jurisdictional boundaries.
    (iv) Use of enhanced weapons, if applicable.
    f. Administrative and Logistical Considerations. Descriptions of 
licensee practices which influence how the security organization 
responds to a safeguards contingency event to include, but not limited 
to, a description of the procedures that will be used for ensuring that 
equipment needed to facilitate response will be readily accessible, in 
good working order, and in sufficient supply.
    4. Responsibility Matrix. This category of information consists of 
the detailed identification of responsibilities and specific actions to 
be taken by licensee organizations

[[Page 584]]

and/or personnel in response to safeguards contingency events.
    a. Licensees shall develop site procedures that consist of matrixes 
detailing the organization and/or personnel responsible for decisions 
and actions associated with specific responses to safeguards contingency 
events. The responsibility matrix and procedures shall be referenced in 
the licensee's safeguards contingency plan.
    b. Responsibility matrix procedures shall be based on the events 
outlined in the licensee's Generic Planning Base and must include the 
following information:
    (i) The definition of the specific objective to be accomplished 
relative to each identified safeguards contingency event. The objective 
may be to obtain a level of awareness about the nature and severity of 
the safeguards contingency to prepare for further responses, to 
establish a level of response preparedness, or to successfully nullify 
or reduce any adverse safeguards consequences arising from the 
contingency.
    (ii) A tabulation for each identified initiating event and each 
response entity which depicts the assignment of responsibilities for 
decisions and actions to be taken in response to the initiating event.
    (iii) An overall description of response actions and 
interrelationships specifically associated with each responsible entity 
must be included.
    c. Responsibilities shall be assigned in a manner that precludes 
conflict of duties and responsibilities that would prevent the execution 
of the safeguards contingency plan and emergency response plans.
    d. Licensees shall ensure that predetermined actions can be 
completed under the postulated conditions.
    5. Implementing Procedures.
    (i) Licensees shall establish and maintain written implementing 
procedures that provide specific guidance and operating details that 
identify the actions to be taken and decisions to be made by each member 
of the security organization who is assigned duties and responsibilities 
required for the effective implementation of the security plans and the 
site protective strategy.
    (ii) Licensees shall ensure that implementing procedures accurately 
reflect the information contained in the Responsibility Matrix required 
by this appendix, the security plans, and other site plans.
    (iii) Implementing procedures need not be submitted to the 
Commission for approval but are subject to inspection.

                         C. Records and Reviews

    1. Licensees shall review the safeguards contingency plan in 
accordance with the requirements of Sec. 73.55(m).
    2. The safeguards contingency plan audit must include a review of 
applicable elements of the Physical Security Plan, Training and 
Qualification Plan, implementing procedures and practices, the site 
protective strategy, and response agreements made by local, State, and 
Federal law enforcement authorities.
    3. Licensees shall retain all reports, records, or other 
documentation required by this appendix in accordance with the 
requirements of Sec. 73.55(q).

(Sec. 161i, Pub. L. 83-703, 68 Stat. 948, secs. 201, 204(b)(1), Pub L. 
93-438, 88 Stat. 1243, 1245 (42 U.S.C. 2201, 5841, 5844))

[43 FR 11965, Mar. 23, 1978; 43 FR 14007, Apr. 4, 1978, as amended at 57 
FR 33432, July 29, 1992; 64 FR 14818, Mar. 29, 1999; 72 FR 49562, Aug. 
28, 2007; 74 FR 13991, Mar. 27, 2009; 77 FR 39910, July 6, 2012]



 Sec. Appendix D to Part 73--Physical Protection of Irradiated Reactor 
           Fuel in Transit, Training Program Subject Schedule

    Pursuant to the provision of Sec. 73.37 of 10 CFR part 73, each 
licensee who transports or delivers to a carrier for transport 
irradiated reactor fuel is required to assure that individuals used as 
shipment escorts have completed a training program. The subjects that 
are to be included in this training program are as follows:

                            Security Enroute

--Route planning and selection
--Vehicle operation
--Procedures at stops
--Detours and use of alternate routes

                             Communications

--Equipment operation
--Status reporting
--Contacts with law enforcement units
--Communications discipline
--Procedures for reporting incidents

                       Radiological Considerations

--Description of the radioactive cargo
--Function and characteristics of the shipping casks
--Radiation hazards
--Federal, State and local ordinances relative to the shipment of 
          radioactive materials
--Responsible agencies

                        Response to Contingencies

--Accidents
--Severe weather conditions
--Vehicle breakdown
--Communications problems
--Radioactive ``spills''
--Use of special equipment (flares, emergency lighting, etc.)

[[Page 585]]

                           Response to Threats

--Reporting
--Calling for assistance
--Use of immobilization features
--Hostage situations
--Avoiding suspicious situations
    The licensee is also required to assure that armed individuals 
serving as shipment escorts, other than members of local law enforcement 
agencies, have completed a weapons training and qualifications program 
equivalent to that required of guards, as described in III and IV of 
appendix B of this part, to assure that each such individual is fully 
qualified to use weapons assigned him.

[44 FR 34468, June 15, 1979, as amended at 45 FR 34710, June 3, 1980]



Sec. Appendix E to Part 73--Levels of Physical Protection To Be Applied 
           in International Transport of Nuclear Material \1\
---------------------------------------------------------------------------

    \1\ See appendix C to part 110 of this chapter from the physical 
description of the categories of nuclear material as set forth in Annex 
I to the Convention. For the purposes of this part, the following 
categories of nuclear material are synonymous:
    Category I is a formula quantity of strategic special nuclear 
material;
    Category II is special nuclear material of moderate strategic 
significance or irradiated fuel; and
    Category III is special nuclear material of low strategic 
significance.
---------------------------------------------------------------------------

    (Verbatim from Annex I to the Convention on the Physical Protection 
of Nuclear Material)
    (a) Levels of physical protection for nuclear material during 
storage incidental to international nuclear transport include:
    (1) For Category III materials, storage within an area to which 
access is controlled;
    (2) For Category II materials, storage within an area under constant 
surveillance by guards or electronic devices, surrounded by a physical 
barrier with a limited number of points of entry under appropriate 
control or any area with an equivalent level of physical protection;
    (3) For Category I material, storage within a protected area as 
defined for Category II, to which, in addition, access is restricted to 
persons whose trustworthiness has been determined, and which is under 
surveillance by guards who are in close communication with appropriate 
response forces. Specific measures taken in this context should have as 
their objective the detection and prevention of any assault, 
unauthorized access, or unauthorized removal of material.
    (b) Levels of physical protection for nuclear material during 
international transport include:
    (1) For Category II and III materials, transportation shall take 
place under special precautions including prior arrangements among 
sender, receiver, and carrier, and prior agreement between natural or 
legal persons subject to the jurisdiction and regulation of exporting 
and importing States, specifying time, place and procedures for 
transferring transport responsibility;
    (2) For Category I materials, transportation shall take place under 
special precautions identified for transportation of Category II and III 
materials, and in addition, under constant surveillance by escorts and 
under conditions which assure close communication with appropriate 
response forces;
    (3) For natural uranium other than in the form of ore or ore 
residue, transportation protection for quantities exceeding 500 
kilograms U shall include advance notification of shipment specifying 
mode of transport, expected time of arrival and [shall provide for] 
confirmation of receipt of shipment.

[52 FR 9654, Mar. 26, 1987]



 Sec. Appendix F to Part 73--Nations That Are Parties to the Convention 
           on the Physical Protection of Nuclear Material \1\
---------------------------------------------------------------------------

    \1\ An update list of party nations will appear annually in the 
Department of State's publication, Treaties in Force. Appendix F will be 
amended as required to maintain its currency.

------------------------------------------------------------------------
                                                 Date of deposit of
                  Nation                     instrument of ratification
                                                    with the IAEA
------------------------------------------------------------------------
Brazil....................................  Oct. 17, 1985.
Bulgaria..................................  May 2, 1984.
Canada....................................  Mar. 21, 1986.
Czechoslovakia............................  Apr. 23, 1982.
German Democratic Republic (E. Germany)...  Feb. 5, 1981.
Guatemala.................................  Apr. 23, 1985.
Hungary...................................  May 4, 1984.
Indonesia.................................  Nov. 5, 1986.
Korea, Republic of........................  Apr. 7, 1982.
Liechtenstein.............................  Nov. 25, 1986.
Mongolia..................................  May 28, 1986.
Norway....................................  Aug. 15, 1985.
Paraguay..................................  Feb. 6, 1985.
Philippines...............................  Sept. 22, 1981.
Poland....................................  Oct. 5, 1983.
Sweden....................................  Aug. 1, 1980.
Switzerland...............................  Jan. 9, 1987.
Turkey....................................  Feb. 27, 1985.
Yugoslavia................................  May 14, 1986.
Union of Soviet Socialist Republic........  May 25, 1983.
United States of America..................  Dec. 13, 1982.
------------------------------------------------------------------------


[52 FR 9654, Mar. 26, 1987]

[[Page 586]]



        Sec. Appendix G to Part 73--Reportable Safeguards Events

    Pursuant to the provisions of 10 CFR 73.71 (b) and (c), licensees 
subject to the provisions of 10 CFR 73.20, 73.37, 73.50, 73.55, 73.60, 
and 73.67 shall report or record, as appropriate, the following 
safeguards events.
    I. Events to be reported within one hour of discovery, followed by a 
written report within 60 days.
    (a) Any event in which there is reason to believe that a person has 
commited or caused, or attempted to commit or cause, or has made a 
credible threat to commit or cause:
    (1) A theft or unlawful diversion of special nuclear material; or
    (2) Significant physical damage to a power reactor or any facility 
possessing SSNM or its equipment or carrier equipment transporting 
nuclear fuel or spent nuclear fuel, or to the nuclear fuel or spent 
nuclear fuel a facility or carrier possesses; or
    (3) Interruption of normal operation of a licensed nuclear power 
reactor through the unauthorized use of or tampering with its machinery, 
components, or controls including the security system.
    (b) An actual entry of an unauthorized person into a protected area, 
material access area, controlled access area, vital area, or transport.
    (c) Any failure, degradation, or the discovered vulnerability in a 
safeguard system that could allow unauthorized or undetected access to a 
protected area, material access area, controlled access area, vital 
area, or transport for which compensatory measures have not been 
employed.
    (d) The actual or attempted introduction of contraband into a 
protected area, material access area, vital area, or transport.
    II. Events to be recorded within 24 hours of discovery in the 
safeguards event log.
    (a) Any failure, degradation, or discovered vulnerability in a 
safeguards system that could have allowed unauthorized or undetected 
access to a protected area, material access area, controlled access 
area, vital area, or transport had compensatory measures not been 
established.
    (b) Any other threatened, attempted, or committed act not previously 
defined in appendix G with the potential for reducing the effectiveness 
of the safeguards system below that committed to in a licensed physical 
security or contingency plan or the actual condition of such reduction 
in effectiveness.

[52 FR 21658, June 9, 1987, as amended at 60 FR 13618, Mar. 14, 1995; 68 
FR 33617, June 5, 2003]

          Appendix H to Part 73--Weapons Qualification Criteria

    The B-27 Target or a target of equivalent difficulty will be used 
for all weapon qualification testing.

                                                       Table H-1--Minimum Day Firing Criteria \1\
                                                           [see footnotes at end of Table H-1]
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                             String                     Number of
               Weapon                 Stage     2         Distance        rounds          Timing 3                Position                Scoring
--------------------------------------------------------------------------------------------------------------------------------------------------------
Handgun............................       1       1  3 yards..........          6  9 seconds.............  Draw and fire 2 rounds  Minimum qualifying =
                                                  2                                                         (repeat 2 times) 3      70%.
                                                  3                                                         seconds each string.
                                          2       1  7 yards..........          6  10 seconds............  Draw and fire 2 rounds
                                                  2                                                         at center mass and 1
                                                                                                            round at the head
                                                                                                            (repeat once) 5
                                                                                                            seconds each string.
                                          3       1  7 yards..........          6  12 seconds (4 seconds   Using weaker hand
                                                  2                                 each string).           only, from the low
                                                  3                                                         ready position, fire
                                                                                                            2 rounds (repeat
                                                                                                            twice).
                                          4       1  10 yards.........          2  4 seconds.............  Draw and fire 2
                                                                                                            rounds, come to low
                                                                                                            ready position.
                                     ......       2  10 yards.........          2  3 seconds.............  Fire 2 rounds from low
                                                                                                            ready position and
                                                                                                            reholster.
                                     ......       3  10 yards.........          4  12 seconds (revolver)   Draw and fire 2
                                                                                    10 seconds              rounds, reload, fire
                                                                                    (semiautomatic).        2 rounds and
                                                                                                            reholster.
                                     ......       4  10 yards.........          2  4 seconds.............  Draw and fire 2
                                                                                                            rounds, come to low
                                                                                                            ready position.
                                     ......       5  10 yards.........          2  3 seconds.............  Fire 2 rounds from low
                                                                                                            ready position and
                                                                                                            reholster.
                                          5       1  15 yards.........          2  5 seconds.............  Standing, draw weapon,
                                                                                                            move to kneeling
                                                                                                            position, then fire 2
                                                                                                            rounds and reholster.

[[Page 587]]

 
                                     ......       2  15 yards.........          2  5 seconds.............  Standing, draw weapon,
                                                                                                            move to kneeling
                                                                                                            position, then fire 2
                                                                                                            rounds and reholster.
                                          5       3  15 yards.........          4  14 seconds (revolver)   Standing, draw weapon,  Minimum qualifying =
                                                                                    12 seconds              fire 2 rounds, move     70%.
                                                                                    (semiautomatic).        to kneeling position
                                                                                                            and fire 2 rounds,
                                                                                                            reload and reholster.
                                     ......       4  15 yards.........          2  5 seconds.............  Draw weapon and fire 2
                                                                                                            rounds standing, come
                                                                                                            to low ready position
                                                                                                            and....
                                     ......       5  15 yards.........          2  3 seconds.............  Fire 2 rounds from low
                                                                                                            ready.
                                          6       1  25 yards.........          2  5 seconds.............  Draw and fire 2
                                                                                                            rounds, standing,
                                                                                                            left side of
                                                                                                            barricade.
                                     ......       2  25 yards.........          2  5 seconds.............  Draw and fire 2
                                                                                                            rounds, right side of
                                                                                                            barricade (standing).
                                     ......       3  25 yards.........          4  15 seconds (revolver)   Draw weapon and move
                                                                                    12 seconds (semi-       from standing to
                                                                                    automatic).             kneeling position,
                                                                                                            fire 2 rounds, left
                                                                                                            side of barricade,
                                                                                                            reload, and from the
                                                                                                            kneeling position,
                                                                                                            fire 2 rounds, right
                                                                                                            side of barricade.
                                     ......       4  25 yards.........          2  10 seconds............  Draw weapon and move
                                                                                                            from standing to
                                                                                                            prone, fire 2 rounds.
                                     ......       5  25 yards.........          2  10 seconds............  Draw weapon and move
                                                                                                            from standing to
                                                                                                            prone, fire 2 rounds.
                                          7       1  50 yards.........          2  8 seconds.............  Draw weapon and fire 2
                                                                                                            rounds from a
                                                                                                            standing barricade
                                                                                                            position (right or
                                                                                                            left side, shooter's
                                                                                                            option).
                                     ......       2  50 yards.........          2  10 seconds............  Draw weapon and fire 2
                                                                                                            rounds from a
                                                                                                            kneeling barricade
                                                                                                            position (right or
                                                                                                            left side, shooter's
                                                                                                            option).
                                     ......       3  50 yards.........          2  12 seconds............  Draw weapon and fire 2
                                                                                                            rounds from prone
                                                                                                            position.
Shotgun............................       1       1  7 yards..........   2 Double  4 seconds.............  At low ready position   Minimum qualifying =
                                                                          0 buck-                           fire 2 rounds           70%.
                                                                             shot                           standing.
                                          2       1  15 yards.........   4 Double  15 seconds............  At low ready position
                                                  2                       0 buck-                           fire 2 rounds
                                                                             shot                           standing, reload and
                                                                                                            fire 2 rounds.
                                          3       1  25 yards.........   4 rifled  20 seconds............  On command, load 4
                                                  2                      slugs or                           rounds and fire 2
                                                                         00 buck-                           rounds standing and 2
                                                                             shot                           rounds kneeling.
Rifle..............................       1       1  15 yards.........          6  10 seconds (4 seconds   Standing in low ready   Minimum qualifying =
                                                  2                                 for 1st string, 3       position, move to       70%.
                                                  3                                 seconds for each of     standing point
                                                                                    2nd and 3rd string).    shoulder position (1
                                                                                                            magazine loaded with
                                                                                                            6 rounds, weapon in
                                                                                                            half-load
                                                                                                            configuration), fire
                                                                                                            2 rounds per string.
                                          2       1  25 yards.........          6  11 seconds (5 seconds   Standing in low ready
                                                  2                                 for 1st string, 3       position, move to
                                                  3                                 seconds for each of     standing point
                                                                                    2nd and 3rd string).    shoulder position (1
                                                                                                            magazine loaded with
                                                                                                            6 rounds, weapon in
                                                                                                            half-load
                                                                                                            configuration), fire
                                                                                                            2 rounds per string.
                                          3       1  25 yards.........          6  17 seconds (7 seconds   Standing in low ready
                                                  2                                 for 1st string, 5       position, move to
                                                  3                                 seconds for each of     kneeling point
                                                                                    2nd and 3rd string).    shoulder position (1
                                                                                                            magazine loaded with
                                                                                                            6 rounds, weapon in
                                                                                                            half-load
                                                                                                            configuration), fire
                                                                                                            2 rounds per string.
                                          4       1  50 yards.........          4  16 seconds (9 seconds   Standing in low ready
                                                  2                                 for 1st string, 7       position, move to
                                                                                    second for 2nd          kneeling point
                                                                                    string).                shoulder position (1
                                                                                                            magazine loaded with
                                                                                                            4 rounds, weapon in
                                                                                                            half-load
                                                                                                            configuration), fire
                                                                                                            2 rounds per string.

[[Page 588]]

 
                                       \4\5       1  50 yards.........          4  20 seconds............  Standing in low ready   Minimum qualifying =
                                                                                                            position, move to       70%.
                                                                                                            prone (weapon in half-
                                                                                                            load configuration)
                                                                                                            with two magazines
                                                                                                            each loaded with 2
                                                                                                            rounds, fire 2
                                                                                                            rounds, reload with
                                                                                                            2nd magazine and fire
                                                                                                            2 rounds.
                                       \4\6       1  100 yards........          4  25 seconds............  Standing in low ready
                                                                                                            position, move to
                                                                                                            prone (weapon in half-
                                                                                                            load configuration)
                                                                                                            two magazines each
                                                                                                            loaded with 2 rounds,
                                                                                                            fire 2 rounds, reload
                                                                                                            with 2nd magazine and
                                                                                                            fire 2 rounds.
--------------------------------------------------------------------------------------------------------------------------------------------------------
Footnotes:
\1\ This day firing qualifications course is to be used by all TRT members, armed response personnel, and guards.
\2\ A string is one of the different phases within a single stage.
\3\ Security personnel will be timed as shown.
\4\ Stages 5 and 6 are to be used for .30 caliber or larger rifles.


                                                        Table H-2--Minimum Night Firing Criteria
--------------------------------------------------------------------------------------------------------------------------------------------------------
             Weapon               Stage      Distance        No. of rounds         Timing             Position           Scoring            Lighting
--------------------------------------------------------------------------------------------------------------------------------------------------------
Handgun (Rev.).................       1  7 yds...........  12..............  35 seconds........  Standing-no        Minimum            For all courses
                                                                                                  artificial         qualifying = 70%.  0.2 footcandles
                                                                                                  support.                              at center mass
                                                                                                                                        of target area.
                                      2  15 yds..........  12..............  45 seconds........
Handgun (Semi-)................       1  7 yds...........  2 + clip........  30 seconds........  Standing-no
                                                                                                  artificial
                                                                                                  support.
                                      2  15 yds..........  2 + clip........  40 seconds........
Shotgun........................       1  25 yds..........  2 rifled slugs..  30 seconds (Load 2  Standing-strong    Rifled slug hits
                                                                              slugs--chamber      shoulder.          = strike area on
                                                                              empty--Time                            target (10, 9,
                                                                              starts--Commence                       7).
                                                                              firing).
                                      1  15 yds..........  5 Double 0        10 seconds (Load    Standing-strong    Double 0
                                                            buckshot.         5rds Buckshot--     shoulder.          Buckshot: Hits
                                                                              chamber, empty--                       in black = 2 pts
                                                                              Time starts--                          (5rds x 9
                                                                              Commence firing).                      pellets/rd x 2
                                                                                                                     pts = 90)
                                                                                                                     Minimum
                                                                                                                     qualifying = 70%.
Rifle..........................       1  25 yds..........  1-5rd mag.......  45 sec............  Standing-          Minimum
                                                                                                  barricade.         qualifying = 70%.
                                      2  25 yds..........  1-5rd mag.......  45 sec............  Standing.........
                                      3  25 yds..........  1-5rd mag.......  45 sec............  Kneeling.........
                                      4  25 yds..........  1-5rd mag.......  45 sec............  Prone ...........
--------------------------------------------------------------------------------------------------------------------------------------------------------
Note. All firing is to be done only at night. Use of night simulation equipment during daylight is not allowable. Use of site specific devices (i.e.,
  laser, etc.) should be included in the licensee amended security plan for NRC approval.


[58 FR 45785, Aug. 31, 1993]

[[Page 589]]



PART 74_MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL
--Table of Contents



                      Subpart A_General Provisions

Sec.
74.1 Purpose.
74.2 Scope.
74.4 Definitions.
74.5 Interpretations.
74.6 Communications.
74.7 Specific exemptions.
74.8 Information collection requirements: OMB approval.

       Subpart B_General Reporting and Recordkeeping Requirements

74.11 Reports of loss or theft or attempted theft or unauthorized 
          production of special nuclear material.
74.13 Material status reports.
74.15 Nuclear material transaction reports.
74.17 Special nuclear material physical inventory summary report.
74.19 Recordkeeping.

    Subpart C_Special Nuclear Material of Low Strategic Significance

74.31 Nuclear material control and accounting for special nuclear 
          material of low strategic significance.
74.33 Nuclear material control and accounting for uranium enrichment 
          facilities authorized to produce special nuclear material of 
          low strategic significance.

  Subpart D_Special Nuclear Material of Moderate Strategic Significance

74.41 Nuclear material control and accounting for special nuclear 
          material of moderate strategic significance.
74.43 Internal controls, inventory, and records.
74.45 Measurements and measurement control.

   Subpart E_Formula Quantities of Strategic Special Nuclear Material

74.51 Nuclear material control and accounting for strategic special 
          nuclear material.
74.53 Process monitoring.
74.55 Item monitoring.
74.57 Alarm resolution.
74.59 Quality assurance and accounting requirements.

                          Subpart F_Enforcement

74.81 Inspections.
74.82 Tests.
74.83 Violations.
74.84 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 53, 57, 161, 182, 223, 
234, 1701 (42 U.S.C. 2073, 2077, 2201, 2232, 2273, 2282, 2297f); Energy 
Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); 44 
U.S.C. 3504 note.

    Source: 50 FR 7579, Feb. 25, 1985, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 74.1  Purpose.

    (a) This part has been established to contain the requirements for 
the control and accounting of special nuclear material at fixed sites 
and for documenting the transfer of special nuclear material. General 
reporting requirements as well as specific requirements for certain 
licensees possessing special nuclear material of low strategic 
significance, special nuclear material of moderate strategic 
significance, and formula quantities of strategic special nuclear 
material are included. Requirements for the control and accounting of 
source material at enrichment facilities are also included.
    (b) The general conditions and procedures for the submittal of a 
license application for the activities covered in this part are detailed 
in Sec. 70.22 of this chapter.

[50 FR 7579, Feb. 25, 1985, as amended at 56 FR 55998, Oct. 31, 1991; 67 
FR 78144, Dec. 23, 2002]



Sec. 74.2  Scope.

    (a) The general reporting and recordkeeping requirements of subpart 
B of this part apply to each person licensed under this chapter who 
possesses special nuclear material in a quantity of one gram or more of 
contained uranium-235, uranium-233, or plutonium; or who transfers or 
receives a quantity of special nuclear material of one gram or more of 
contained uranium-235, uranium-233, or plutonium. The general reporting 
and recordkeeping requirements of subpart B of this part do not apply to 
licensees whose MC&A reporting and recordkeeping requirements are 
covered by Sec. Sec. 72.72, 72.76, and 72.78 of this chapter.
    (b) In addition, specific control and accounting requirements are 
included in subparts C, D, and E for certain licensees who:

[[Page 590]]

    (1) Possess and use formula quantities of strategic special nuclear 
material;
    (2) Possess and use special nuclear material of moderate strategic 
significance;
    (3) Possess and use special nuclear material of low strategic 
significance; or
    (4) Possess uranium source material and equipment capable of 
producing enriched uranium.
    (c) As provided in part 76 of this chapter, the regulations of this 
part establish procedures and criteria for material control and 
accounting for the issuance of a certificate of compliance or the 
approval of a compliance plan.

[67 FR 78144, Dec. 23, 2002, as amended at 73 FR 32463, June 9, 2008]



Sec. 74.4  Definitions.

    As used in this part:
    Abrupt loss means a loss occurring in the time interval between 
consecutive sequential performances of a material control test which is 
designed to detect anomalies potentially indicative of a loss of 
strategic special nuclear material from a specific unit of SSNM (i.e., a 
quantity characterized by a unique measurement) introduced into a 
process.
    Accessible location means a process location at which SSNM could be 
acquired without leaving evidence of the acquisition, i.e., without 
tools or other equipment to obviously violate the integrity of the 
containment.
    Act means the Atomic Energy Act of 1954 (68 Stat. 919), including 
any amendments thereto.
    Active inventory means the sum of additions to inventory, beginning 
inventory, ending inventory, and removals from inventory, after all 
common terms have been excluded. Common terms are any material values 
which appear in the active inventory calculation more than once and come 
from the same measurement.
    Additions to material in process means: (1) Receipts that are 
opened, except for receipts opened only for sampling and subsequently 
maintained under tamper-safing; (2) opened sealed sources; and (3) 
material removed from process for nonconformance with chemical or 
physical specifications that is subsequently reprocessed, measured for 
contained SSNM, and reintroduced to process.
    Alarm Threshold means a predetermined quantity of SSNM calculated 
from the specified probability of detection for a given loss and the 
standard deviation associated with a material control test. An alarm 
threshold serves to trigger a response action.
    Batch means a portion of source material or special nuclear material 
handled as a unit for accounting purposes at a key measurement point and 
for which the composition and quantity are defined by a single set of 
measurements. The source material or special nuclear material may be in 
bulk form or contained in a number of separate items.
    Beginning inventory (BI) means the book inventory quantity at the 
beginning of an inventory period, and is the reconciled physical 
inventory entered into the books as an adjusted inventory at the 
completion of the prior inventory period.
    Bias means the deviation of the expected value of a random variable 
from the corresponding correct or assigned value.
    Calibration means the process of determining the numerical 
relationship between the observed output of a measurement system and the 
value, based upon reference standards, of the characteristic being 
measured.
    Category IA material means SSNM directly useable in the manufacture 
of a nuclear explosive device, except if:
    (1) The dimensions are large enough (at least two meters in one 
dimension, greater than one meter in each of two dimensions, or greater 
than 25cm in each of three dimensions) to preclude hiding the item on an 
individual;
    (2) The total weight of an encapsulated item of SSNM is such that it 
cannot be carried inconspicuously by one person (i.e., at least 50 
kilograms gross weight); or
    (3) The quantity of SSNM (less than 0.05 formula kilograms) in each 
container requires protracted diversions to accumulate five formula 
kilograms.
    Category IB material means all SSNM material other than Category IA.

[[Page 591]]

    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Continuous process means a unit process in which feed material must 
be introduced in a systematic manner in order to maintain equilibrium 
conditions.
    Controlled access area means any temporarily or permanently 
established area which is clearly demarcated, access to which is 
controlled, and which affords isolation of the material or persons 
within it.
    DOE means the U.S. Department of Energy or its duly authorized 
representatives.
    Effective kilograms of special nuclear material means:
    (1) For plutonium and uranium-233 their weight in kilograms;
    (2) For uranium with an enrichment in the isotope U\235\ of 0.01 (1 
percent) and above, its element weight in kilograms multiplied by the 
square of its enrichment expressed as a decimal weight fraction; and
    (3) For uranium with an enrichment in the isotope U\235\ below 0.01 
(1 percent), its element weight in kilograms multiplied by 0.0001.
    Element means uranium or plutonium.
    Estimate means a specific numerical value arrived at by the 
application of an estimator.
    Estimator means a function of a sample measurement used to estimate 
a population parameter.
    Fissile isotope means: (1) Uranium U-233, or (2) uranium-235 by 
enrichment category, (3) plutonium-239, and (4) plutonium-241.
    Formula kilogram means SSNM in any combination in a quantity of 1000 
grams computed by the formula, grams = (grams contained U-235) + 2.5 
(grams U-233 + grams plutonium).
    Formula quantity means strategic special nuclear material in any 
combination in a quantity of 5,000 grams or more computed by the 
formula, grams = (grams contained U\235\) + 2.5 (grams U\233\ + grams 
plutonium).
    Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America, which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the Government.
    High enriched uranium means uranium enriched to 20 percent or 
greater in the isotope uranium-235.
    Inventory difference (ID) means the arithmetic difference obtained 
by subtracting the quantity of SNM tabulated from a physical inventory 
from the book inventory quantity. Book inventory quantity is equivalent 
to the beginning inventory (BI) plus additions to inventory (A) minus 
removals from inventory (R), while the physical inventory quantity is 
the ending inventory (EI) for the material balance period in question 
(as physically determined). Thus mathematically, ID = (BI + A-R) -EI or 
ID = BI + A-R-EI
    Item means any discrete quantity or container of special nuclear 
material or source material, not undergoing processing, having an unique 
identity and also having an assigned element and isotope quantity.
    License, except where otherwise specified, means a license issued 
pursuant to part 70 of this chapter.
    Low enriched uranium means uranium enriched below 20 percent in the 
isotope uranium-235.
    Material means special nuclear material.
    Material access area means any location which contains special 
nuclear material, within a vault or a building, the roof, walls, and 
floor of which constitute a physical barrier.
    Material balance means the determination of an inventory difference 
(ID).
    MC&A alarm means a situation in which there is: (1) an out-of-
location item or an item whose integrity has been violated, (2) an 
indication of a flow of SSNM where there should be none, or (3) a 
difference between a measured or observed amount or property of material 
and its corresponding predicted or property value that exceeds a 
threshold established to provide the detection capability required by 
Sec. 74.53.

[[Page 592]]

    Material control test means a comparison of a pre-established alarm 
threshold with the results of a process difference or process yield 
performed on a unit process.
    Material in process means any special nuclear material possessed by 
the licensee except in unopened receipts, sealed sources, measured waste 
discards, and ultimate product maintained under tamper-safing.
    Measurement includes sampling and means the determination of mass, 
volume, quantity, composition or other property of a material where such 
determinations are used for special nuclear material control and 
accounting purposes.
    Measurement system means all of the apparatus, equipment, 
instruments and procedures used in performing a measurement.
    Person means:
    (1) Any individual, corporation, partnership, firm, association, 
trust, estate, public or private institution, group, Government agency 
other than the Commission or the Department of Energy, except that the 
Department of Energy shall be considered a person within the meaning of 
the regulations in this part to the extent that its facilities and 
activities are subject to the licensing and related regulatory authority 
of the Commission pursuant to section 202 of the Energy Reorganization 
Act of 1974 (88 Stat. 1244), any state or any political subdivision of 
or any political entity within a state, any foreign government or nation 
or political subdivision of any such government or nation, or other 
entity; and
    (2) Any legal successor, representative, agent, or agency of the 
foregoing.
    Physical inventory means determination on a measured basis of the 
quantity of special nuclear material on hand at a given time. The 
methods of physical inventory and associated measurements will vary 
depending on the material to be inventoried and the process involved.
    Plant means a set of processes or operations (on the same site, but 
not necessarily all in the same building) coordinated into a single 
manufacturing, R&D, or testing effort. A scrap recovery operation, or an 
analytical laboratory, serving both onsite and offsite customers (or 
more than one onsite manufacturing effort) should be treated as a 
separate plant.
    Power of detection means the probability that the critical value of 
a statistical test will be exceeded when there is an actual loss of a 
specific SSNM quantity.
    Process difference (PD) means the determination of an ID on a unit 
process level with the additional qualification that difficult to 
measure components may be modeled.
    Process yield means the quantity of SSNM actually removed from a 
unit process compared with the quantity predicted (based on a measured 
input) to be available for removal. Process yield differs from a process 
difference in that holdup and sidestreams are not measured or modeled.
    Produce when used in relation to special nuclear material, means: 
(1) To manufacture, make, produce, or refine special nuclear material; 
(2) to separate special nuclear material from other substances in which 
such material may be contained; or (3) to make or to produce new special 
nuclear material.
    Random error means the deviation of a random variable from its 
expected value.
    Receipt means special nuclear material received by a licensee from 
an off-site source.
    Reconciliation means the process of evaluating and comparing 
licensee reports required under this part to the projected material 
balances generated by the Nuclear Materials Management and Safeguards 
System. This process is considered complete when the licensee resolves 
any differences between the reported and projected balances, including 
those listed for foreign obligated materials.
    Reference standard means a material, device, or instrument whose 
assigned value is known relative to national standards or nationally 
accepted measurement systems. This is also commonly referred to as a 
traceable standard.
    Removals from inventory means measured quantities of special nuclear 
material contained in:
    (1) Shipments;

[[Page 593]]

    (2) Waste materials transferred to an onsite holding account via a 
DOE/NRC Form 741 transaction;
    (3) Measured discards transported offsite; and
    (4) Effluents released to the environment.
    Removals of material from process (or removals from process) means 
measured quantities of special nuclear material contained in:
    (1) Effluents released to the environment;
    (2) Previously unencapsulated materials that have been encapsulated 
as sealed sources;
    (3) Waste materials that will not be subject to further onsite 
processing and which are under tamper-safing;
    (4) Ultimate product placed under tamper-safing; and
    (5) Any materials (not previously designated as removals from 
process) shipped offsite.
    Research and development means: (1) Theoretical analysis, 
exploration, or experimentation; or (2) the extension of investigative 
findings and theories of a scientific or technical nature into practical 
application for experimental and demonstration purposes, including the 
experimental production and testing of models, devices, equipment, 
materials, and processes.
    Scrap means the various forms of special nuclear material generated 
during chemical and mechanical processing, other than recycle material 
and normal process intermediates, which are unsuitable for continued 
processing, but all or part of which will be converted to useable 
material by appropriate recovery operations.
    Sealed source means any special nuclear material that is physically 
encased in a capsule, rod, element, etc. that prevents the leakage or 
escape of the special nuclear material and that prevents removal of the 
special nuclear material without penetration of the casing.
    Source material means source material as defined in section 11z. of 
the Act and in the regulations contained in part 40 of this chapter.
    Special nuclear material means:
    (1) Plutonium, uranium-233, uranium enriched in the isotope U\233\ 
or in the isotope U\235\, and any other material which the Commission, 
pursuant to the provisions of section 51 of the Atomic Energy Act of 
1954, as amended, determines to be special nuclear material, but does 
not include source material; or
    (2) Any material artificially enriched by any of the foregoing, but 
does not include source material.
    Special nuclear material of low strategic significance means:
    (1) Less than an amount of special nuclear material of moderate 
strategic significance, but more than 15 grams of uranium-235 (contained 
in uranium enriched to 20 percent or more in the U\235\ isotope) or 15 
grams of uranium-233 or 15 grams of plutonium or the combination of 15 
grams when computed by the equation, grams = grams contained U\235\ + 
grams plutonium + grams U\233\; or
    (2) Less than 10,000 grams but more than 1,000 grams of uranium-235 
(contained in uranium enriched to 10 percent or more, but less than 20 
percent in the U\235\ isotope); or
    (3) 10,000 grams or more of uranium-235 contained in uranium 
enriched above natural, but less than 10 percent in the U\235\ isotope.
    Special nuclear material of moderate strategic significance means:
    (1) Less than a formula quantity of strategic special nuclear 
material but more than 1,000 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in the U\235\ isotope) or more than 500 
grams of uranium-233 or plutonium or in a combined quantity of more than 
1,000 grams when computed by the equation, grams = (grams contained 
U\235\) + 2 (grams U\233\ + grams plutonium); or
    (2) 10,000 grams or more or uranium-235 (contained in uranium 
enriched to 10 percent or more but less than 20 percent in the U\235\ 
isotope).
    Standard Error of the Inventory Difference (SEID) means the standard 
deviation of an inventory difference that takes into account all 
measurement error contributions to the components of the ID.
    Standard Error of the Process Difference means the standard 
deviation of a process difference value that takes into account both 
measurement and nonmeasurement contributions to the components of PD.

[[Page 594]]

    Strategic special nuclear material means uranium-235 (contained in 
uranium enriched to 20 percent or more in the U\235\ isotope), uranium-
233, or plutonium.
    Tamper-safing means the use of devices on containers or vaults in a 
manner and at a time that ensures a clear indication of any violation of 
the integrity of previously made measurements of special nuclear 
material within the container or vault.
    Traceability means the ability to relate individual measurement 
results to national standards or nationally accepted measurement systems 
through an unbroken chain of comparisons.
    Ultimate product means any special nuclear material in the form of a 
product that would not be further processed at that licensed location.
    Unit process means an identifiable segment or segments of processing 
activities for which the amounts of input and output SSNM are based on 
measurements.
    Unopened receipts means receipts not opened by the licensee, 
including receipts of sealed sources, and receipts opened only for 
sampling and subsequently maintained under tamper-safing.
    Vault means a windowless enclosure with walls, floor, roof and 
door(s) designed and constructed to delay penetration from forced entry.

[50 FR 7579, Feb. 25, 1985, as amended at 52 FR 10039, Mar. 30, 1987; 56 
FR 55998, Oct. 31, 1991; 67 FR 78144, Dec. 23, 2002; 73 FR 32463, June 
9, 2008; 80 FR 45844, Aug. 3, 2015]



Sec. 74.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretations of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized as binding on 
the Commission.



Sec. 74.6  Communications.

    Any communication or report concerning the regulations in this part 
and any application filed under these regulations may be submitted to 
the Commission as follows:
    (a) By mail addressed to: ATTN: Document Control Desk, Director of 
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001.
    (b) By hand delivery to the NRC's offices at 11555 Rockville Pike, 
Rockville, Maryland.
    (c) Where practicable, by electronic submission, for example, via 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[50 FR 7579, Feb. 25, 1985, as amended at 53 FR 4112, Feb. 12, 1988; 53 
FR 43422, Oct. 27, 1988; 68 FR 58821, Oct. 10, 2003; 74 FR 62685, Dec. 
1, 2009; 80 FR 74981, Dec. 1, 2015]



Sec. 74.7  Specific exemptions.

    The Commission may, upon application of any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
will not endanger life or property or the common defense and security, 
and are otherwise in the public interest.



Sec. 74.8  Information collection requirements: OMB approval.

    (a) The Commission has submitted the information collection 
requirements contained in this part to the Office of Management and 
Budget (OMB) for approval as required by the Paperwork Reduction Act (44 
U.S.C. 3501 et seq.). The NRC may not conduct or sponsor, and a person 
is not required to respond to, a collection of information if it does 
not display a currently valid OMB control number. OMB has approved the 
information collection requirements contained in this part under control 
number 3150-0123.

[[Page 595]]

    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 74.11, 74.13, 74.15, 74.17, 74.19, 74.31, 
74.33, 74.41, 74.43, 74.45, 74.51, 74.57, and 74.59.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. These information collection requirements 
and the control numbers under which they are approved are as follows:
    (1) In Sec. 74.15, DOE/NRC Form-741 is approved under Control No. 
3150-0003.
    (2) In Sec. 74.13, DOE/NRC Form-742 is approved under Control No. 
3150-0004.
    (3) In Sec. 74.13, DOE/NRC Form-742C is approved under Control No. 
3150-0058.
    (4) In Sec. 74.17, NRC Form 327 is approved under Control No. 3150-
0139.

[50 FR 7579, Feb. 25, 1985, as amended at 52 FR 10040, Mar. 30, 1987; 52 
FR 19305, May 22, 1987; 56 FR 55998, Oct. 31, 1991; 62 FR 52189, Oct. 6, 
1997; 67 FR 78144, Dec. 23, 2002]



       Subpart B_General Reporting and Recordkeeping Requirements



Sec. 74.11  Reports of loss or theft or attempted theft or unauthorized
production of special nuclear material.

    (a) Each licensee who possesses one gram or more of contained 
uranium-235, uranium-233, or plutonium shall notify the NRC Operations 
Center within 1 hour of discovery of any loss or theft or other unlawful 
diversion of special nuclear material which the licensee is licensed to 
possess, or any incident in which an attempt has been made to commit a 
theft or unlawful diversion of special nuclear material. The requirement 
to report within 1 hour of discovery does not pertain to measured 
quantities of special nuclear material disposed of as discards or 
inventory difference quantities. Each licensee who operates an uranium 
enrichment facility shall notify the NRC Operations Center within 1 hour 
of discovery of any unauthorized production of enriched uranium. For 
centrifuge enrichment facilities the requirement to report enrichment 
levels greater than that authorized by license within 1 hour does not 
apply to each cascade during its start-up process, not to exceed the 
first 24 hours.
    (b) This notification must be made to the NRC Operations Center via 
the Emergency Notification System if the licensee is party to that 
system. If the Emergency Notification System is inoperative or 
unavailable, the licensee shall make the required notification via 
commercial telephonic service or other dedicated telephonic system or 
any other method that will ensure that a report is received by the NRC 
Operations Center within one hour. The exemption of Sec. 73.22(f)(3) 
applies to all telephonic reports required by this section.
    (c) Reports required under Sec. 73.71 need not be duplicated under 
requirements of this section.

[52 FR 21659, June 9, 1987; 52 FR 23257, June 18, 1987, as amended at 56 
FR 55998, Oct. 31, 1991, 81 FR 86910, Dec. 2, 2016]



Sec. 74.13  Material status reports.

    (a) Each licensee, including nuclear reactor licensees as defined in 
Sec. Sec. 50.21 and 50.22 of this chapter, possessing, or who had 
possessed in the previous reporting period, at any one time and 
location, special nuclear material in a quantity totaling one gram or 
more of contained uranium-235, uranium-233, or plutonium shall complete 
and submit, in computer-readable format Material Balance Reports 
concerning special nuclear material that the licensee has received, 
produced, possessed, transferred, consumed, disposed, or lost. This 
prescribed computer-readable report replaces the DOE/NRC form 742 which 
has been previously submitted in paper form. The Physical Inventory 
Listing Report must be submitted with each Material Balance Report. This 
prescribed computer-readable report replaces the DOE/NRC Form 742C which 
has been previously submitted in paper form. Reports must be submitted 
for each Reporting Identification Symbol (RIS) account including all 
holding accounts. Each licensee shall prepare and submit the reports 
described in this paragraph as specified in the instructions in NUREG/
BR-0007 and NMMSS Report D-24 ``Personal Computer Data Input for NRC 
Licensees.'' Copies of these instructions may be obtained from the U.S. 
Nuclear Regulatory Commission, Division of Fuel

[[Page 596]]

Cycle Safety, Safeguards, and Environmental Review, Washington, DC 
20555-0001, or by e-mail to [email protected]. Each licensee subject 
to the requirements of Sec. 74.51 shall compile a report as of March 31 
and September 30 of each year and file it within 30 days after the end 
of the period covered by the report. Licensees subject to the 
requirements of Sec. Sec. 74.19(c), 74.31(c)(5), 74.33(c)(4), or 
74.43(c)(6) shall submit a report within 60 calendar days of the 
beginning of the physical inventory. All other licensees shall submit a 
report no later than March 31 of each year. The Commission may permit a 
licensee to submit the reports at other times for good cause. Each 
licensee required to report material balance, and inventory information, 
as detailed in this part, shall resolve any discrepancies identified 
during the report review and reconciliation process within 30 calendar 
days of notification of a discrepancy identified by NRC.
    (b) Any licensee who is required to submit routine Material Status 
Reports pursuant to Sec. 75.35 of this chapter (pertaining to 
implementation of the US/IAEA Safeguards Agreement) shall prepare and 
submit these reports only as provided in that section (instead of as 
provided in paragraph (a) of this section).

[67 FR 78144, Dec. 23, 2002, as amended at 73 FR 32463, June 9, 2008; 79 
FR 75741, Dec. 19, 2014]



Sec. 74.15  Nuclear material transaction reports.

    (a) Each licensee who transfers or receives special nuclear material 
in a quantity of one gram or more of contained uranium-235, uranium-233, 
or plutonium shall complete in computer-readable format a Nuclear 
Material Transaction Report. In addition, each licensee who adjusts the 
inventory in any manner, other than for transfers and receipts, shall 
submit a Nuclear Material Transaction Report, in computer-readable 
format, to coincide with the submission of the Material Balance report. 
This shall be done as specified in the instructions in NUREG/BR-0006 and 
NMMSS Report D-24, ``Personal Computer Data Input for NRC Licensees.'' 
Copies of these instructions NUREG/BR-0006 and NMMSS Report D-24, 
``Personal Computer Data Input for NRC Licensees'' may be obtained 
either by writing the U.S. Nuclear Regulatory Commission, Division of 
Fuel Cycle Safety, Safeguards, and Environmental Review, Washington, DC 
20555-0001, or by e-mail to [email protected]. Each licensee who 
transfers the material shall submit a Nuclear Material Transaction 
Report in computer-readable format as specified in the instructions no 
later than the close of business the next working day. Each licensee who 
receives the material shall submit a Nuclear Material Transaction Report 
in computer-readable format in accordance with instructions within ten 
(10) days after the material is received. This prescribed computer-
readable format replaces the DOE/NRC Form 741 which has been previously 
submitted in paper form.
    (b) Each licensee who receives 1 gram or more of contained uranium-
235, uranium-233, or plutonium from a foreign source shall:
    (1) Complete in computer-readable format both the supplier's and 
receiver's portion of the Nuclear Material Transaction Report;
    (2) Perform independent tests to assure the accurate identification 
and measurement of the material received, including its weight and 
enrichment; and
    (3) Indicate the results of these tests on the receiver's portion of 
the form.
    (c) Each licensee who ships special nuclear material in a quantity 
of one gram or more of contained uranium-235, uranium-233, or plutonium 
to foreign recipient shall complete in computer-readable format the 
supplier's portion of the Nuclear Material Transaction Report. The 
licensee shall complete the receiver's portion of the Nuclear Material 
Transaction Report only if a significant shipper-receiver difference as 
described in Sec. Sec. 74.31, 74.43, or 74.59, as applicable, is 
identified.
    (d) Any licensee who is required to submit inventory change reports 
pursuant to Sec. 75.34 of this chapter (pertaining to implementation of 
the US/International Atomic Energy Agency (IAEA) Safeguards Agreement) 
shall prepare and submit these reports only

[[Page 597]]

as provided in that section (instead of as provided in paragraphs (a) 
and (b) of this section).

[59 FR 35621, July 13, 1994, as amended at 68 FR 58821, Oct. 10, 2003; 
73 FR 32464, June 9, 2008; 79 FR 75741, Dec. 19, 2014]



Sec. 74.17  Special nuclear material physical inventory summary 
report.

    (a) Each licensee subject to the requirements of Sec. Sec. 74.31 or 
74.33 of this part shall submit a completed Special Nuclear Material 
Physical Inventory Summary Report on NRC Form 327 not later than 60 
calendar days from the start of each physical inventory required by 
Sec. Sec. 74.31(c)(5) or 74.33(c)(4). Using an appropriate method 
listed in Sec. 74.6, the licensee shall report the inventory results by 
plant and total facility to the Director of the NRC's Office of Nuclear 
Material Safety and Safeguards.
    (b) Each licensee subject to the requirements of Sec. 74.41(a) of 
this part shall submit a completed Special Nuclear Material Physical 
Inventory Summary Report on NRC form 327 not later than 60 calendar days 
from the start of each physical inventory required by Sec. 74.43(c)(7). 
Using an appropriate method listed in Sec. 74.6, the licensee shall 
report the inventory results by plant and total facility to the Director 
of the NRC's Office of Nuclear Material Safety and Safeguards.
    (c) Each licensee subject to the requirements of Sec. 74.51 shall 
submit a completed Special Nuclear Material Physical Inventory Summary 
Report on NRC form 327 not later than 45 calendar days from the start of 
each physical inventory required by Sec. 74.59(f). The licensee shall 
report the physical inventory results by plant and total facility to the 
Director, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001.

[67 FR 78145, Dec. 23, 2002, as amended at 68 FR 58821, Oct. 10, 2003]



Sec. 74.19  Recordkeeping

    (a) Licensees subject to the recordkeeping requirements of 
Sec. Sec. 74.31, 74.33, 74.43, or 74.59 of this part are exempt from 
the requirements of paragraphs (a)(1) through (4) of this section. 
Otherwise:
    (1) Each licensee shall keep records showing the receipt, inventory 
(including location and unique identity), acquisition, transfer, and 
disposal of all special nuclear material in its possession regardless of 
its origin or method of acquisition.
    (2) Each record relating to material control or material accounting 
that is required by the regulations in this chapter or by license 
condition must be maintained and retained for the period specified by 
the appropriate regulation or license condition. If a retention period 
is not otherwise specified by regulation or license condition, the 
licensee shall retain the record until the Commission terminates the 
license that authorizes the activity that is subject to the 
recordkeeping requirement.
    (3) Each record of receipt, acquisition, or physical inventory of 
special nuclear material that must be maintained pursuant to paragraph 
(a)(1) of this section must be retained as long as the licensee retains 
possession of the material and for 3 years following transfer or 
disposal of the material.
    (4) Each record of transfer of special nuclear material to other 
persons must be retained by the licensee who transferred the material 
until the Commission terminates the license authorizing the licensee's 
possession of the material.
    (b) Each licensee that is authorized to possess special nuclear 
material in a quantity exceeding one effective kilogram at any one time 
shall establish, maintain, and follow written material control and 
accounting procedures that are sufficient to enable the licensee to 
account for the special nuclear material in its possession under 
license. The licensee shall retain these procedures until the Commission 
terminates the license that authorizes possession of the material and 
retain any superseded portion of the procedures for 3 years after the 
portion is superseded.
    (c) Other than licensees subject to Sec. Sec. 74.31, 74.33, 74.41, 
or 74.51, each licensee who is authorized to possess special nuclear 
material, at any one time and site location, in a quantity greater than 
350 grams of contained uranium-235, uranium-233, or plutonium, or any 
combination thereof, shall conduct a physical inventory of

[[Page 598]]

all special nuclear material in its possession under license at 
intervals not to exceed 12 months. The results of these physical 
inventories need not be reported to the Commission, but the licensee 
shall retain the records associated with each physical inventory until 
the Commission terminates the license that authorized the possession of 
special nuclear material.
    (d) Records that must be maintained pursuant to this part may be the 
original or a reproduced copy or a microform if the reproduced copy or 
microform is duly authenticated by authorized personnel and the 
microform is capable of producing a clear and legible copy after storage 
for the period specified by Commission regulations. The record may also 
be stored in electronic media with the capability for producing legible, 
accurate, and complete records during the required retention period. 
Records such as letters, drawings, or specifications must include all 
pertinent information such as stamps, initials, and signatures. The 
licensee shall maintain adequate safeguards against tampering with and 
loss of records.

[67 FR 78145, Dec. 23, 2002]



    Subpart C_Special Nuclear Material of Low Strategic Significance



Sec. 74.31  Nuclear material control and accounting for special 
nuclear material of low strategic significance.

    (a) General performance objectives. Each licensee who is authorized 
to possess and use more than one effective kilogram of special nuclear 
material of low strategic significance, excluding sealed sources, at any 
site or contiguous sites subject to control by the licensee, other than 
a production or utilization facility licensed pursuant to part 50 or 70 
of this chapter, or operations involved in waste disposal, shall 
implement and maintain a Commission approved material control and 
accounting system that will achieve the following objectives:
    (1) Confirm the presence of special nuclear material;
    (2) Resolve indications of missing material; and
    (3) Aid in the investigation and recovery of missing material.
    (b) Implementation. Each applicant for a license, and each licensee 
that, upon application for modification of its license, would become 
newly subject to the performance objectives of paragraph (a) of this 
section, shall submit a fundamental nuclear material control (FNMC) plan 
describing how the requirements of paragraph (c) of this section will be 
met. The FNMC plan shall be implemented when a license is issued or 
modified to authorize the activities being addressed in paragraph (a) of 
this section, or by the date specified in a license condition.
    (c) System capabilities. To meet the general performance objectives 
of paragraph (a) of this section, the material control and accounting 
system must include the capabilities described in paragraph (c) (1) 
through (8) of this section. The licensee shall:
    (1) Establish, document, and maintain a management structure which 
assures clear overall responsibility for material control and accounting 
functions, independence from production responsibilities, separation of 
key responsibilities, and adequate review and use of critical material 
control and accounting procedures;
    (2) Establish and maintain a measurement system which assures that 
all quantities in the material accounting records are based on measured 
values;
    (3) Follow a measurement control program which assures that 
measurement bias is estimated and significant biases are eliminated from 
inventory difference values of record;
    (4) In each inventory period, control total material control and 
accounting measurement uncertainty so that twice its standard error is 
less than the greater of 9,000 grams of U-235 or 0.25 percent of the 
active inventory, and assure that any measurement performed under 
contract is controlled so that the licensee can satisfy this 
requirement;
    (5) Unless otherwise required to satisfy part 75 of this chapter, 
perform a physical inventory at least every 12 months and, within 60 
days after the start of the inventory, reconcile and adjust the book 
inventory to the results of the physical inventory, and resolve, or 
report an inability to resolve,

[[Page 599]]

any inventory difference which is rejected by a statistical test which 
has a 90 percent power of detecting a discrepancy of a quantity of 
uranium-235 established by NRC on a site-specific basis;
    (6) Maintain current knowledge of items when the sum of the time of 
existence of an item, the time to make a record of the item, and the 
time necessary to locate the item exceeds 14 days. Store and handle, or 
subsequently measure, items in a manner so that unauthorized removals of 
substantial quantities of material from items will be detected. Exempted 
are items individually containing less than 500 grams of U\235\ up to a 
total of 50 kilograms of U\235\, solutions with a concentration of less 
than 5 grams of U\235\ per liter, and items of waste destined for burial 
or incineration;
    (7) Resolve, on a shipment basis and when required to satisfy part 
75 of this chapter, on a batch basis, shipper/receiver differences that 
exceed both twice the combined measurement standard error for that 
shipment and 500 grams of U\235\; and
    (8) Independently assess the effectiveness of the material control 
and accounting system at least every 24 months, and document 
management's action on prior assessment recommendations.
    (d) Recordkeeping. (1) Each licensee shall establish records that 
will demonstrate that the requirements of paragraph (c) of this section 
have been met and maintain these records for at least 3 years, unless a 
longer retention time is required by part 75 of this chapter.
    (2) Records which must be maintained pursuant to this part may be 
the original or a reproduced copy or a microform if such reproduced copy 
or microform is duly authenticated by authorized personnel and the 
microform is capable of producing a clear and legible copy after storage 
for the period specified by Commission regulations. The record may also 
be stored in electronic media with the capability for producing legible, 
accurate, and complete records during the required retention period. 
Records such as letters, drawings, specifications, must include all 
pertinent information such as stamps, initials, and signatures.
    The licensee shall maintain adequate safeguards against tampering 
with and loss of records.

[50 FR 7579, Feb. 25, 1985, as amended at 53 FR 19262, May 27, 1988; 56 
FR 55998, Oct. 31, 1991; 67 FR 78145, Dec. 23, 2002]



Sec. 74.33  Nuclear material control and accounting for uranium
enrichment facilities authorized to produce special nuclear 
material of low strategic significance.

    (a) General performance objectives. Each licensee who is authorized 
by this chapter to possess equipment capable of enriching uranium or 
operate an enrichment facility, and produce, possess, or use more than 
one effective kilogram of special nuclear material of low strategic 
significance at any site or contiguous sites, subject to control by the 
licensee, shall establish, implement, and maintain a NRC-approved 
material control and accounting system that will achieve the following 
objectives:
    (1) Maintain accurate, current, and reliable information of and 
periodically confirm the quantities and locations of source material and 
special nuclear material in the licensee's possession;
    (2) Protect against and detect production of uranium enriched to 10 
percent or more in the isotope U\235\;
    (3) Protect against and detect unauthorized production of uranium of 
low strategic significance;
    (4) Resolve indications of missing uranium;
    (5) Resolve indications of production of uranium enriched to 10 
percent or more in the isotope U\235\ (for centrifuge enrichment 
facilities this requirement does not apply to each cascade during its 
start-up process, not to exceed the first 24 hours);
    (6) Resolve indications of unauthorized production of uranium of low 
strategic significance;
    (7) Provide information to aid in the investigation of missing 
uranium;
    (8) Provide information to aid in the investigation of the 
production of uranium enriched to 10 percent or more in the isotope 
U\235\; and
    (9) Provide information to aid in the investigation of unauthorized 
production of uranium of low strategic significance.

[[Page 600]]

    (b) Implementation dates. Each applicant for a license who would, 
upon issuance of a license pursuant to any part of this chapter, be 
subject to the requirements of paragraph (a) of this section shall:
    (1) Submit a fundamental nuclear material control plan describing 
how the performance objectives of Sec. 74.33(a), the system features 
and capabilities of Sec. 74.33(c), and the recordkeeping requirements 
of Sec. 74.33(d) will be met; and
    (2) Implement the NRC approved plan submitted pursuant to paragraph 
(b)(1) of this section prior to:
    (i) The cumulative receipt of 5,000 grams of U\235\ contained in any 
combination of natural, depleted, or enriched uranium or
    (ii) NRC's issuance of a license to test or operate the enrichment 
facility; whichever occurs first.
    (c) System features and capabilities. To meet the general 
performance objectives of paragraph (a) of this section, the Material 
Control and Accounting (MC&A) system must include the features and 
capabilities described in paragraphs (c) (1) through (8) of this 
section. The licensee shall establish, document, and maintain:
    (1) A management structure that ensures:
    (i) Clear overall responsibility for MC&A functions;
    (ii) Independence of MC&A management from production 
responsibilities;
    (iii) Separation of key MC&A responsibilities from each other; and
    (iv) Use of approved written MC&A procedures and periodic review of 
those procedures;
    (2) A measurement program that ensures that all quantities of source 
material and special nuclear material in the accounting records are 
based on measured values;
    (3) A measurement control program that ensures that:
    (i) Measurement bias is estimated and minimized through the 
measurement control program, and any significant biases are eliminated 
from inventory difference values of record;
    (ii) All MC&A measurement systems are controlled so that twice the 
standard error of the inventory difference, based on all measurement 
error contributions, is less than the greater of 5,000 grams of U\235\ 
or 0.25 percent of the U\235\ of the active inventory for each total 
plant material balance; and
    (iii) Any measurements performed under contract are controlled so 
that the licensee can satisfy the requirements of paragraphs (c)(3) (i) 
and (ii) of this section;
    (4) A physical inventory program that provides for:
    (i) Performing, unless otherwise required to satisfy part 75 of this 
chapter, a dynamic (nonshutdown) physical inventory of in-process (e.g., 
in the enrichment equipment) uranium and U\235\ at least every 65 days, 
and performing a static physical inventory of all other uranium and 
total U\235\ contained in natural, depleted, and enriched uranium 
located outside of the enrichment processing equipment at least every 
370 calendar days, with static physical inventories being conducted in 
conjunction with a dynamic physical inventory of in-process uranium and 
U\235\ so as to provide a total plant material balance at least every 
370 calendar days; and
    (ii) Reconciling and adjusting the book inventory to the results of 
the static physical inventory and resolving, or reporting an inability 
to resolve, any inventory difference that is rejected by a statistical 
test which has a 90 percent power of detecting a discrepancy of a 
quantity of U\235\, established by NRC on a site-specific basis, within 
60 days after the start of each static physical inventory;
    (5) A detection program, independent of production, that provides 
high assurance of detecting:
    (i) Production of uranium enriched to 10 percent or more in the 
U\235\ isotope, to the extent that SNM of moderate strategic 
significance could be produced within any 370 calendar day period;
    (ii) Production of uranium enriched to 20 percent or more in the 
U\235\ isotope; and
    (iii) Unauthorized production of uranium of low strategic 
significance;
    (6) An item control program that ensures that:
    (i) Current knowledge is maintained of items with respect to 
identity, uranium and U\235\ content, and stored location; and

[[Page 601]]

    (ii) Items are stored and handled, or subsequently measured, in a 
manner so that unauthorized removal of 500 grams or more of U\235\, as 
individual items or as uranium contained in items, will be detected. 
Exempted from the requirements of paragraph (c)(6) (i) and (ii) of this 
section are licensed-identified items each containing less than 500 
grams U\235\ up to a cumulative total of 50 kilograms of U\235\ and 
items that exist for less than 14 calendar days;
    (7) A resolution program that ensures that any shipper-receiver 
differences are resolved that are statistically significant and exceed 
500 grams U\235\ on:
    (i) An individual batch basis; and
    (ii) A total shipment basis for all source material and special 
nuclear material;
    (8) An assessment program that:
    (i) Independently assesses the effectiveness of the MC&A system at 
least every 24 months;
    (ii) Documents the results of the above assessment;
    (iii) Documents management's findings on whether the MC&A system is 
currently effective; and
    (iv) Documents any actions taken on recommendations from prior 
assessments.
    (d) Recordkeeping. (1) Each licensee shall establish records that 
will demonstrate that the performance objectives of paragraph (a) of 
this section and the system features and capabilities of paragraph (c) 
of this section have been met and maintain these records in an auditable 
form, available for inspection, for at least 3 years, unless a longer 
retention time is required by part 75 of this chapter.
    (2) Records that must be maintained pursuant to this part may be the 
original or a reproduced copy or a microform if such reproduced copy or 
microform is duly authenticated by authorized personnel and the 
microform is capable of producing a clear and legible copy after storage 
for the period specified by Commission regulations. The record may also 
be stored in electronic media with the capability for producing, on 
demand, legible, accurate, and complete records during the required 
retention period. Records such as letters, drawings, and specifications 
must include all pertinent information such as stamps, initials, and 
signatures.
    (3) The licensee shall maintain adequate safeguards against 
tampering with and loss of records.

[56 FR 55999, Oct. 31, 1991]



  Subpart D_Special Nuclear Material of Moderate Strategic Significance



Sec. 74.41  Nuclear material control and accounting for special
nuclear material of moderate strategic significance.

    (a) General performance objectives. Each licensee who is authorized 
to possess special nuclear material (SNM) of moderate strategic 
significance or SNM in a quantity exceeding one effective kilogram of 
strategic special nuclear material in irradiated fuel reprocessing 
operations other than as sealed sources and to use this material at any 
site other than a nuclear reactor licensed pursuant to part 50 of this 
chapter; or as reactor irradiated fuels involved in research, 
development, and evaluation programs in facilities other than irradiated 
fuel reprocessing plants; or an operation involved with waste disposal, 
shall establish, implement, and maintain a Commission-approved material 
control and accounting (MC&A) system that will achieve the following 
performance objectives:
    (1) Maintain accurate, current, and reliable information on, and 
confirm, the quantities and locations of SNM in the licensee's 
possession;
    (2) Conduct investigations and resolve any anomalies indicating a 
possible loss of special nuclear material;
    (3) Permit rapid determination of whether an actual loss of a 
significant quantity of SNM has occurred, with significant quantity 
being either:
    (i) More than one formula kilogram of strategic SNM; or
    (ii) 10,000 grams or more of uranium-235 contained in uranium 
enriched up to 20.00 percent.
    (4) Generate information to aid in the investigation and recovery of 
missing SNM in the event of an actual loss.
    (b) Implementation schedule. Each applicant for a license, and each 
licensee that, upon application for modification

[[Page 602]]

of its license, would become newly subject to the requirements of 
paragraph (a) of this section shall:
    (1) Submit a fundamental nuclear material control (FNMC) plan 
describing how the performance objectives of Sec. 74.41(a) will be 
achieved, and how the system capabilities required by Sec. 74.41(c) 
will be met; and
    (2) Implement the NRC-approved FNMC plan submitted pursuant to 
paragraph (b)(1) of this section upon the Commission's issuance or 
modification of a license or by the date specified in a license 
condition.
    (c) System capabilities. To achieve the performance objectives 
specified in Sec. 74.41(a), the MC&A system must include the 
capabilities described in Sec. Sec. 74.43 and 74.45, and must 
incorporate checks and balances that are sufficient to detect 
falsification of data and reports that could conceal diversion of SNM 
by:
    (1) A single individual, including an employee in any position; or
    (2) Collusion between two individuals, one or both of whom have 
authorized access to SNM.

[67 FR 78146, Dec. 23, 2002]



Sec. 74.43  Internal controls, inventory, and records.

    (a) General. Licensees subject to Sec. 74.41 shall maintain the 
internal control, inventory, and recordkeeping capabilities required in 
paragraphs (b), (c), and (d) of this section.
    (b) Internal controls.
    (1) A management structure shall be established, documented, and 
maintained that assures:
    (i) Clear overall responsibility for material control and accounting 
(MC&A) functions;
    (ii) Independence from production and manufacturing 
responsibilities; and
    (iii) Separation of key responsibilities.
    (2) The overall planning, coordination, and administration of the 
MC&A functions for special nuclear material (SNM) shall be vested in a 
single individual at an organizational level sufficient to assure 
independence of action and objectiveness of decisions.
    (3) The licensee shall provide for the adequate review, approval, 
and use of written MC&A procedures that are identified in the approved 
FNMC plan as being critical to the effectiveness of the described 
system.
    (4) The licensee shall assure that personnel who work in key 
positions where mistakes could degrade the effectiveness of the MC&A 
system are trained to maintain a high level of safeguards awareness and 
are qualified to perform their duties and/or responsibilities.
    (5) The licensee shall establish, document, and maintain an item 
control program that:
    (i) Provides current knowledge of SNM items with respect to 
identity, element and isotope content, and stored location; and
    (ii) Assures that SNM items are stored and handled, or subsequently 
measured, in a manner such that unauthorized removal of 200 grams or 
more of plutonium or uranium-233 or 300 grams or more of uranium-235, as 
one or more whole items and/or as SNM removed from containers, will be 
detected.
    (6) Exempted from the requirements of paragraph (b)(5) of this 
section are items that exist for less than 14 calendar days and 
licensee-identified items each containing less than 200 grams of 
plutonium or uranium-233 or 300 grams or more of uranium-235 up to a 
cumulative total of one formula kilogram of strategic SNM or 17 
kilograms of uranium-235 contained in uranium enriched to 10.00 percent 
or more but less than 20.00 percent in the uranium-235 isotope.
    (7) Conduct and document shipper-receiver comparisons for all SNM 
receipts, both on an individual batch basis and a total shipment basis, 
and ensure that any shipper-receiver difference that is statistically 
significant and exceeds twice the estimated standard deviation of the 
difference estimator and 200 grams of plutonium or uranium-233 or 300 
grams of uranium-235 is investigated and resolved; and
    (8) Perform independent assessments of the total MC&A system, at 
intervals not to exceed 18 months, that assess the performance of the 
system, review its effectiveness, and document management's action on 
prior assessment

[[Page 603]]

recommendations and identified deficiencies. These assessments must 
include a review and evaluation of any contractor who performs SNM 
accountability measurements for the licensee.
    (c) Inventory control and physical inventories. The licensee shall:
    (1) Provide unique identification for each item on inventory and 
maintain inventory records showing the identity, location, and quantity 
of SNM for these items;
    (2) Document all transfers of SNM between designated internal 
control areas within the licensee's site;
    (3) Maintain and follow procedures for tamper-safing of containers 
or vaults containing SNM, if tamper-safe seals are to be used for 
assuring the validity of prior measurements, which include control of 
access to, and distribution of, unused seals and to records showing the 
date and time of seal application;
    (4) Maintain and follow procedures for confirming the validity of 
prior measurements associated with unencapsulated and unsealed items on 
ending inventory;
    (5) Maintain and follow physical inventory procedures to assure 
that:
    (i) The quantity of SNM associated with each item on ending 
inventory is a measured value;
    (ii) Each item on ending inventory is listed and identified to 
assure that all items are listed and no item is listed more than once;
    (iii) Cutoff procedures for transfers and processing are established 
so that all quantities are inventoried and none are inventoried more 
than once;
    (iv) Cutoff procedures for records and reports are established so 
that only transfers for the inventory and material balance interval are 
included in the records for the material balance period in question;
    (v) Upon completion of the physical inventory, all book and 
inventory records, for total plant and individual internal control 
areas, are reconciled with and adjusted to the results of the physical 
inventory; and
    (vi) Measurements will be performed for element and isotope content 
on all quantities of SNM not previously measured.
    (6) Conduct physical inventories according to written instructions 
for each physical inventory which:
    (i) Assign inventory duties and responsibilities;
    (ii) Specify the extent to which each internal control area and 
process is to be shut down, cleaned out, and/or remain static;
    (iii) Identify the basis for accepting previously made measurements 
and their limits of error; and
    (iv) Designate measurements to be made for physical inventory 
purposes and the procedures for making these measurements.
    (7) Conduct physical inventories of all possessed SNM for each plant 
at intervals not to exceed 9 calendar months; and
    (8) Within 60 calendar days after the start of each physical 
inventory required by paragraph (c)(7) of this section:
    (i) Calculate, for the material balance period terminated by the 
physical inventory, the inventory difference (ID) and its associated 
standard error of inventory difference (SEID) for both element and 
isotope;
    (ii) Reconcile and adjust the book record of quantity of element and 
isotope content, as appropriate, to the results of the physical 
inventory; and
    (iii) Investigate and report to the Director, Office of Nuclear 
Material Safety and Safeguards, any occurrence of SEID exceeding 0.125 
percent of active inventory, and any occurrence of ID exceeding both 
three times SEID and 200 grams of plutonium or uranium-233 or 300 grams 
of uranium-235 contained in high enriched uranium, or 9000 grams of 
uranium-235 contained in low enriched uranium. The report shall include 
a statement of the probable reasons for the excessive inventory 
difference and the corrective actions taken or planned.
    (d) Recordkeeping. The licensee shall:
    (1) Maintain records of the receipt, shipment, disposal, and current 
inventory associated with all possessed SNM;
    (2) Maintain records of the quantities of SNM added to and removed 
from process;

[[Page 604]]

    (3) Maintain records of all shipper-receiver evaluations associated 
with SNM receipts;
    (4) Retain each record pertaining to receipt and disposal of SNM 
until the Commission terminates the license; and
    (5) Establish records that will demonstrate that the performance 
objectives of Sec. 74.41(a)(1) through (4), the system capabilities of 
paragraphs (b) and (c) of this section and Sec. 74.45(b) and (c) have 
been met, and maintain these records in an auditable form, available for 
inspection, for at least 3 years, unless a longer retention time is 
specified by Sec. 74.19(b), part 75 of this chapter, or by a specific 
license condition.

[67 FR 78146, Dec. 23, 2002]



Sec. 74.45  Measurements and measurement control.

    (a) General. Licensees subject to Sec. 74.41 of this part shall 
establish and maintain the measurement and measurement control 
capabilities required by paragraphs (b) and (c) of this section.
    (b) Measurements. The licensee shall:
    (1) Establish, maintain, and use a program for the measurement of 
all SNM received, produced, transferred between internal control areas, 
on inventory, or shipped, discarded, or otherwise removed from 
inventory, except for:
    (i) Sealed sources that have been determined by other means to 
contain less than 10 grams of uranium-235, uranium-233, or plutonium 
each;
    (ii) Samples received, transferred between internal control areas, 
or on inventory that have been determined by other means to contain less 
than 10 grams of uranium-235, uranium-233, or plutonium each;
    (iii) Receipt of sealed sources, of any quantity, previously 
manufactured and shipped by the licensee and which are returned to the 
licensee, provided the unique identity and encapsulation integrity have 
not been compromised, and the booked receipt quantity equals the 
previously shipped quantity for the involved sealed sources; and
    (iv) Heterogeneous scrap that cannot be accurately measured in its 
as received form, provided this scrap is measured after dissolution 
within 18 months of receipt. The after dissolution measurement must 
include measurement of both the resulting solution and any undissolved 
residues, before any co-mingling with other scrap solutions or residues.
    (2) Maintain and follow a program for the development and use of 
written procedures that includes documented review and approval of these 
procedures, and any revisions thereof, before use, for:
    (i) Preparing or acquiring, maintaining, storing, and using 
reference standards;
    (ii) Calibrating measurement systems, performing bulk mass and 
volume measurements, conducting nondestructive assay measurements, 
obtaining samples, and performing laboratory analyses for element 
concentration and isotope abundance; and
    (iii) Recording, reviewing, and reporting measurements.
    (c) Measurement control. To maintain measurement quality and to 
estimate measurement uncertainty values, the licensee shall:
    (1) Assign responsibility for planning, developing, coordinating, 
and administering a measurement control program to an individual who has 
no direct responsibility for performing measurements or for SNM 
processing or handling, and who holds a position at an organizational 
level which permits independence of action and has adequate authority to 
obtain all the information required to monitor and evaluate measurement 
quality as required by this section.
    (2) Ensure that any contractor who performs MC&A measurements 
services conforms with applicable requirements in paragraphs (c)(5), 
(6), (7), (10) and (11) of this section. Conformance must include 
reporting by the contractor of sufficient measurement control data to 
allow the licensee to calculate bias corrections and measurement limits 
of error.
    (3) Ensure that potential sources of sampling error are identified 
and that samples are representative by performing process sampling tests 
using well characterized materials to establish or verify the 
applicability of utilized procedures for sampling SNM and

[[Page 605]]

for maintaining sample integrity during transport and storage. These 
sampling tests or sample integrity tests, as appropriate, shall be 
conducted whenever:
    (i) A new sampling procedure or technique is used, or new sampling 
equipment is installed;
    (ii) A sampling procedure, technique, or sampling equipment is 
modified to the extent that a systematic sampling error could be 
introduced; and
    (iii) Sample containers, sample transport methods, or sample storage 
conditions are changed or modified to the extent that a systematic 
sampling error could be introduced.
    (4) Establish and maintain a measurement control program so that for 
each inventory period the SEID is less than 0.125 percent of the active 
inventory, and assure that any MC&A measurements performed under 
contract are controlled so that the licensee can satisfy this 
requirement.
    (5) Generate current data on the performance of each measurement 
system used during each material balance period for the establishment of 
measured values and estimated measurement uncertainties, including 
estimates of bias, variance components for calibration, sampling, and 
repeat measurements. The program data must reflect the current process 
and measurement conditions existing at the time the control measurements 
are made.
    (6) Use standards on an ongoing basis for the calibration and 
control of all measurement systems used for SNM accountability. 
Calibrations shall be repeated whenever any significant change occurs in 
a measurement system or when program data indicate a need for 
recalibration. Calibrations and control standard measurements shall be 
based on standards whose assigned values are traceable to certified 
reference standards or certified standard reference materials. 
Additionally, control standards shall be representative of the process 
material or items being measured by the measurement system in question.
    (7) Conduct control measurements to provide current data for the 
determination of random error behavior. On a predetermined schedule, the 
program shall include, as appropriate:
    (i) Replicate analyses of individual samples;
    (ii) Analysis of replicate process samples;
    (iii) Replicate volume measurements of bulk process batches;
    (iv) Replicate weight measurements of process items and bulk 
batches, or alternatively, the use of data generated from the replicate 
weighings of control standard weights as derived from the control 
standard program; and
    (v) Replicate NDA measurements of individual process containers 
(items), or alternatively, the use of data generated from the replicate 
measurements of NDA control standards as derived from the control 
standard program.
    (8) Use all measurements and measurement controls generated during 
the current material balance period for the estimation of the SEID.
    (9) Evaluate with appropriate statistical methods all measurement 
system data generated in paragraph (c)(5) of this section to determine 
significant contributors to the measurement uncertainties associated 
with inventory differences and shipper-receiver differences, so that if 
SEID exceeds the limits established in paragraph (c)(4) of this section, 
the cause of the excessive SEID can be identified for corrective action 
with respect to controlling the standard error within applicable limits.
    (10) Establish and maintain a statistical control system, including 
control charts and formal statistical procedures, designed to monitor 
the quality of each measurement device or system. Control chart limits 
must be established to be equivalent to levels of significance of 0.05 
and 0.001.
    (11) Promptly investigate and take any appropriate corrective action 
whenever a control datum exceeds an 0.05 control limit, and whenever a 
control datum exceeds an 0.001 control limit, the measurement system 
that generated the datum shall immediately be placed out-of-service with 
respect to MC&A measurements until the deficiency has been corrected and 
the system brought into control within the 0.05 control limits.

[67 FR 78146, Dec. 23, 2002]

[[Page 606]]



   Subpart E_Formula Quantities of Strategic Special Nuclear Material

    Source: 52 FR 10040, Mar. 30, 1987, unless otherwise noted.



Sec. 74.51  Nuclear material control and accounting for strategic 
special nuclear material.

    (a) General performance objectives. Each licensee who is authorized 
to possess five or more formula kilograms of strategic special nuclear 
material (SSNM) and to use such material at any site, other than a 
nuclear reactor licensed pursuant to part 50 of this chapter, an 
irradiated fuel reprocessing plant, an operation involved with waste 
disposal, or an independent spent fuel storage facility licensed 
pursuant to part 72 of this chapter shall establish, implement, and 
maintain a Commission-approved material control and accounting (MC&A) 
system that will achieve the following objectives:
    (1) Prompt investigation of anomalies potentially indicative of SSNM 
losses;
    (2) Timely detection of the possible abrupt loss of five or more 
formula kilograms of SSNM from an individual unit process;
    (3) Rapid determination of whether an actual loss of five or more 
formula kilograms occurred;
    (4) Ongoing confirmation of the presence of SSNM in assigned 
locations; and
    (5) Timely generation of information to aid in the recovery of SSNM 
in the event of an actual loss.
    (b) System capabilities. To achieve the general performance 
objectives specified in Sec. 74.51(a), the MC&A system must provide the 
capabilities described in Sec. Sec. 74.53, 74.55, 74.57 and 74.59 and 
must incorporate checks and balances that are sufficient to detect 
falsification of data and reports that could conceal diversion by:
    (1) An individual, including an employee in any position; or
    (2) Collusion between an individual with MC&A responsibilities and 
another individual who has responsibility or control within both the 
physical protection and the MC&A systems.
    (c) Implementation dates. Each applicant for a license, and each 
licensee that, upon application for modification of a license, would 
become newly subject to paragraph (a) of this section, shall submit a 
fundamental nuclear material control (FNMC) plan describing how the MC&A 
system shall satisfy the requirement of paragraph (b) of this section. 
The FNMC plan shall be implemented when a license is issued or modified 
to authorize the activities being addressed in paragraph (a) of this 
section, or by the date specified in a license condition.
    (d) Inventories. Notwithstanding Sec. 74.59(f)(1), licensees shall 
perform at least three bimonthly physical inventories after 
implementation of the NRC approved FNMC Plan and shall continue to 
perform bimonthly inventories until performance acceptable to the NRC 
has been demonstrated and the Commission has issued formal approval to 
perform semiannual inventories. Licensees who have prior experience with 
process monitoring and/or can demonstrate acceptable performance against 
all Plan commitments may request authorization to perform semiannual 
inventories at an earlier date.

[52 FR 10040, Mar. 30, 1987, as amended at 63 FR 26963, May 15, 1998; 67 
FR 78148, Dec. 23, 2002]



Sec. 74.53  Process monitoring.

    (a) Licensees subject to Sec. 74.51 shall monitor internal 
transfers, storage, and processing of SSNM. The process monitoring must 
achieve the detection capabilities described in paragraph (b) of this 
section for all SSNM except:
    (1) SSNM that is subject to the item loss detection requirements of 
Sec. 74.55;
    (2) Scrap in the form of small pieces, cuttings, chips, solutions, 
or in other forms that result from a manufacturing process, held in 
containers of 30 gallons or larger, with an SSNM content of less than 
0.25 grams per liter;
    (3) SSNM with an estimated measurement standard deviation greater 
than five percent that is either input or output material associated 
with a unit that processes less than five formula kilograms over a 
consecutive three-month period; and
    (4) SSNM involved in research and development operations that 
process less than five formula kilograms during any seven-consecutive-
day period.

[[Page 607]]

    (b) Unit process detection capability. For each unit process, a 
licensee shall establish a production quality control program capable of 
monitoring the status of material in process. The program shall include:
    (1) A statistical test that has at least a 95 percent power of 
detecting an abrupt loss of five formula kilograms within three working 
days of a loss of Category IA material from any accessible process 
location and within seven calendar days of a loss of Category IB 
material from any accessible process location;
    (2) A quality control test whereby process differences greater than 
three times the estimated standard deviation of the process difference 
estimator and 25 grams of SSNM are investigated; and
    (3) A trend analysis for monitoring and evaluating sequences of 
material control test results from each unit process to determine if 
they indicate a pattern of losses or gains that are of safeguards 
significance.
    (c) For research and development operations exempt from the 
requirements of paragraph (b) of this section, the licensee shall:
    (1) Perform material balance tests on a lot or a batch basis, as 
appropriate, or monthly, whichever is sooner, and investigate any 
difference greater than 200 grams of plutonium or U-233 or 300 grams of 
U-235 that exceeds three times the estimated standard error of the 
inventory difference estimator;
    (2) Evaluate material balance results generated during an inventory 
period for indications of measurement biases or unidentified loss 
streams and investigate, determine the cause(s) of, and institute 
corrective action for cumulative inventory differences generated during 
an inventory period that exceed three formula kilograms of SSNM.



Sec. 74.55  Item monitoring.

    (a) Licensees subject to Sec. 74.51 shall provide the detection 
capability described in paragraph (b) of this section for laboratory 
samples containing less than 0.05 formula kilograms of SSNM and any 
uniquely identified items of SSNM that have been quantitatively 
measured, the validity of that measurement independently confirmed, and 
that additionally have been either:
    (1) Tamper-safed or placed in a vault or controlled access area that 
provides protection at least equivalent to tamper-safing; or
    (2) Sealed such that removal of SSNM would be readily and 
permanently apparent (e.g., encapsulated).
    (b) The licensee shall verify on a statistical sampling basis, the 
presence and integrity of SSNM items. The statistical sampling plan must 
have at least 99 percent power of detecting item losses that total five 
formula kilograms or more, plant-wide, within:
    (1) Thirty calendar days for Category IA items and 60 calendar days 
for Category IB items contained in a vault or in a permanently 
controlled access area isolated from the rest of the material access 
area (MAA);
    (2) Three working days for Category IA items and seven calendar days 
for Category IB items located elsewhere in the MAA, except for reactor 
components measuring at least one meter in length and weighing in excess 
of 30 kilograms for which the time interval shall be 30 days;
    (3) Sixty calendar days for items in a permanently controlled access 
area outside of an MAA; or
    (4) Sixty calendar days for samples in a vault or permanently 
controlled access area and 30 calendar days for samples elsewhere in the 
MAA for samples each containing less than 0.05 formula kilograms of 
SSNM.
    (c) Items containing scrap in the form of small pieces, cuttings, 
chips, solutions, or in other forms that result from a manufacturing 
process, held in containers of 30 gallon or larger, with an SSNM 
concentration of less than 0.25 grams per liter are exempt from the 
requirements of paragraph (b) of this section.

[52 FR 10040, Mar. 30, 1987, as amended at 80 FR 45844, Aug. 3, 2015]



Sec. 74.57  Alarm resolution.

    (a) Licensees subject to Sec. 74.51 shall provide the MC&A alarm 
resolution capabilities described in paragraphs (b) through (f) of this 
section.
    (b) Licensees shall resolve the nature and cause of any MC&A alarm 
within approved time periods.
    (c) Each licensee shall notify the NRC Operations Center by 
telephone of

[[Page 608]]

any MC&A alarm that remains unresolved beyond the time period specified 
for its resolution in the licensee's fundamental nuclear material 
control plan. Notification must occur within 24 hours except when a 
holiday or weekend intervenes in which case the notification must occur 
on the next scheduled workday. The licensee may consider an alarm to be 
resolved if:
    (1) Clerical or computational error is found that clearly was the 
cause for the alarm; or
    (2) An assignable cause for the alarm is identified or it is 
substantiated that no material loss has occurred.
    (d) If a material loss has occurred, the licensee shall determine 
the amount of SSNM lost and take corrective action to:
    (1) Return out-of-place SSNM, if possible, to its appropriate place;
    (2) Update and correct associated records; and
    (3) Modify the MC&A system, if appropriate, to prevent similar 
future occurrences.
    (e) The licensee shall provide an ability to rapidly assess the 
validity of alleged thefts.
    (f) If an abrupt loss detection estimate exceeds five formula 
kilograms of SSNM:
    (1) Material processing operations related to the alarm must be 
suspended until completion of planned alarm resolution activities, 
unless the suspension of operations will adversely affect the ability to 
resolve the alarm. Operation of continuous processes may continue for 24 
hours from the time of the occurrence of the alarm during which time 
checks shall be made for mistakes in records or calculations that could 
have caused the alarm.
    (2) Within 24 hours, the licensee shall notify the NRC Operations 
Center by telephone that an MC&A alarm resolution procedure has been 
initiated.

[52 FR 10040, Mar. 30, 1987, as amended at 54 FR 6877, Feb. 15, 1989; 55 
FR 5979, Feb. 21, 1990; 60 FR 24553, May 9, 1995; 67 FR 78148, Dec. 23, 
2002]



Sec. 74.59  Quality assurance and accounting requirements.

    (a) Licensees subject to Sec. 74.51 shall provide the quality 
assurance and accounting capabilities described in paragraphs (b) 
through (h) of this section.
    (b) Management structure. The licensee shall:
    (1) Establish and maintain a management structure that includes 
clear overall responsibility for planning, coordinating, and 
administering material control and accounting functions, independence of 
material control and accounting functions from production 
responsibilities, and separation of functions such that the activities 
of one individual or organizational unit serve as controls over and 
checks of the activities of others; and
    (2) Provide for the adequate review, approval, and use of those 
material control and accounting procedures that are identified in the 
approved FNMC plan as being critical to the effectiveness of the 
described system.
    (c) Personnel qualification and training. The licensee shall assure 
that personnel who work in key positions where mistakes could degrade 
the effectiveness of the material control and accounting system are 
trained to maintain a high level of safeguards awareness and are 
qualified to perform their duties and/or responsibilities.
    (d) Measurements. The licensee shall establish and maintain a system 
of measurements sufficient to:
    (1) Substantiate the plutonium element and uranium element and 
isotope content of all SSNM received, produced, transferred between 
areas of custodial responsibility, on inventory, or shipped, discarded, 
or otherwise removed from inventory;
    (2) Enable the estimation of the standard deviation associated with 
each measured quantity; and
    (3) Provide the data necessary for performance of the material 
control tests required by Sec. 74.53(b).
    (e) Measurement control. The licensee shall assure that the quality 
of SSNM measurement systems and material processing practices is 
continually controlled to a level of effectiveness sufficient to satisfy 
the capabilities required for detection, response, and accounting. To 
achieve this objective the licensee shall:
    (1) Perform engineering analyses and evaluations of the design, 
installation, preoperational tests, calibration, and

[[Page 609]]

operation of all measurement systems to be used for MC&A purposes;
    (2) Perform process and engineering tests using well characterized 
materials to establish or to verify the applicability of existing 
procedures for mixing and sampling SSNM and maintaining sample integrity 
during transport and storage. Tests must be repeated at least every 
three years, at any time there is a process modification that alters the 
physical or chemical composition of the SSNM, or whenever there is a 
change in the sampling technique or equipment; and
    (3) Generate current data on the performance of measurement 
processes, including, as appropriate, values for bias corrections, 
uncertainties on calibration factors, and random error standard 
deviations. The program must include:
    (i) The onging use of standards for calibration and control of all 
applicable measurement systems. Calibrations must be repeated whenever 
any change in a measurement system occurs which has the potential to 
affect a measurement result or when program data, generated by tests 
performed at a pre-determined frequency, indicate a need for 
recalibration. Calibrations and tests must be based on standards with 
traceability to national standards or nationally accepted measurement 
systems; and
    (ii) A system of control measurements to provide current data for 
the estimation of the standard deviations that are significant 
contributors to the measurement uncertainties associated with shipper/
receiver differences, inventory differences, and process differences.
    (4) Utilize the data generated during the current material balance 
period for the estimation of the standard error of the inventory 
difference (SEID) and the standard error of the process differences. 
Calibration and measurement error data collected and used during 
immediately preceding material balance periods may be combined with 
current data provided that the measurement systems are in statistical 
control and the combined data are utilized in characterizing the 
unknowns.
    (5) Evaluate all program data and information to assure that 
measurement performance is so controlled that the SEID estimator is less 
than 0.1 percent of active inventory.
    (6) Apply bias corrections by an appropriate procedure whereby:
    (i) Bias corrections are applied to individual items if for any 
measurement system the relative bias estimate exceeds twice the standard 
deviation of its estimator, the absolute bias estimate exceeds 50 grams 
of SSNM when applied across all affected items, and the absolute bias 
estimate on an individual item basis exceeds the rounding error of 
affected items; and
    (ii) All biases (regardless of significance) that are not applied as 
corrections to individual items are applied as a correction to the 
inventory difference.
    (7) Investigate and take corrective action, as appropriate, to 
identify and reduce associated measurement biases when, for like 
material types (i.e., measured by the same measurement system), the net 
cumulative shipper/receiver differences accumulated over a six-month 
period exceed the larger of one formula kilogram or 0.1 percent of the 
total amount received.
    (8) Establish and maintain a statistical control system designed to 
monitor the quality of each type of program measurement. Control limits 
must be established to be equivalent to levels of significance of 0.05 
and 0.001. Control data exceeding the 0.05 limits must be investigated 
and corrective action taken in a timely manner. Whenever a single data 
point exceeds the 0.001 control limit, the measurement system in 
question must not be used for material control and accounting purposes 
until it has been brought into control at the 0.05 level.
    (f) Physical inventory. The licensee shall:
    (1) Except as required by part 75 of this Chapter, perform a 
physical inventory at least every six calendar months and within 45 days 
after the start of the ending inventory:
    (i) Calculate the inventory difference (ID); estimate the standard 
error of the inventory difference (SEID); and investigate and report any 
SEID estimate of 0.1 percent or more of active inventory, and any ID 
that exceeds both three times SEID and 200 grams of plutonium

[[Page 610]]

or uranium-233, or 300 grams of uranium-235 contained in high enriched 
uranium.
    (ii) If required to perform an investigation pursuant to paragraph 
(f)(1)(i) of this section, evaluate the significance of the inventory 
difference relative to expected performance as determined from an 
analysis of an appropriate sequence of historical inventory differences;
    (iii) Investigate and report, by an appropriate method listed in 
Sec. 74.6, to the Director, Office of Nuclear Material Safety and 
Safeguards, any difference that exceeds three times the standard 
deviation determined from the sequential analysis;
    (iv) Perform a reinventory if directed to do so by the Commission; 
and
    (v) Reconcile and adjust the plant and subsidiary book records to 
the results of the physical inventory.
    (2) Implement policies, practices, and procedures designed to ensure 
the quality of physical inventories. These must include:
    (i) Development of procedures for tamper-safing of containers or 
vaults containing SSNM not in process that include adequate controls to 
assure the validity of assigned SSNM values;
    (ii) Maintenance of records of the quantities of SSNM added to and 
removed from process;
    (iii) Requirements for signed documentation of all SSNM transfers 
between areas with different custodial responsibility that reflect all 
quantities of SSNM transferred;
    (iv) Means for control of and accounting for internal transfer 
documents;
    (v) Cutoff procedures for transfers and processing so that all 
quantities of SSNM are inventoried and none are inventoried more than 
once;
    (vi) Cutoff procedures for records and reports so that all transfers 
for the inventory and material balance interval and no others are 
included in the records;
    (vii) Inventory procedures for sealed sources and containers or 
vaults containing SSNM that assure reliable identification and 
quantification of contained SSNM;
    (viii) Inventory procedures for in-process SSNM that provide for 
measurement of quantities not previously measured for element and 
isotope, as appropriate, and remeasurement of material previously 
measured but whose validity has not been assured by tamper-safing or 
equivalent protection; and
    (ix) Written instructions for conducting physical inventories that 
detail assignments, responsibilities, and preparation for and 
performance of an inventory.
    (g) Accounting. The licensee shall establish auditable records 
sufficient to demonstrate that the requirements of Sec. Sec. 74.53, 
74.55, 74.57, and 74.59 have been met and retain those records for at 
least three years unless a longer retention period is required by part 
75 of this Chapter.
    (h) Internal control. The licensee shall:
    (1) Establish procedures for shipping and receiving SSNM that 
provide for:
    (i) Accurate identification and measurement of the quantities 
shipped and received;
    (ii) Review and evaluation of shipper/receiver differences on an 
individual container or lot basis, as appropriate, on a shipment basis, 
and on a batch basis when required by part 75 of this Chapter;
    (iii) Investigation and corrective action when shipper/receiver 
differences exceed twice the estimated standard deviation of the 
difference estimator and the larger of 0.5 percent of the amount of SSNM 
in the container, lot, or shipment, as appropriate, or 50 grams of SSNM; 
and
    (iv) Documentation of shipper/receiver difference evaluations, 
investigations, and corrective actions.
    (2) Establish a scrap control program that assures that:
    (i) Internally generated scrap and scrap from other licensees or 
contractors is segregated until accountability is established; and
    (ii) Any scrap measured with a standard deviation greater than five 
percent of the measured amount is recovered so that the results are 
segregated by inventory period and recovered within six months of the 
end of the inventory period in which the scrap was generated except 
where it can be demonstrated that the scrap measurement

[[Page 611]]

uncertainty will not cause noncompliance with Sec. 74.59(e)(5).
    (3) Incorporate checks and balances in the MC&A system sufficient to 
control the rate of human errors in material control and accounting 
information.
    (4) Perform independent assessments at least every 12 months that 
assess the performance of the MC&A system, review its effectiveness, and 
document management's action on prior assessment recommendations. 
Assessments must include an evaluation of the measurement control 
program of any outside contractor laboratory performing MC&A 
measurements for a licensee, unless the contractor is also subject to 
the requirements of Sec. 74.59(e).
    (5) Assign custodial responsibility in a manner that ensures that 
such responsibility can be effectively executed for all SSNM possessed 
under license.

[52 FR 10040, Mar. 30, 1987, as amended at 54 FR 6878, Feb. 15, 1989; 55 
FR 5979, Feb. 21, 1990; 60 FR 24553, May 9, 1995; 67 FR 78148, Dec. 23, 
2002; 68 FR 58822, Oct. 10, 2003]



                          Subpart F_Enforcement



Sec. 74.81  Inspections.

    (a) Each licensee shall afford to the Commission at all reasonable 
times opportunity to inspect special nuclear material and the premises 
and facilities wherein special nuclear material is used, produced, or 
stored.
    (b) Each licensee shall make available to the Commission for 
inspection, upon reasonable notice, records kept by the licensee 
pertaining to its receipt, possession, use, acquisition, import, export, 
or transfer of special nuclear material.
    (c)(1) In the case of fuel cycle facilities where nuclear reactor 
fuel is fabricated or processed, each licensee shall upon request by the 
Director, Office of Nuclear Material Safety and Safeguards or the 
appropriate NRC Regional Administrator, provide rent-free office space 
for the exclusive use of Commission inspection personnel. Heat, air 
conditioning, light, electrical outlets, and janitorial services shall 
be furnished by each licensee. The office shall be convenient to and 
have full access to the facility, and shall provide the inspector both 
visual and acoustic privacy.
    (2) For a site with a single fuel facility licensed pursuant to part 
70 of this chapter, the space provided shall be adequate to accommodate 
a full-time inspector, a part-time secretary, and transient NRC 
personnel. It will be generally commensurate with other office 
facilities at the site. A space of 250 square feet either within the 
site's office complex or in an office trailer or other on-site space is 
suggested as a guide. For sites containing multiple fuel facilities, 
additional space may be requested to accommodate additional full-time 
inspector(s). The office space that is provided shall be subject to the 
approval of the Director, Office of Nuclear Material Safety and 
Safeguards or the appropriate NRC Regional Administrator. All furniture, 
supplies, and communication equipment will be furnished by the 
Commission.
    (3) The licensee shall afford any NRC resident inspector assigned to 
their site, or other NRC inspectors identified by the Director of the 
Office of Nuclear Material Safety and Safeguards as likely to inspect 
the facility, immediate unfettered access, equivalent to access provided 
regular plant employees, following proper identification and compliance 
with applicable access control measures for security, radiological 
protection, and personal safety.
    (d) At a facility using and possessing a formula quantity of 
strategic special nuclear material in unirradiated form, the licensee 
may not announce or otherwise communicate to its employees or site 
contractors the arrival or presence of an NRC safeguards inspector 
unless specifically requested to do so by the safeguards inspector.

[50 FR 7579, Feb. 25, 1985, as amended at 52 FR 31613, Aug. 21, 1987; 54 
FR 6878, Feb. 15, 1989; 55 FR 5979, Feb. 21, 1990; 58 FR 29522, May 21, 
1993]



Sec. 74.82  Tests.

    Each licensee shall perform, or permit the Commission to perform, 
any tests that the Commission deems appropriate or necessary for the 
administration of the regulations in this part, including tests of:
    (a) Special nuclear material;

[[Page 612]]

    (b) Facilities where special nuclear material is utilized, produced, 
or stored; and
    (c) Other equipment and devices used in connection with the 
production, utilization, or storage of special nuclear material.



Sec. 74.83  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55079, Nov. 24, 1992]



Sec. 74.84  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 74 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 74 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 74.1, 74.2, 74.4, 74.5, 74.6, 74.7, 74.8, 74.83 and 74.84.

[57 FR 55079, Nov. 24, 1992]



PART 75_SAFEGUARDS ON NUCLEAR MATERIAL_IMPLEMENTATION OF US/
IAEA AGREEMENT--Table of Contents



                           General Provisions

Sec.
75.1 Purpose.
75.2 Scope.
75.3 Exemptions.
75.4 Definitions.
75.5 Interpretations.
75.6 Facility and location reporting.
75.7 Notification of IAEA safeguards.
75.8 IAEA inspections
75.9 Information collection requirements: OMB approval.

                    Facility and Location Information

75.10 Facility information.
75.11 Location information.
75.12 Communication of information to IAEA.

             Material Accounting and Control for Facilities

75.15 Facility attachments.
75.21 General requirements.
75.22 Accounting records.
75.23 Operating records.
75.24 Retention of records.

                                 Reports

75.31 General requirements.
75.32 Initial inventory report.
75.33 Accounting reports.
75.34 Inventory change reports.
75.35 Material status reports.
75.36 Special reports.

                   Advanced Notification and Expenses

75.43 Circumstances requiring advance notification.
75.44 Timing of advance notification.
75.45 Content of advance notification.
75.46 Expenses.

                               Enforcement

75.51 Violations.
75.53 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 53, 63, 103, 104, 122, 
161, 223, 234, 1701 (42 U.S.C. 2073, 2093, 2133, 2134, 2152, 2201, 2273, 
2282, 2297f); Energy Reorganization Act of 1974, sec. 201 (42 U.S.C. 
5841); Nuclear Waste Policy Act of 1982, secs. 135, 141 (42 U.S.C. 
10155, 10161); 44 U.S.C. 3504 note.
    Section 75.4 also issued under Nuclear Waste Policy Act secs. 135 
(42 U.S.C. 10155, 10161).

[[Page 613]]


    Source: 45 FR 50711, July 31, 1980, unless otherwise noted.

                           General Provisions



Sec. 75.1  Purpose.

    The purpose of this part is to implement the requirements 
established by treaties between the United States and the International 
Atomic Energy Agency (IAEA). These treaties include the Agreement 
Between the United States of America and the International Atomic Energy 
Agency for the Application of Safeguards in the United States of America 
(Safeguards Agreement) and the Protocol Additional to the Agreement 
Between the United States of America and the International Atomic Energy 
Agency for the Application of Safeguards in the United States of America 
(Additional Protocol). This part contains requirements to ensure that 
the United States meets its nuclear non-proliferation obligations under 
these US/IAEA Safeguards treaties. These obligations include providing 
information to the IAEA on the place of applicant, licensee, or 
certificate holder activities; information on source and special nuclear 
materials; and access to the place of applicant, licensee, or 
certificate holder activities. These obligations are similar to the 
obligations accepted by other countries.

[73 FR 78607, Dec. 23, 2008]



Sec. 75.2  Scope.

    (a) All persons licensed by the Nuclear Regulatory Commission or an 
Agreement State, or who hold a certificate of compliance, or 
construction permit or authorization issued by the Nuclear Regulatory 
Commission are subject to the requirements of this part. These 
requirements also apply to all persons who have filed an application 
with the NRC to construct a facility or to receive source or special 
nuclear material. Locations determined by the U.S. Government to be 
associated with activities or information of direct national security 
significance to the United States are excluded from these requirements. 
Specifically, these requirements pertain to the following locations and 
activities of licensees and certificate holders:
    (1) A facility, as defined in Sec. 75.4, and the site of the 
facility;
    (2) A location performing nuclear fuel cycle-related research and 
development, as defined in Sec. 75.4;
    (3) A location manufacturing, assembling, or constructing nuclear 
fuel cycle-related equipment or materials as defined in Sec. 75.4;
    (4) A location of a uranium or thorium mine or concentration plant 
(e.g., in-situ leach mines and activities involving ore processing);
    (5) A location importing or possessing ``impure'' source material 
[i.e., source material not in the form of purified chemical products 
(e.g., UF6, U metal, UO2)];
    (6) A location possessing source or special nuclear material on 
which IAEA safeguards have been exempted or terminated;
    (7) A location receiving imports of material or equipment that is 
subject to export controls; and
    (8) The activity of exporting source materials for non-nuclear 
purposes or exporting of non-nuclear material or equipment that is 
subject to export controls.
    (b) Facilities referred to in Sec. 75.2(a)(1) are also subject to 
the reporting requirements of Sec. 75.6(b) and (c), IAEA inspections in 
Sec. 75.8, Facility information in Sec. 75.10, and the Material 
Accounting and Control requirements in Sec. Sec. 75.21 through 75.45.
    (c) Locations referred to in Sec. 75.2(a)(2) through 75.2(a)(7) are 
also subject to the reporting requirements of Sec. 75.6(b) and (d), and 
IAEA inspections in Sec. 75.8, and location information in Sec. 75.11.

[73 FR 78607, Dec. 23, 2008]



Sec. 75.3  Exemptions.

    (a) The Commission may, upon application of any interested person or 
upon its own initiative, grant exemptions from the requirements of this 
Part that it determines are authorized by law and consistent with the 
Safeguards Agreement or the Additional Protocol, are not inimical to the 
common defense and security, and are otherwise in the public interest.
    (b) Without limiting the generality of paragraph (a) of this 
section, the U.S. Government may request from the

[[Page 614]]

IAEA an exemption with respect to nuclear material of the following 
types:
    (1) Source and special nuclear material in gram quantities or less 
as a sensing component in instruments;
    (2) Nuclear material used in non-nuclear activities; and
    (3) Plutonium with an isotopic concentration of plutonium-238 
exceeding 80 percent.

[73 FR 78607, Dec. 23, 2008]



Sec. 75.4  Definitions.

    As used in this part:
    Unless otherwise defined in this section, the terms defined in 
Sec. Sec. 40.4, 50.2, and 70.4 of this chapter have the same meaning 
when used in this part.
    Additional Protocol means the Protocol Additional to the Agreement 
Between the United States of America and the International Atomic Energy 
Agency for the Application of Safeguards in the United States of 
America, concluded between the United States and the IAEA in Vienna, 
Austria, on June 12, 1998, that follows the provisions of INFCIRC/540.
    Agreement, except as used in the term Agreement State, means the 
Agreement between the United States and the International Atomic Energy 
Agency for the Application of Safeguards in the United States. Unless 
otherwise specified, the term refers both to the principal text of the 
Agreement, consisting of 90 articles, and to the Protocol thereto.
    Agreement State as designated in part 150 of this chapter means any 
State with which the Commission has entered into an effective agreement 
under subsection 274b. of the Act.
    Batch means a portion of nuclear material handled as a unit for 
accounting purposes at a key measurement point and for which the 
composition and quantity are defined by a single set of specifications 
or measurements. The nuclear material may be in bulk form or contained 
in a number of separate items.
    Complementary access means access provided to IAEA inspectors in 
accordance with the provisions of the Additional Protocol.
    Containment (with respect to IAEA safeguards) means containers, 
devices, or structures that are used to prevent undetected access to or 
movement of nuclear material.
    Effective kilogram means a unit used in safeguarding nuclear 
material. The quantity is:
    (1) For special nuclear material: The amount specified in Sec. 70.4 
of this chapter.
    (2) For source material: The amount specified in Sec. 40.4 of this 
chapter.
    Eligible Facilities List means the list of facilities that are 
eligible for IAEA safeguards inspections under the US/IAEA Safeguards 
Agreement, which the Secretary of State or his designee last submitted 
for Congressional review and which was not disapproved. A copy of this 
list is available for inspection at the NRC Web site, http://
www.nrc.gov, and/or at the NRC Public Document Room. In accordance with 
the provisions of the Safeguards Agreement, facilities of direct 
national security significance are excluded from the Eligible Facilities 
List.
    Environmental sampling (with respect to IAEA Safeguards) means the 
collection of environmental samples (e.g., air, water, vegetation, soil, 
or smears from surfaces) at a location specified by the IAEA for the 
purpose of assisting the IAEA to draw a conclusion about the absence of 
undeclared nuclear material or nuclear activities.
    Facility means:
    (1) A production facility or utilization facility as defined in 
Sec. 50.2 of this chapter;
    (2) A plant that converts nuclear material from one chemical form to 
another (e.g., Uranium hexafluoride plant);
    (3) A fuel fabrication plant;
    (4) An enrichment plant or isotope separation plant for the 
separation of isotopes of uranium or to increase the abundance of 
235U.
    (5) An installation designed to store nuclear material, such as an 
independent spent fuel storage installation (ISFSI) or a monitored 
retrievable storage installation (MRS) as defined in Sec. 72.3 of this 
chapter; or
    (6) Any plant or location where the possession of more than 1 
effective kilogram of nuclear material is licensed pursuant to Parts 40, 
50, 60, 61, 63, 70, 72, 76, or 150 of this chapter or an Agreement State 
license.

[[Page 615]]

    Facility attachment means a document negotiated between the U.S. and 
the IAEA that establishes safeguards commitments for a particular 
facility.
    IAEA means the International Atomic Energy Agency or its duly 
authorized representatives.
    IAEA material balance area means an area established for IAEA 
accounting purposes, such that:
    (1) The quantity of nuclear material in each transfer into or out of 
each material balance area can be determined; and
    (2) The physical inventory of nuclear material in each material 
balance area can be determined when necessary in accordance with 
specified procedures.
    Initial protocol means the protocol to the Agreement Between the 
United States of America and the International Atomic Energy Agency for 
the Application of Safeguards in the United States of America that was 
concluded with the IAEA and provides the IAEA the right to select a 
facility for material accounting reporting only without the right to 
conduct inspections.
    Inventory change means an increase or decrease in the quantity of 
source or special nuclear material in an IAEA material balance area.
    Key measurement point means a location where nuclear material 
appears in such a form that it may be measured to determine material 
flow or inventory. Key measurement points thus include, but are not 
limited to, the inputs and outputs (including measured discards) and 
storages in material balance areas.
    Location means any geographical point or area identified by the 
United States in its declarations, or by the IAEA resulting from a 
question, under the Additional Protocol.
    Managed access means procedures to protect sensitive or classified 
information or, to meet safety or physical protection requirements, 
while allowing the IAEA to accomplish the purpose of a complementary 
access request.
    Nuclear fuel cycle-related manufacturing and construction means 
those activities related to the manufacture or construction of any of 
the following: Components for separating the isotopes of uranium or 
enriching uranium in the isotope 235, zirconium tubes, heavy water or 
deuterium, nuclear-grade graphite, irradiated fuel casks and canisters, 
reactor control rods, criticality safe tanks and vessels, irradiated 
fuel element chopping machines, and hot cells.
    Nuclear fuel cycle-related research and development means those 
activities specifically related to any process or system development 
aspect of any of the following: Conversion of nuclear material; 
enrichment of nuclear material; nuclear fuel fabrication; reactors; 
critical facilities; reprocessing of nuclear fuel; and processing of 
intermediate or high-level waste containing plutonium, high-enriched 
uranium, or uranium-233.
    Nuclear material means any source material or any special nuclear 
material.
    Safeguards Agreement means the Agreement Between the United States 
and the IAEA for the Application of Safeguards in the United States, and 
all protocols and subsidiary arrangements to the agreement.
    Subsidiary Arrangement means a document, negotiated between the U.S. 
and the IAEA, that formally defines the technical and administrative 
procedures to implement the measures contained in the Safeguards 
Agreement.
    Surveillance (with respect to IAEA Safeguards) means instrumental or 
human observation aimed at detecting the movement of nuclear material.
    Transitional Facility Attachment means that portion of the 
``Transitional Subsidiary Arrangements to the Protocol to the Safeguards 
Agreement'' that pertains to a particular facility that has been 
identified under the Initial Protocol.

[45 FR 50711, July 13, 1980, as amended at 46 FR 58283, Dec. 1, 1981; 53 
FR 31683, Aug. 19, 1988; 57 FR 18393, Apr. 30, 1992; 57 FR 33432, July 
29, 1992; 63 FR 26963, May 15, 1998; 66 FR 55816, Nov. 2, 2001; 73 FR 
78608, Dec. 23, 2008]



Sec. 75.5  Interpretations.

    Except as authorized specifically by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.

[[Page 616]]



Sec. 75.6  Facility and location reporting.

    (a) Except where otherwise specified, all communications concerning 
the regulations in this Part shall be addressed to the U.S. Nuclear 
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 
20555-0001. Written communications may be delivered in person to the 
Nuclear Regulatory Commission at One White Flint North, 11555 Rockville 
Pike, Rockville, MD 20852-2738 between 7:30 a.m. and 4:15 p.m. eastern 
time. If a submittal deadline falls on a Saturday, Sunday, or a Federal 
holiday, the next Federal working day becomes the official due date.
    (b) Each applicant, licensee, or certificate holder who has been 
given notice by the Commission in writing that its facility or location 
is required to report under the Safeguards Agreement shall make its 
initial and subsequent reports, including attachments, in an appropriate 
format defined in the instructions.
    (c) Facilities--Specific information regarding facilities is to be 
reported as follows:

----------------------------------------------------------------------------------------------------------------
                     Item                           Section                    Manner of delivery
----------------------------------------------------------------------------------------------------------------
Initial Inventory Report......................           75.32  As specified by printed instructions for
                                                                 preparation of DOE/NRC Form-742.
Inventory Change Reports......................           75.34  As specified by printed instructions for
                                                                 preparation of DOE/NRC Form-741 and Form-740M.
Material Status Reports.......................           75.35  As specified by printed instructions for
                                                                 preparation of DOE/NRC Form-742, Form-742C, and
                                                                 Form-740M.
Special Reports...............................           75.36  To the NRC Headquarters Operations Center.
Facility information..........................        75.10(d)  As specified by printed instructions for Form N-
                                                                 71 and associated forms.
Site information..............................        75.10(e)  As specified by printed instructions for
                                                                 preparation of DOC/NRC Form AP-A and associated
                                                                 forms.
----------------------------------------------------------------------------------------------------------------

    (d) Locations--Specific information regarding locations is to be 
reported as follows:

------------------------------------------------------------------------
                Item                   Section      Manner of delivery
------------------------------------------------------------------------
Fuel cycle-related research and      75.11(b)(1)  As specified by
 development information.                          printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
Fuel cycle-related manufacturing     75.11(b)(2)  As specified by
 and construction information.                     printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
Mines and concentration plant        75.11(b)(3)  As specified by
 information.                                      printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
Impure source material possession    75.11(b)(4)  As specified by
 information.                                      printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
Imports and exports of source        75.11(b)(5)  As specified by
 material for non-nuclear end uses.                printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
IAEA safeguards-exempted and         75.11(b)(6)  As specified by
 terminated nuclear material                       printed instructions
 information.                                      for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
Imports and exports of non-nuclear   75.11(b)(7)  As specified by
 material and equipment.                           printed instructions
                                                   for preparation of
                                                   DOC/NRC Form AP-1 and
                                                   associated forms.
------------------------------------------------------------------------


[73 FR 78609, Dec. 23, 2008, as amended at 80 FR 45844, Aug. 3, 2015]



Sec. 75.7  Notification of IAEA safeguards.

    (a) The licensee must inform the NRC:
    (1) Before the licensee begins an activity that may be subject to 
the Safeguards Agreement; or
    (2) Within 30 days of beginning an activity subject to the 
Additional Protocol.
    (b) The Commission, by written notice, will inform the applicant, 
licensee, or certificate holder of those facilities subject to the 
application of IAEA safeguards.
    (c) Such notice is effective until the Commission informs the 
licensee or certificate holder, in writing, that its

[[Page 617]]

facility or location is no longer so designated. Whenever a previously 
designated facility or location is no longer subject to the application 
of IAEA safeguards, the Commission will give the licensee or certificate 
holder prompt notice to that effect.

[73 FR 78609, Dec. 23, 2008]



Sec. 75.8  IAEA inspections.

    (a) As provided in the Safeguards Agreement and Additional Protocol, 
inspections may be ad hoc, routine, special, or a complementary access 
(or a combination of the foregoing). The objectives of the IAEA 
inspectors in the performance of inspections are as follows:
    (1) Ad hoc inspections to verify information contained in the 
licensee's, applicant's, or certificate holder's facility information or 
initial inventory report, or to identify and verify changes in the 
situation which have occurred after the initial inventory reporting date 
at any location where the initial inventory report or any inspections 
carried out indicate that nuclear material subject to safeguards under 
the Safeguards Agreement may be present;
    (2) Ad hoc inspections to identify and, if possible, verify the 
quantity and composition of the nuclear material referred to in 
notifications specified under Sec. 75.43(b) (pertaining to exports) or 
Sec. 75.43(c) (pertaining to imports) at any place where nuclear 
material may be located;
    (3) Routine inspections are conducted as specified by the facility 
attachments referred to in Sec. 75.15 to verify nuclear material and 
as-built facility design at the strategic points and the records 
maintained under this part;
    (4) Special inspections may be conducted at any of the places 
specified above and any additional places where the Commission (in 
coordination with other Federal agencies), in response to an IAEA 
request, finds access to be necessary;
    (5) Complementary access may be conducted at a location, using 
measures permitted under the Additional Protocol and as specified by 
managed access procedures, for the IAEA inspectors to verify the 
completeness and accuracy of the information provided on DOC/NRC Form 
AP-1 or AP-A and associated forms; and
    (6) Complementary access must be provided at any additional 
locations where the Commission (in coordination with other Federal 
agencies), in response to an IAEA request, finds access to be necessary.
    (b) The NRC will notify the applicant, licensee, or certificate 
holder of each such inspection or complementary access in writing as 
soon as possible after receiving the IAEA's notice from the U.S. 
Department of State. The applicant, licensee, or certificate holder 
should consult with the Commission immediately if the inspection or 
complementary access would unduly interfere with its activities or if 
its key personnel cannot be available.
    (c) Each applicant, licensee, or certificate holder subject to the 
provisions of this part shall recognize as a duly authorized 
representative of the IAEA any person bearing IAEA credentials for whom 
the NRC has provided written or electronic authorization that the IAEA 
representative is permitted to conduct inspection activities on 
specified dates. If the IAEA representative's credentials have not been 
confirmed by the NRC, the applicant, licensee, or certificate holder 
shall not admit the person until the NRC has confirmed the person's 
credentials. The applicant, licensee, or certificate holder shall notify 
the Commission promptly, by telephone, whenever an IAEA representative 
arrives at a facility or location without advance notification. The 
applicant, licensee, or certificate holder shall also contact the 
Commission, by telephone, within one hour with respect to the 
credentials of any person who claims to be an IAEA representative and 
shall accept written or electronic confirmation of the credentials from 
the NRC. Confirmation may be requested through the NRC Operations Center 
(commercial telephone number 301-816-5100).
    (d) Each applicant, licensee, or certificate holder subject to the 
provisions of this part shall allow the IAEA opportunity to conduct an 
NRC-approved inspection or complementary access of the facility or 
location to verify the information submitted under Sec. Sec. 75.10, 
75.11, and 75.31 through 75.43. The NRC

[[Page 618]]

will assign an employee to accompany IAEA representative(s) at all times 
during the inspection or complementary access. The applicant, licensee, 
or certificate holder may accompany IAEA representatives who inspect or 
access the facility or location. The IAEA representatives should not be 
delayed or otherwise impeded in the exercise of their duties.
    (e) Each applicant, licensee, or certificate holder shall permit the 
IAEA, in conducting an ad hoc, routine, or special inspection at a 
facility, to:
    (1) Examine records kept under Sec. 75.21;
    (2) Observe that the measurements of nuclear material at key 
measurement points for material balance accounting are representative;
    (3) Verify the function and calibration of instruments and other 
measurement control equipment;
    (4) Observe that samples at key measurement points for material 
balance accounting are taken in accordance with procedures that produce 
representative samples, observe the treatment and analysis of the 
samples, and obtain duplicates of these samples;
    (5) Arrange to use the IAEA's own equipment for independent 
measurement and surveillance; and
    (6) Perform other measures requested by the IAEA and approved by the 
NRC.
    (f) Each applicant, licensee, or certificate holder shall, at the 
request of an IAEA inspector during an ad hoc, routine, or special 
inspection at a facility:
    (1) Ship material accountancy samples taken for the IAEA's use, in 
accordance with applicable packaging and export licensing regulations, 
by the method of carriage and to the address specified by the inspector; 
and
    (2) Take other actions contemplated by the Safeguards Agreement, and 
included in the safeguards approach approved by the United States and 
the IAEA, including but not limited to the following examples:
    (i) Enabling the IAEA to arrange to install its equipment for 
measurement and surveillance;
    (ii) Enabling the IAEA to apply its seals and other identifying and 
tamper-indicating devices to containers;
    (iii) Making additional measurements and taking additional samples 
for the IAEA's use;
    (iv) Analyzing the IAEA's standard analytical samples;
    (v) Using appropriate standards in calibrating instruments and other 
equipment; and
    (vi) Carrying out other calibrations.
    (g) Each applicant, licensee, or certificate holder shall permit the 
IAEA, in conducting complementary access at a location, under the 
provisions of the Additional Protocol and subsidiary arrangements, to:
    (1) Perform visual observations and record observations as 
photographs;
    (2) Conduct environmental sampling, when authorized by the U.S. 
Government;
    (3) Use radiation detection and measurement devices;
    (4) Apply seals and other identifying and tamper-indicating devices;
    (5) Perform nondestructive measurements and sampling;
    (6) Examine records relevant to quantities, origin, and disposition 
of materials to confirm the accuracy of the information provided under 
Sec. 75.11;
    (7) Examine safeguards-relevant production and shipping records; and
    (8) Other objective measures that have been demonstrated to be 
technically feasible and the use of which has been agreed upon by the 
IAEA Board of Governors and following consultations between the IAEA and 
U.S. Government.
    (h) Nothing in this section requires or authorizes an applicant, 
licensee, or certificate holder to carry out any operation that would 
otherwise constitute a violation of the terms of any applicable license, 
regulation, or order of the Commission.

[73 FR 78609, Dec. 23, 2008]



Sec. 75.9  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission, or another U.S. Government 
agency, has submitted the information collection requirements contained 
in this Part to the Office of Management and Budget (OMB) for approval 
as required by the Paperwork Reduction Act (44 U.S.C. 3501 et seq.). The 
NRC

[[Page 619]]

may not conduct or sponsor, and a person is not required to respond to, 
a collection of information unless it displays a currently valid OMB 
control number. OMB has approved the information collection requirements 
contained in this Part under control number 3150-0055.
    (b) The approved information collection requirements contained in 
this Part appear in Sec. Sec. 75.6, 75.7a, 75.10, 75.11, 75.21, 75.22, 
75.23, 75.24, 75.31, 75.32, 75.33, 75.34, 75.35, 75.36, 75.43, 75.44, 
and 75.45.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. These information collection requirements 
and the control numbers under which they are approved are as follows:
    (1) In Sec. 75.10, Form N-71 and associated forms are approved 
under control number 3150-0056.
    (2) In Sec. Sec. 75.31, 75.32, 75.33, and 75.35, DOE/NRC Form 742 
is approved under control number 3150-0004.
    (3) In Sec. Sec. 75.33 and 75.34, DOE/NRC Form 741 is approved 
under control number 3150-0003.
    (4) In Sec. Sec. 75.34 and 75.35, DOE/NRC Form 740M is approved 
under OMB control number 3150-0057.
    (5) In Sec. 75.35, DOE/NRC Form 742C is approved under control 
number 3150-0058.
    (6) In Sec. Sec. 75.10 and 75.11, DOC/NRC Forms AP-1, AP-A, and 
associated forms are approved under control number 0694-0135.

[49 FR 19628, May 9, 1984, as amended at 62 FR 52189, Oct. 6, 1997; 67 
FR 67101, Nov. 4, 2002; 73 FR 78610, Dec. 23, 2008]

                    Facility and Location Information



Sec. 75.10  Facility information.

    (a) Each applicant, licensee, or certificate holder subject to the 
provisions of this Part shall submit facility information, in response 
to written notification from the Commission, with respect to any 
facility that the Commission indicates has been identified under the 
Safeguards Agreement, the Initial Protocol to the Agreement, or meets 
the Additional Protocol reporting criteria, and in which the applicant, 
licensee, or certificate holder carries out licensed activities. (The 
Commission request must state whether the facility has been identified 
under Article 39(b) of the principal text of the Safeguards Agreement or 
Article 2(a) of the Initial protocol.) The applicant, licensee, or 
certificate holder shall submit the requested information to the 
Commission within the period specified in the Commission's request.
    (b) Facility information includes:
    (1) The identification of the facility, stating its general 
character, purpose, nominal capacity (thermal power level, in the case 
of power reactors), and geographic location, and the name and address to 
be used for routine purposes;
    (2) A description of the general arrangement of the facility with 
reference, to the extent feasible, to the form, location and flow of 
nuclear material, and to the general layout of important items of 
equipment which use, produce, or process nuclear material;
    (3) A description of features of the facility relating to material 
accounting, containment, and surveillance;
    (4) A description of the existing and proposed procedures at the 
facility for nuclear material accounting and control, with special 
reference to material balance areas established by the licensee, 
measurement of flow, and procedures for physical inventory taking (As 
part of this description, the applicant, licensee, or certificate holder 
may identify a process step involving information that it deems to be 
commercially sensitive and for which it proposes that a special material 
balance area be established so as to restrict IAEA access to this 
information); and
    (5) A map of the site and information on the size of the buildings 
and on the general nature of the activities conducted in each building.
    (c) Each licensee or certificate holder shall thereafter submit to 
the Commission information with respect to any modification at the 
facility affecting the information referred to in paragraph (a) of this 
section. The following information must be submitted:
    (1) Regarding a modification of a type described in the license or 
certificate conditions: At least 180 days before the modification is 
scheduled to be started, except that in an emergency or

[[Page 620]]

other unforeseen situation a shorter period may be approved by the 
Commission.
    (2) Regarding any other modification relevant to the application of 
the provisions of the Safeguards Agreement: At the time the first 
inventory change report is submitted after the modification is 
completed.
    (d) The information specified in paragraphs (b) and (c) of this 
section, except for the information specified in paragraph (b)(5) of 
this section, must be prepared on IAEA approved Design Information 
Questionnaire forms (Form N-71 and associated forms or other forms 
supplied by the Commission). The information must be sufficiently 
detailed to enable knowledgeable determinations to be made in the 
development of Facility Attachments or amendments thereto, including:
    (1) Identification of the features of facilities and nuclear 
material relevant to the application of safeguards to nuclear material 
in sufficient detail to facilitate verification;
    (2) Determination of IAEA material balance areas to be used for IAEA 
accounting purposes and selection of those strategic points which are 
key measurement points and which will be used to determine flow and 
inventory of nuclear material;
    (3) Establishment of the nominal timing and procedures for taking of 
physical inventories of nuclear material for IAEA accounting purposes;
    (4) Establishment of the records and reports requirements and 
records evaluation procedures;
    (5) Establishment of requirements and procedures for verification of 
the quantity and location of nuclear material;
    (6) Selection of appropriate combinations of containment and 
surveillance methods and techniques at the strategic points at which 
they are to be applied; and
    (7) Information on organizational responsibility for material 
accounting and control.
    (e) Information specified in paragraph (b)(5) of this section must 
be submitted as specified by instructions for DOC/NRC Form AP-A and 
associated forms and shall contain a site map drawn to scale as an 
attachment.
    (f) The applicant's, licensee's, or certificate holder's security 
rules for physical protection that will impact the IAEA inspectors at 
the facility must be included in the facility information only when and 
to the extent specifically requested by the Commission.
    (g) Health and safety rules that are to be observed by the IAEA 
inspectors at the facility must be included in the facility information.
    (h) Information must be provided on the need to manage IAEA access 
to the facility to protect health and safety or to protect classified, 
proprietary, or other sensitive information, and on other protective 
measures that should be implemented should an IAEA access be requested.

[73 FR 78611, Dec. 23, 2008]



Sec. 75.11  Location information.

    (a) As required by the Additional Protocol, each applicant, 
licensee, or certificate holder shall submit location information to the 
Commission as specified in the instructions for DOC/NRC Form AP-1 and 
associated forms.
    (b) Location information includes:
    (1) Nuclear fuel cycle-related research and development information 
including a general description of the activity and information 
specifying the location of the activity.
    (2) Nuclear fuel cycle-related manufacturing or construction 
information including a description of the scale of operations for the 
activity.
    (3) Uranium and thorium mine and concentration plant information 
including information on the location, operational status, and the 
estimated annual production capacity and current annual production of 
the activity.
    (4) Impure source material possession information including the 
quantities, the chemical composition, and the use or intended use of the 
material (e.g., nuclear or non-nuclear use).
    (5) Imports and exports of source material for non-nuclear end uses 
including the location, quantities, chemical compositions, and use of 
the imported or exported material.
    (6) IAEA-exempted and -terminated nuclear material information 
including information regarding the quantities,

[[Page 621]]

uses, and location of the nuclear material.
    (7) Imports and exports of non-nuclear material and equipment 
including the location, quantity and description of the materials and 
equipment.
    (c) Information specified in paragraphs (b)(1) through (b)(7) of 
this section must be supplied as specified in the instructions for DOC/
NRC Form AP-1 and associated forms. The Information provided on DOC/NRC 
Form AP-1 and associated forms must be submitted annually. If the 
information has not changed, a ``No change'' report must be provided. 
NRC should also be notified when the activity is no longer performed. 
The annual report must be submitted by January 31 of each succeeding 
year after the initial report. The initial report must be submitted no 
later than 30 calendar days following the date of publication of this 
rule.
    (d) Information must be provided on the need to manage IAEA access 
to the location to protect health and safety or to protect classified, 
proprietary, or other sensitive information, and on other protective 
measures that should be implemented should an IAEA access be requested.

[73 FR 78611, Dec. 23, 2008]



Sec. 75.12  Communication of information to IAEA.

    (a) Except as otherwise provided in this section, the Commission 
will furnish to the IAEA all information submitted under Sec. Sec. 
75.10, 75.11, and 75.31 through 75.43.
    (b)(1) An applicant, licensee, or certificate holder may request 
that information of particular sensitivity, that it customarily holds in 
confidence, not be transmitted physically to the IAEA. An applicant, 
licensee, or certificate holder who makes this request shall, at the 
time the information is submitted, identify the pertinent document or 
part thereof and make a full statement of the reasons supporting the 
request. The applicant, licensee, or certificate holder shall retain a 
copy of the request and all documents related to the request as a record 
until the Commission terminates the license or certificate for each 
facility or location involved with the request, or until the Commission 
notifies the applicant, licensee, or certificate holder that the 
applicant, licensee, or certificate holder is no longer under the 
Safeguards Agreement. Superseded material must be retained for 3 years 
after each change is made.
    (2) In considering such a request, it is the policy of the 
Commission to achieve an effective balance between legitimate concerns 
of licensees, applicants, or certificate holders, including protection 
of the competitive position of the owner of the information, and the 
undertaking of the United States to cooperate with the IAEA to 
facilitate the implementation of the safeguards provided for in the 
Safeguards Agreement and Additional Protocol. The Commission will take 
into account the obligation of the IAEA to take every precaution to 
protect commercial and industrial secrets and other confidential 
information coming to its knowledge in the implementation of the 
Safeguards Agreement and Additional Protocol.
    (3) A request made under Sec. 2.390 of this chapter will not be 
treated as a request under this section unless the application makes 
specific reference to this section, nor shall a determination to 
withhold information from public disclosure necessarily require a 
determination that such information not be transmitted physically to the 
IAEA.
    (4) If a request is granted, the Commission will determine a 
location where the information will remain readily available for 
examination by the IAEA and will so inform the applicant, licensee, or 
certificate holder. The applicant, licensee, or certificate holder shall 
retain this information as a record until the Commission terminates the 
license or certificate for the facility involved with the request or 
until the Commission notifies the applicant, licensee, or certificate 
holder that the applicant, licensee, or certificate holder is no longer 
under the Safeguards Agreement. Superseded material must be retained for 
3 years after each change is made.
    (c) A request made under Sec. 2.390(b) of this chapter will not be 
treated as a request under this section unless the application makes 
specific reference to this section, nor shall a determination

[[Page 622]]

to withhold information from public disclosure necessarily require a 
determination that this information not be transmitted physically to the 
IAEA.
    (d) Where consistent with the Safeguards Agreement, the Commission 
may at its own initiative, or at the request of a licensee, determine 
that any information submitted under Sec. Sec. 75.10, and 75.11 shall 
not be physically transmitted to, or made available for examination by, 
the IAEA.

[45 FR 50711, July 31, 1980, as amended at 53 FR 19262, May 27, 1988; 69 
FR 2281, Jan. 14, 2004; 73 FR 78612, Dec. 23, 2008]

             Material Accounting and Control for Facilities



Sec. 75.15  Facility attachments.

    (a) The Facility Attachment or Transitional Facility Attachment will 
document the determinations referred to in Sec. 75.10 and will contain 
other appropriate provisions.
    (b) The Commission will issue license or certificate amendments, as 
necessary, to implement the Safeguards Agreement and the Facility 
Attachment (as amended from time to time). The license or certificate 
amendments through reference to the Facility Attachment or Transitional 
Facility Attachment, or otherwise, will specify:
    (1) IAEA material balance areas;
    (2) Types of modifications for which information is required, under 
Sec. 75.10, to be submitted in advance;
    (3) Procedures, as referred to in Sec. 75.21;
    (4) The extent to which isotopic composition must be included in 
batch data (under Sec. 75.22) and advance notification (Sec. 75.45);
    (5) Items to be reported in the concise notes accompanying inventory 
change reports, as referred to in Sec. 75.34;
    (6) Loss limits and changes in containment, as referred to in Sec. 
75.36 (pertaining to special reports);
    (7) Actions required to be taken under Sec. 75.8(f) at the request 
of an IAEA inspector;
    (8) Procedures to be used for documentation of requests under Sec. 
75.46 (pertaining to expenses); and
    (9) Other appropriate matters.
    (c) The Commission will also issue license or certificate 
amendments, as necessary, for implementing the Initial Protocol to the 
Safeguards Agreement and the Transitional Facility Attachment (as 
amended from time to time).
    (d) License or certificate amendments will be made under the 
Commission's rules of practice (part 2 of this chapter). Specifically, 
if the licensee or certificate holder does not agree to an amendment, an 
order modifying the license would be issued under Sec. 2.204 of this 
chapter.
    (e) Subject to constraints imposed by the Safeguards Agreement, the 
Commission will afford the applicant, licensee, or certificate holder a 
reasonable opportunity to participate in the development of the Facility 
Attachment or Transitional Facility Attachment applicable to the 
facility, and any amendments thereto, and to review and comment upon any 
instrument before it has been agreed to by the United States. The 
Commission will provide to the applicant, licensee, or certificate 
holder a copy of any such instrument that has been completed under the 
Safeguards Agreement.
    (f) Locations reporting under the Additional Protocol, unless 
located in a facility selected under Article 39(b) of the main text of 
the Safeguards Agreement, do not have Facility Attachments or 
Transitional Facility Attachments.

[73 FR 78612, Dec. 23, 2008]



Sec. 75.21  General requirements.

    (a) Each licensee or certificate holder who has been given notice by 
the Commission in writing that its facility has been identified under 
the Safeguards Agreement shall establish, maintain, and follow written 
material accounting and control procedures. The licensee or certificate 
holder shall retain as a record current material accounting and control 
procedures until the Commission terminates the license or certificate 
for the facility involved with the request or until the Commission 
notifies the licensee or certificate holder that the licensee or 
certificate holder is no longer under the Safeguards Agreement. 
Superseded material must be retained for 3 years after each change is 
made.
    (b) The material accounting and control procedures required by 
paragraph

[[Page 623]]

(a) of this section shall include, as appropriate:
    (1) A measurement system for the determination of the quantities of 
nuclear material received, produced, shipped, lost or otherwise removed 
from inventory, and the quantities on inventory;
    (2) The evaluation of precision and accuracy of measurements and the 
estimation of measurement uncertainty;
    (3) Procedures for identifying, reviewing and evaluating differences 
in shipper/receiver measurements;
    (4) Procedures, including frequency, for taking a physical 
inventory;
    (5) Procedures for the evaluation of accumulations of unmeasured 
inventory and unmeasured losses; and
    (6) A system of accounting and operating records.
    (c)(1) The procedures must, unless otherwise specified in license or 
certificate conditions, conform to the facility information submitted by 
the licensee under Sec. 75.10.
    (2) Until facility information has been submitted by the applicant, 
licensee, or certificate holder, the procedures must be sufficient to 
document changes in the quantity of nuclear material in or at its 
facility. Observance of the procedures described in Sec. Sec. 40.61 or 
74.15 of this chapter (or the corresponding provisions of the 
regulations of an Agreement State) by any applicant, licensee, or 
certificate holder subject thereto constitutes compliance with this 
paragraph.
    (d) The requirements of this section are in addition to any other 
requirements of this chapter, relating to material accounting and 
control, that may apply to the licensee.

[45 FR 50711, July 31, 1980, as amended at 53 FR 19263, May 27, 1988; 67 
FR 78149, Dec. 23, 2002; 73 FR 78613, Dec. 23, 2008]



Sec. 75.22  Accounting records.

    (a) The accounting records required by Sec. 75.21 shall include, 
for each IAEA material balance area:
    (1) All inventory changes, so as to permit a determination of the 
book inventory at any time;
    (2) All measurement results that are used for determination of 
nuclear material quantities; and
    (3) All adjustments and corrections that have been made with respect 
to inventory changes, book inventories and physical inventories.
    (b) The records shall show, for each batch of nuclear material: 
material identification, batch data and source data. The batch data 
means a separate listing of the total weight of each element of nuclear 
material (including, as specified in the license conditions, isotopic 
composition for special nuclear material) with plutonium and enriched 
uranium measured in grams and natural or depleted uranium and thorium 
measured in kilograms. The source data are the data, recorded during 
measurement or calibration or used to derive empirical relationships, 
which identify nuclear material and provide batch data.
    (c) For each inventory change, the records shall show the date of 
the inventory change and, when appropriate, (1) the originating IAEA 
material balance area or the shipper, and (2) the receiving IAEA 
material balance area or the recipient.



Sec. 75.23  Operating records.

    The operating records required by Sec. 75.21 shall include, as 
appropriate, for each IAEA material balance area:
    (a) Those operating data which are used to establish changes in the 
quantities and composition of nuclear material;
    (b) The data obtained from the calibration of tanks and instruments 
and from sampling and analyses, the procedures employed to control the 
quality of measurements, and the derived estimates of random and 
systematic error;
    (c) A description of the sequence of the actions taken in preparing 
for, and in taking, a physical inventory, to ensure that it is correct 
and complete; and
    (d) A description of the actions taken to ascertain the magnitude 
and cause of any accidental or unmeasured loss that might occur.



Sec. 75.24  Retention of records.

    The records referred to in Sec. Sec. 75.22 and 75.23 shall be 
retained by the licensee for at least five years.

[[Page 624]]

                                 Reports



Sec. 75.31  General requirements.

    Each licensee or certificate holder who has been given notice by the 
Commission in writing that its facility has been identified under the 
Safeguards Agreement shall make, in an appropriate computer-readable 
format, an initial inventory report, and thereafter shall make 
accounting reports, with respect to the facility and, in addition, 
licensees or certificate holders who have been given notice, under Sec. 
75.7 that their facilities are subject to the application of IAEA 
safeguards, shall make the special reports described in Sec. 75.36. 
These reports must be based on the records kept under Sec. 75.21. At 
the request of the Commission, the licensee or certificate holder shall 
amplify or clarify any report with respect to any matter relevant to 
implementation of the Safeguards Agreement. Any amplification or 
clarification must be in writing and must be submitted, to the address 
specified in the request, within 20 days or other time as may be 
specified by the Commission.

[73 FR 78613, Dec. 23, 2008]



Sec. 75.32  Initial inventory report.

    (a) The initial inventory reporting date shall be the last day of 
the calendar month in which the Commission gives the licensee notice 
that an initial inventory report is required.
    (b) The initial inventory report, to be submitted to the Commission 
as specified by the instructions (NUREG/BR-0007 and NMMSS Report D-24 
``Personal Computer Data Input for NRC Licensees''), must show the 
quantities of nuclear material contained in or at a facility as of the 
initial inventory reporting date. The information in the initial 
inventory report may be based upon the licensee's or certificate 
holder's book record.
    (c) The initial inventory report shall be dispatched within twenty 
(20) days after the initial inventory reporting date.

[45 FR 50711, July 31, 1980, as amended at 59 FR 35622, July 13, 1994; 
73 FR 78613, Dec. 23, 2008]



Sec. 75.33  Accounting reports.

    (a)(1) The accounting reports for each IAEA material balance area 
must consist of:
    (i) Nuclear Material Transaction Reports (Inventory Change Reports); 
and
    (ii) Material status reports showing the material balance based on a 
physical inventory of nuclear material actually present.
    (2) These prescribed computer-readable forms replace the following 
forms which have been submitted in paper form:
    (i) The DOE/NRC Form 741; and
    (ii) The DOE/NRC Form 742.
    (b) The reports shall be based on data available as of the date of 
reporting and may be corrected at a later date, as required.

[45 FR 50711, July 31, 1980, as amended at 49 FR 19629, May 9, 1984; 59 
FR 35622, July 13, 1994; 73 FR 78613, Dec. 23, 2008]



Sec. 75.34  Inventory change reports.

    (a) Nuclear Material Transaction Reports (Inventory Change Reports) 
in computer-readable format to be completed in accordance with 
instructions (NUREG/BR-0006 and NMMSS Report D-24 ``Personal Computer 
Data Input for NRC Licensees''), must specify identification and batch 
data for each batch of nuclear material, the date of the inventory 
change, and, as appropriate,
    (1) The originating IAEA material balance area or the shipper; and
    (2) The receiving IAEA material balance area or the recipient.

Each licensee who receives special nuclear material from a foreign 
source shall complete both the supplier's and receiver's portion of the 
form.
    (b) Nuclear Material Transactions Reports (Inventory Change 
Reports), when appropriate, must be accompanied by Concise Notes, 
completed as specified in the instructions (NUREG/BR-0006 and NMMSS 
Report D-24 ``Personal Computer Data Input for NRC Licensees''). Copies 
of these instructions may be obtained from the U.S. Nuclear Regulatory 
Commission, Division of Fuel Cycle Safety, Safeguards, and Environmental 
Review, Washington, DC 20555-0001. This Concise Note is used in:

[[Page 625]]

    (1) Explaining the inventory changes on the basis of the operating 
records provided for under Sec. 75.23; and
    (2) Describing, to the extent specified in the license conditions, 
the anticipated operational program for the facility, including 
particularly, but not exclusively, the schedule for taking physical 
inventory.

[59 FR 35622, July 13, 1994, as amended at 73 FR 78613, Dec. 23, 2008; 
79 FR 75741, Dec. 19, 2014]



Sec. 75.35  Material status reports.

    (a) A material status report must be submitted for each physical 
inventory which is taken as part of the material accounting and control 
procedures required by Sec. 75.21. The material status report must 
include a material balance report and a physical inventory report which 
lists all batches separately and specifies material identification and 
batch data for each batch. When appropriate, the material status report 
must be accompanied by a Concise Note. The reports described in this 
section must be prepared and submitted in accordance with instructions 
(NUREG/BR-0006, NUREG/BR-0007, and NMMSS Report D-24 ``Personal Computer 
Data Input for NRC Licensees''). Copies of these instructions may be 
obtained from the U.S. Nuclear Regulatory Commission, Division of Fuel 
Cycle Safety, Safeguards, and Environmental Review, Washington, DC 
20555-0001.
    (b) Unless otherwise specified in the license conditions, material 
status reports shall be dispatched as soon as possible and in any event 
within thirty (30) days after the start of the physical inventory.

[45 FR 50711, July 31, 1980, as amended at 59 FR 35622, July 13, 1994; 
73 FR 78613, Dec. 23, 2008; 79 FR 75741, Dec. 19, 2014]



Sec. 75.36  Special reports.

    (a) This section applies only to licenses or certificate holders who 
have been given notice under Sec. 75.7(b) that their facilities are 
subject to the application of IAEA safeguards.
    (b) Each licensee who is subject to this section shall immediately 
make a special report to the Commission, by telephone (and also by 
telegraph, mailgram, or facsimile), in those situations described in 
license conditions.
    (c) The situations referred to in paragraph (b) of this section 
include (1) the possibility of loss of nuclear material in excess of 
specified limits and (2) unexpected changes in containment to the extent 
that unauthorized removal of nuclear material has become possible.

[45 FR 50711, July 31, 1980, as amended at 73 FR 78613, Dec. 23, 2008]

                   Advanced Notification and Expenses



Sec. 75.43  Circumstances requiring advance notification.

    (a) Each applicant, licensee, or certificate holder who has been 
given notice under Sec. 75.7 shall give advance written notification to 
the Commission regarding the international and domestic transfers 
specified in this section.
    (b) Exports. Notification shall be given of any proposed shipment of 
nuclear material for peaceful purposes under an export license issued 
pursuant to part 110 of this chapter, in an amount exceeding one 
effective kilogram, directly or indirectly to any non-nuclear-weapon 
state (as referred to in Article III(2) of the Treaty on the Non-
Proliferation of Nuclear Weapons, 21 U.S.T. 483). If the licensee 
anticipates that it will make two or more shipments for peaceful 
purposes, within any period of 90 days, directly or indirectly to 
destinations in the same non-nuclear-weapon state, notification shall be 
given of each shipment if the aggregate quantity of nuclear material to 
be transferred exceeds one effective kilogram. 2
---------------------------------------------------------------------------

    \2\ All foreign countries, with the exception of the People's 
Republic of China, France, the Soviet Union, and the United Kingdom, are 
non-nuclear-weapon states. Treaty on the Non-Proliferation of Nuclear 
Weapons, Article IX(3).
---------------------------------------------------------------------------

    (c) Imports. (1) Notification shall be given (to the fullest extent 
possible on the basis of available information) with respect to nuclear 
material which immediately prior to export is subject to safeguards, 
under an agreement with the IAEA, in the country from which the 
material, directly or indirectly, is being exported. Such notification 
is only required, however, if the quantities of nuclear material are as 
specified in paragraph (c)(2) of this section.

[[Page 626]]

    (2) Notification shall be given with respect to any proposed import 
of nuclear material described in paragraph (c)(1) of this section in an 
amount exceeding one effective kilogram. If the licensee anticipates 
that it will receive two or more shipments of such nuclear material, 
within any 90-day period from points of origin in the same country, 
notification shall be given with respect to each shipment if the 
aggregate quantity of such nuclear material to be received exceeds one 
effective kilogram.
    (d) Domestic transfers. Notification must be given regarding any 
shipments of nuclear material (other than small quantities in the form 
of samples containing less than 0.01 effective kilogram per sample) to a 
non-eligible destination. As used in this paragraph, a non-eligible 
destination means any destination in the United States other than a 
facility on the Eligible Facilities List.

[45 FR 50711, July 31, 1980, as amended at 73 FR 78613, Dec. 23, 2008]



Sec. 75.44  Timing of advance notification.

    (a) Except as provided in paragraph (b) of this section, 
notification to the Commission, when required by Sec. 75.43, must be 
given:
    (1) In the case of exports and domestic transfers, at least 20 days 
in advance of the preparation of the nuclear material for shipment from 
the facility.
    (2) In the case of imports, at least 12 days in advance of the 
unpacking of nuclear material at the facility.
    (b) For a particular receipt or shipment of nuclear material, the 
Commission will approve a shorter notice period than that specified by 
paragraph (a) of this section, for good cause, if it determines that 
observing the specified notification period would result in delay in 
shipment or unpackaging.
    (c) The licensee shall inform the Commission, by phone, as soon as 
possible, with respect to any delay in the receipt (or unpackaging) or 
the shipment (or preparation for shipment) of nuclear material for which 
advance notification is required. New dates should be provided, if 
known.

[45 FR 50711, July 31, 1980, as amended at 73 FR 78614, Dec. 23, 2008]



Sec. 75.45  Content of advance notification.

    (a) The notifications required by Sec. 75.43 must include the 
element weight of nuclear material being received or shipped, the 
chemical composition and physical form, the isotopic composition (to the 
extent specified by license conditions), the estimated date and place at 
the reporting facility where the nuclear material is to be unpackaged or 
prepared for shipment (and where the quantity and composition can be 
verified), the applicable IAEA material balance area at the reporting 
facility, the approximate number of items to be received or shipped, and 
the probable dates of receipt or shipment. The notification must 
indicate that the information is being supplied under Sec. 75.43.
    (b) The notifications required with respect to export and import 
shipments shall also include
    (1) If available, a general description of containers (including, in 
the case of exports, features that would permit sealing);
    (2) Destination of export as authorized under an export license 
issued pursuant to part 110 of this chapter, or origin of import (by 
country and, if known, place);
    (3) Means of transport; and
    (4) Expected date and place of arrival in the destination country 
(for exports) or in the United States (for imports).

[45 FR 50711, July 31, 1980, as amended at 73 FR 78614, Dec. 23, 2008]



Sec. 75.46  Expenses.

    (a) Under the Safeguards Agreement, the IAEA undertakes to reimburse 
an applicant, licensee, or certificate holder who has been given notice 
under Sec. 75.7 for extraordinary expenses incurred as a result of its 
specific request: Provided, That the IAEA has agreed in advance to do 
so. The Safeguards Agreement also contemplates

[[Page 627]]

that, in any case, the IAEA will reimburse an applicant, licensee, or 
certificate holder for the cost of making additional measurements or 
taking samples at the specific request of an IAEA inspector.
    (b) The Commission will inform the licensee, in the license 
conditions or other written communication, of those items of 
extraordinary expense which the Agency has agreed in advance to 
reimburse.
    (c) The Commission will inform the licensee, in the license 
conditions, of the procedures to be used to document:
    (1) An IAEA inspector's request for making additional measurements 
or taking additional samples; and
    (2) An IAEA request for a particular action by the licensee that 
will give rise to reimbursable extraordinary expense.
    (d) The Commission will take appropriate action to assist the 
applicant, licensee, or certificate holder regarding the reimbursement 
of any expense which, under the Safeguards Agreement, is to be borne by 
the IAEA.

[45 FR 50711, July 31, 1980, as amended at 73 FR 78614, Dec. 23, 2008]

                               Enforcement



Sec. 75.51  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(l)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.
    (c) The Commission may issue orders to secure compliance with the 
provisions of this part or to prohibit any violation of such provisions 
as may be proper to protect the common defense and security. Enforcement 
actions, including proceedings instituted with respect to Agreement 
State licensees, will be conducted in accordance with the procedures set 
forth in part 2, subpart B of this chapter. Only NRC licensees, however, 
are subject to license modification, suspension, or revocation as a 
result of enforcement action.

[57 FR 55079, Nov. 24, 1992]



Sec. 75.53  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, or conspiracy 
to violate, any regulation issued under sections 161b., 161i., or 161o. 
of the Act. For purposes of criminal sanctions under section 223, all 
the regulations in Part 75 are issued under one or more of sections 
161b., 161i., or 161o., except as provided in paragraphs (b) and (c) of 
this section.
    (b) The regulations in Part 75 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 75.1, 75.2, 75.3, 75.4, 75.5, 75.7, 75.9, 75.12, 75.15, 
75.46, 75.51, and 75.53.
    (c) Any provision in Part 75 that implements the ``Protocol 
Additional to the Agreement between the United States of America and the 
International Atomic Energy Agency for the Application of Safeguards in 
the United States of America,'' known as the ``Additional Protocol,'' 
signed by the United States on June 12, 1998, is not issued under 
sections 161b., 161i., or 161o, for the purposes of criminal sanctions 
under section 223.

[73 FR 78614, Dec. 23, 2008]

[[Page 628]]



PART 76_CERTIFICATION OF GASEOUS DIFFUSION PLANTS--Table of Contents



                      Subpart A_General Provisions

Sec.
76.1 Purpose.
76.2 Scope.
76.4 Definitions.
76.5 Communications.
76.6 Interpretations.
76.7 Employee protection.
76.8 Information collection requirements: OMB approval not required.
76.9 Completeness and accuracy of information.
76.10 Deliberate misconduct.
76.21 Certificate required.
76.22 Ineligibility of certain applicants.
76.23 Specific exemptions.

                          Subpart B_Application

76.31 Periodic application requirement.
76.33 Application procedures.
76.35 Contents of application.
76.36 Renewals.
76.37 Federal Register notice.
76.39 Public meeting.
76.41 Record underlying decisions.
76.43 Date for decision.
76.45 Application for amendment of certificate.

                         Subpart C_Certification

76.51 Conditions of certification.
76.53 Consultation with Environmental Protection Agency.
76.55 Timely renewal.
76.60 Regulatory requirements which apply.
76.62 Issuance of certificate and/or approval of compliance plan.
76.64 Denial of certificate or compliance plan.
76.65 Inalienability of certificates.
76.66 Expiration and termination of certificates.
76.68 Plant changes.
76.70 Post issuance.
76.72 Miscellaneous procedural matters.
76.74 Computation and extension of time.
76.76 Backfitting.

                            Subpart D_Safety

76.81 Authorized use of radioactive material.
76.83 Transfer of radioactive material.
76.85 Assessment of accidents.
76.87 Technical safety requirements.
76.89 Criticality accident requirements.
76.91 Emergency planning.
76.93 Quality assurance.
76.95 Training.

                    Subpart E_Safeguards and Security

76.111 Physical security, material control and accounting, and 
          protection of certain information.
76.113 Formula quantities of strategic special nuclear material--
          Category I.
76.115 Special nuclear material of moderate strategic significance--
          Category II.
76.117 Special nuclear material of low strategic significance--Category 
          III.
76.119 Security facility approval and safeguarding of National Security 
          Information and Restricted Data.

                    Subpart F_Reports and Inspections

76.120 Reporting requirements.
76.121 Inspections.
76.123 Tests.

                          Subpart G_Enforcement

76.131 Violations.
76.133 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 122, 161, 193(f), 223, 
234, 1701 (42 U.S.C. 2152, 2201, 2243(f), 2273, 2282, 2297f); Energy 
Reorganization Act of 1974, secs. 201, 206, 211 (42 U.S.C. 5841, 5846, 
5851); 44 U.S.C. 3504 note.
    Section 76.22 is also issued under Atomic Energy Act sec. 193(f) (42 
U.S.C. 2243(f)).
    Section 76.35(j) also issued under Atomic Energy Act sec. 122 (42 
U.S.C. 2152).

    Source: 59 FR 48960, Sept. 23, 1994, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 76.1  Purpose.

    (a) This part establishes requirements that will govern the 
operation of those portions of the Portsmouth and Paducah Gaseous 
Diffusion Plants located in Piketon, Ohio, and Paducah, Kentucky, 
respectively, that are leased by the United States Enrichment 
Corporation. These requirements are promulgated to protect the public 
health and safety from radiological hazards and provide for the common 
defense and security. This part also establishes the certification 
process that will be used to ensure compliance with the established 
requirements.
    (b) The regulations contained in this part are issued pursuant to 
the Atomic Energy Act of 1954, as amended (68 Stat. 919); Title II of 
the Energy Reorganization Act of 1974, as amended (88 Stat. 1242); and 
Titles IX and XI of the Energy Policy Act of 1992 (106 Stat. 2923, 
2951).

[[Page 629]]



Sec. 76.2  Scope.

    The regulations in this part apply only to those portions of the 
Portsmouth and Paducah Gaseous Diffusion Plants leased by the 
Corporation, per the Lease Agreement between the Department of Energy 
and the United States Enrichment Corporation. This part also gives 
notice to all persons who knowingly provide to the Corporation or any 
contractor, or subcontractor any components, equipment, materials, or 
other goods or services that relate to the activities subject to this 
part that they may be individually subject to NRC enforcement action for 
violation of Sec. 76.10.



Sec. 76.4  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954 (68 Stat 919), and includes 
any amendments to the Act.
    Administrative controls means the provisions relating to 
organization and management, procedures, recordkeeping, review and 
audit, and reporting necessary to ensure operation of the plant in a 
safe manner.
    Agreement State means any State with which the Commission has 
entered into an effective agreement under subsection 274b. of the Act.
    Non-Agreement State means any other State.
    Alert means events may occur, are in progress, or have occurred that 
could lead to a release of radioactive material[s] but that the release 
is not expected to require a response by an offsite response 
organization to protect persons offsite.
    Atomic energy means all forms of energy released in the course of 
nuclear fission or nuclear transformation.
    Certificate of compliance or certificate means a certificate of 
compliance issued pursuant to this part.
    Classified matter means documents or material revealing classified 
information.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Common defense and security means the common defense and security of 
the United States.
    Compliance plan means a plan for achieving compliance approved 
pursuant to this part.
    Corporation means the United States Enrichment Corporation (USEC), 
or its successor, a Corporation that is authorized by statute to lease 
the gaseous diffusion enrichment plants in Paducah, Kentucky, and 
Piketon, Ohio, from the department of Energy, or any person authorized 
to operate one or both of the gaseous diffusion plants, or other 
facilities, pursuant to a plan for the privatization of USEC that is 
approved by the President.
    Department and Department of Energy (DOE) means the Department of 
Energy established by the Department of Energy Organization Act (Pub. L. 
95-91, 91 Stat. 565, 42 U.S.C. 7101 et seq.), to the extent that the 
Department, or its duly authorized representatives, exercises functions 
formerly vested in the U.S. Atomic Energy Commission, its Chairman, 
members, officers and components and transferred to the U.S. Energy 
Research and Development Administration and to the Administrator thereof 
pursuant to Sections 104(b), (c), and (d) of the Energy Reorganization 
Act of 1974, as amended, (Pub. L. 93-438, 88 Stat. 1233 at 1237, 42 
U.S.C. 5814) and retransferred to the Secretary of Energy pursuant to 
Section 301(a) of the Department of Energy Organization Act (Pub. L. 95-
91, 91 Stat. 565 at 577-578, 42 U.S.C. 7151).
    Depleted uranium means the byproduct residues from the uranium 
enrichment process in which the concentration of the isotope 
U235 is less than that occurring in natural uranium.
    Director means the Director, or his or her designee, of the Office 
of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory 
Commission.
    Effective dose equivalent means the sum of the products of the dose 
equivalent to the body organ or tissue and the weighting factors 
applicable to each of the body organs or tissues that are irradiated, as 
defined in 10 CFR Part 20 (Sec. Sec. 20.1001 through 20.2402).
    Effective kilograms of special nuclear material means:
    (1) For uranium with an enrichment in the isotope U-235 of 0.01 (1 
percent) and above, its element weight in kilograms multiplied by the 
square of its

[[Page 630]]

enrichment expressed as a decimal weight fraction; and
    (2) For uranium with an enrichment in the isotope U-235 below 0.01 
(1 percent), its element weight in kilograms multiplied by 0.0001.
    Formula quantity means strategic special nuclear material in any 
combination in a quantity of 5000 grams or more computed by the formula, 
grams = (grams contained U-235) + 2.5(grams U-233 + grams plutonium).
    Lease Agreement means the agreement entered into as of July 1, 1993, 
and any subsequent revisions between the United States Department of 
Energy and the United States Enrichment Corporation.
    Limiting conditions for operation means the lowest functional 
capability or performance levels of structures, systems, components, and 
their support systems required for normal safe operation of the plant.
    Limiting control settings means settings for automatic alarm or 
protective devices related to those variables having significant safety 
functions.
    National Security Information means information that has been 
determined pursuant to Executive Order 12356 or any predecessor order to 
require protection against unauthorized disclosure and that is so 
designated.
    Person means:
    (1) Any individual, corporation, partnership, firm, association, 
trust, estate, public or private institution, group, Government Agency 
other than the Commission or the Department, except that the Department 
shall be considered a person within the meaning of the regulations in 
this part to the extent that its facilities and activities are subject 
to the licensing and related regulatory authority of the Commission 
pursuant to Section 202 of the Energy Reorganization Act of 1974, as 
amended, (88 Stat. 1244); any State or any political subdivision of or 
any political entity within a State, any foreign government or nation or 
any political subdivision of any such government or nation, or other 
entity; and
    (2) Any legal successor, representative, agent, or agency of the 
foregoing.
    Process means a series of actions that achieves an end or result.
    Produce, when used in relation to special nuclear material, means:
    (1) To manufacture, make, produce, or refine special nuclear 
material;
    (2) To separate special nuclear material from other substances in 
which such material may be contained; or
    (3) To make or to produce new special nuclear material.
    Radioactive material means source material, special nuclear 
material, or byproduct material, possessed, used, transferred, or 
disposed of under part 76.
    Restricted Data means all data concerning design, manufacture or 
utilization of atomic weapons, the production of special nuclear 
material, or the use of special nuclear material in the production of 
energy, but does not include data declassified or removed from the 
Restricted Data category pursuant to Section 142 of the Act.
    Safety limits means those bounds within which the process variables 
must be maintained for adequate control of the operation and that must 
not be exceeded in order to protect the integrity of the physical system 
that is designed to guard against the uncontrolled release of 
radioactivity.
    Sealed source means any radioactive material that is encased in a 
capsule designed to prevent leakage or escape of the radioactive 
material.
    Security facility approval means that a determination has been made 
by the NRC that a facility is eligible to use, process, store, 
reproduce, transmit, or handle classified matter.
    Site area emergency means events may occur, are in progress, or have 
occurred that could lead to a significant release of radioactive 
material and that could require a response by offsite response 
organizations to protect persons offsite.
    Source material means source material as defined in Section 11z. of 
the Act and in the regulations contained in part 40 of this chapter.
    Special nuclear material means:
    (1) Plutonium, uranium 233, uranium enriched in the isotope 233 or 
in the isotope 235, and any other material which the Commission, 
pursuant to the

[[Page 631]]

provisions of Section 51 of the Act, determines to be special nuclear 
material, but does not include source material; or
    (2) Any material artificially enriched in any of the foregoing, but 
does not include source material.
    Special nuclear material of low strategic significance means:
    (1) Less than an amount of special nuclear material of moderate 
strategic significance, as defined in this section, but more than 15 
grams of uranium-235 (contained in uranium enriched to 20 percent or 
more in the U-235 isotope), or 15 grams of uranium-233, or 15 grams of 
plutonium, or the combination of 15 grams when computed by the equation, 
grams = (grams contained U-235) + (grams plutonium) + (grams U-233); or
    (2) Less than 10,000 grams but more than 1000 grams of uranium-235 
(contained in uranium enriched to 10 percent or more but less than 20 
percent in the U-235 isotope), or
    (3) 10,000 grams or more of uranium-235 (contained in uranium 
enriched above natural but less than 10 percent in the U-235 isotope).
    Special nuclear material of moderate strategic significance means:
    (1) Less than a formula quantity of strategic special nuclear 
material but more than 1000 grams of uranium-235 (contained in uranium 
enriched to 20 percent or more in the U-235 isotope), or more than 500 
grams of uranium-233 or plutonium, or in a combined quantity of more 
than 1000 grams when computed by the equation, grams = (grams contained 
U-235) + 2 (grams U-233 + grams plutonium); or
    (2) 10,000 grams or more of uranium-235 (contained in uranium 
enriched to 10 percent or more but less than 20 percent in the U-235 
isotope).
    Special nuclear material scrap means the various forms of special 
nuclear material generated during chemical and mechanical processing, 
other than recycle material and normal process intermediates, which are 
unsuitable for use in their present form, but all or part of which will 
be used after further processing.
    Strategic special nuclear material means uranium-235 (contained in 
uranium enriched to 20 percent or more in the U-235 isotope), uranium-
233, or plutonium.
    Surveillance requirements means requirements relating to test, 
calibration, or inspection to ensure that the necessary quality of 
systems and components is maintained, that plant operation will be 
within the safety limits, and that the limiting conditions of operation 
will be met.
    Unclassified Controlled Nuclear Information is information whose 
unauthorized dissemination is prohibited under Section 148 of the Atomic 
Energy Act.
    United States, when used in a geographical sense, includes Puerto 
Rico and all territories and possessions of the United States.
    Unreviewed safety question means a change which involves any of the 
following:
    (1) The probability of occurrence or the consequences of an accident 
or malfunction of equipment important to safety previously evaluated in 
the safety analysis report may be increased;
    (2) A possibility for an accident or malfunction of a different type 
than any evaluated previously in the safety analysis report may be 
created; or
    (3) The margin of safety as defined in the basis for any technical 
safety requirement is reduced.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6669, Feb. 12, 1997]



Sec. 76.5  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent as follows:
    (a) By mail addressed to: ATTN: Document Control Desk, Director, 
Division of Security Policy, Office of Nuclear Security and Incident 
Response, U.S Nuclear Regulatory Commission, Washington, DC 20555-0001;
    (b) By hand delivery to the NRC's offices at 11555 Rockville Pike, 
Rockville, Maryland; or
    (c) Where practicable, by electronic submission, for example, 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a

[[Page 632]]

time. Detailed guidance on making electronic submissions can be obtained 
by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-
submittals.html; by e-mail to [email protected]; or by writing the 
Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. The guidance discusses, among 
other topics, the formats the NRC can accept, the use of electronic 
signatures, and the treatment of nonpublic information.
    (d) Classified communications shall be transmitted in accordance 
with Sec. 95.39 of this chapter to the NRC Headquarters' classified 
mailing address listed in appendix A to part 73 of this chapter or 
delivered by hand in accordance with Sec. 95.39 of this chapter to the 
NRC Headquarters' street address listed in appendix A to part 73 of this 
chapter.

[68 FR 58822, Oct. 10, 2003, as amended at 74 FR 62685, Dec. 1, 2009; 80 
FR 74981 Dec. 1, 2015]



Sec. 76.6  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 76.7  Employee protection.

    (a) Discrimination by the Corporation, a contractor, or a 
subcontractor of the Corporation against an employee for engaging in 
certain protected activities is prohibited. Discrimination includes 
discharge and other actions that relate to compensation, terms, 
conditions, or privileges of employment. The protected activities are 
established in Section 211 of the Energy Reorganization Act of 1974, as 
amended, and in general are related to the administration or enforcement 
of a requirement imposed under the Atomic Energy Act or the Energy 
Reorganization Act.
    (1) The protected activities include but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the above statutes or possible 
violations of requirements imposed under either of the above statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the above statutes or under these requirements if the employee has 
identified the alleged illegality to the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the above statutes; and
    (v) Assisting or participating in, or attempting to assist or 
participate in, the protected activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs by 
filing a complaint alleging the violation with the Department of Labor, 
Employment Standards Administration, Wage and Hour Division. The 
Department of Labor may order reinstatement, back pay, and compensatory 
damages.
    (c) A violation of paragraphs (a), (e), or (f) of this section by 
the Corporation, or a contractor or subcontractor of the Corporation may 
be grounds for:
    (1) Denial, revocation, or suspension of the certificate.

[[Page 633]]

    (2) Imposition of a civil penalty on the Corporation or a contractor 
or subcontractor of the Corporation.
    (3) Other enforcement action.
    (d) Actions taken by an employer or others which adversely affect an 
employee may be predicated upon nondiscrimination grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) The Corporation shall prominently post the revision of NRC 
Form 3, ``Notice to Employees,'' referenced in 10 CFR 19.11(c). This 
form must be posted at locations sufficient to permit employees 
protected by this section to observe a copy on the way to or from their 
place of work. Premises must be posted during the term of the 
certificate and for 30 days following certificate termination.
    (2) The Corporation shall notify its contractors of the prohibition 
against discrimination for engaging in protected activities.
    (3) Copies of NRC Form 3 may be obtained by writing to the NRC 
Region III Office listed in appendix D to part 20 of this chapter, via 
email to [email protected], or by visiting the NRC's online library 
at http://www.nrc.gov/reading-rm/doc-collections/forms/.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed by an employee with the Department of Labor pursuant to Section 
211 of the Energy Reorganization Act of 1974, as amended, may contain 
any provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[59 FR 48960, Sept. 23, 1994, as amended at 60 FR 24553, May 9, 1995; 63 
FR 15744, Apr. 1, 1998; 64 FR 44649, Aug. 17, 1999; 68 FR 58822, Oct. 
10, 2003; 72 FR 63975, Nov. 14, 2007; 73 FR 30460, May 28, 2008; 79 FR 
66606, Nov. 10, 2014]



Sec. 76.8  Information collection requirements: OMB approval not
required.

    The information collection requirements contained in this part of 
limited applicability apply to a wholly-owned instrumentality of the 
United States and affect fewer than ten respondents. Therefore, Office 
of Management and Budget clearance is not required pursuant to the 
Paperwork Reduction Act (44 U.S.C. 3501 et seq.).

[62 FR 52190, Oct. 6, 1997]



Sec. 76.9  Completeness and accuracy of information.

    (a) Information provided to the Commission or information required 
by statute or by the Commission's rules, regulations, standards, orders, 
or other conditions to be maintained by the Corporation must be complete 
and accurate in all material respects.
    (b) The Corporation shall notify the Commission of information 
identified as having for the regulated activity a significant 
implication for public health and safety or common defense and security. 
The Corporation violates this paragraph only if the Corporation fails to 
notify the Commission of information that the Corporation has identified 
as having a significant implication for public health and safety or 
common defense and security. Notification must be provided to the 
Administrator of NRC's Region III Office within 2 working days of 
identifying the information. This requirement is not applicable to 
information which is already required to be provided to the Commission 
by other reporting or updating requirements.

[59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44649, Aug. 17, 1999]



Sec. 76.10  Deliberate misconduct.

    (a) The Corporation or any employee of the Corporation and any 
contractor (including a supplier or consultant), subcontractor, or any 
employee of a

[[Page 634]]

contractor or subcontractor, who knowingly provides to the Corporation, 
or any contractor or subcontractor, components, equipment, materials, or 
other goods or services, that relate to the Corporation's activities 
subject to this part; may not:
    (1) Engage in deliberate misconduct that causes or, but for 
detection, would have caused, the Corporation to be in violation of any 
rule, regulation, or order, or any term, condition, or limitation of a 
certificate or approval issued by the Commission; or
    (2) Deliberately submit to the NRC, the Corporation, or its 
contractor or subcontractor, information that the person submitting the 
information knows to be incomplete or inaccurate in some respect 
material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause the Corporation to be in violation of any rule, 
regulation, or order, or any term, condition, or limitation of a 
certificate or approved compliance plan issued by the Director; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order or policy of the Corporation, 
contractor, or subcontractor.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6669, Feb. 12, 1997]



Sec. 76.21  Certificate required.

    (a) The Corporation or its contractors may not operate the gaseous 
diffusion plants at Piketon, Ohio, and Paducah, Kentucky, unless an 
appropriate certificate of compliance, and/or an approved compliance 
plan is in effect under this part. Unless authorized by the NRC under 
other provisions of this chapter, a person other than the Corporation or 
its contractors may not acquire, deliver, receive, possess, use, or 
transfer radioactive material at the gaseous diffusion plants at 
Piketon, Ohio, and Paducah, Kentucky.
    (b) For the purposes of Sec. Sec. 30.41, 40.51, and 70.42 of this 
chapter, the Corporation shall be authorized to receive, and licensees 
shall be authorized to transfer to the Corporation, byproduct material, 
source material, or special nuclear material to the extent permitted 
under the certificate of compliance issued, and/or the compliance plan 
approved, pursuant to this part.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6669, Feb. 12, 1997; 
64 FR 44649, Aug. 17, 1999]



Sec. 76.22  Ineligibility of certain applicants.

    A certificate of compliance may not be issued to the Corporation if 
the Commission determines that:
    (a) The Corporation is owned, controlled, or dominated by an alien, 
a foreign corporation, or a foreign government; or
    (b) The issuance of such a certificate of compliance would be 
inimical to--
    (1) The common defense and security of the United States; or
    (2) The maintenance of a reliable and economical domestic source of 
enrichment services.

[62 FR 6670, Feb. 12, 1997]



Sec. 76.23  Specific exemptions.

    The Commission may, upon its own initiative or upon application of 
the Corporation, grant such exemptions from the requirements of the 
certification regulations as it determines are authorized by law and 
will not endanger life, or property, or the common defense and security, 
and are otherwise in the public interest.



                          Subpart B_Application



Sec. 76.31  Periodic application requirement.

    The Corporation shall periodically apply to the Commission for a 
certificate of compliance, in accordance with Sec. 76.36, on or before 
April 15 of the year specified in an existing certificate of compliance 
as determined by the Commission, but not less frequently than every 5 
years.

[62 FR 6670, Feb. 12, 1997]



Sec. 76.33  Application procedures.

    (a) Filing requirements. (1) An application for a certificate of 
compliance

[[Page 635]]

must be tendered by filing the application with the Director of the 
NRC's Office of Nuclear Material Safety and Safeguards, with copies sent 
to the NRC Region III Office and appropriate resident inspector, in 
accordance with Sec. 76.5. If the application is to be submitted 
electronically, see Guidance for Electronic Submissions to the 
Commission at http://www.nrc.gov/site-help/e-submittals.html.
    (2) The application must include the full name, address, age (if an 
individual), and citizenship of the applicant. If the applicant is a 
corporation or other entity, the application must indicate the State 
where it was incorporated or organized; the location of the principal 
office; and the names, addresses, and citizenship of its principal 
officers. The applicant shall include any known information concerning 
the control or ownership, if any, exercised over the applicant by any 
alien, foreign corporation, or foreign government.
    (b) Oath or affirmation. An application for a certificate of 
compliance must be executed in a signed original by a duly authorized 
officer of the Corporation under oath or affirmation.
    (c) Pre-filing consultation. The Corporation may confer with the 
Commission's staff before filing an application.
    (d) Additional information. At any time during the review of an 
application, the Corporation may be required to supply additional 
information to the Commission's staff to enable the Commission or the 
Director, as appropriate, to determine whether the certificate should be 
issued or denied, or to determine whether a compliance plan should be 
approved.
    (e) Withholdable information. If an application contains Restricted 
Data, National Security Information, Safeguards Information, 
Unclassified Controlled Nuclear Information, proprietary data, or other 
withholdable information, the applicant shall ensure that the 
withholdable information is separate from the information to be made 
publicly available.

[64 FR 44649, Aug. 17, 1999, as amended at 68 FR 58822, Oct. 10, 2003; 
74 FR 62685, Dec. 1, 2009]



Sec. 76.35  Contents of application.

    The application for a certificate of compliance must include the 
information identified in this section.
    (a) A safety analysis report which must include the following 
information:
    (1) The activities and locations involving special nuclear material 
and the general plan for carrying out these activities;
    (2) The name, amount, and specifications (including the chemical and 
physical form and, where applicable, isotopic content) of the special 
nuclear material, source and byproduct material the Corporation proposes 
to use, possess or produce, including any material held up in equipment 
from previous operations;
    (3) The qualifications requirements, including training and 
experience, of the Corporation's management organization and key 
individuals responsible for safety in accordance with the regulations in 
this chapter;
    (4) An assessment of accidents based on the requirements of Sec. 
76.85;
    (5) A training program that meets the requirements of Sec. 76.95;
    (6) A description of equipment and facilities which will be used by 
the Corporation to protect health and minimize danger to life or 
property (such as handling devices, working areas, shields, measuring 
and monitoring instruments, devices for the treatment and disposal of 
radioactive effluent and wastes, storage facilities, provisions for 
protection against natural phenomena, fire protection systems, 
criticality accident alarm systems, etc.);
    (7) A description of the management controls and oversight program 
to ensure that activities directly relevant to nuclear safety and 
safeguards and security are conducted in an appropriately controlled 
manner that ensures protection of employee and public health and safety 
and protection of the national security interests; and
    (8) A description of the plant site, and a description of the 
principal structures, systems, and components of the plant.
    (b) A plan prepared and approved by DOE for achieving compliance 
with respect to any areas of noncompliance with the NRC's regulations 
that are

[[Page 636]]

identified by the Corporation as of the date of the application that 
includes:
    (1) A description of the areas of noncompliance;
    (2) A plan of actions and schedules for achieving compliance; and
    (3) A justification for continued operation with adequate safety and 
safeguards.
    (c) Any relevant information concerning deviations from the 
published Environmental Impact Statement, Environmental Assessments, or 
environmental permits under which the plants currently operate from 
which the Commission can prepare an environmental assessment related to 
the compliance plan.
    (d) A quality assurance program that meets the requirements of Sec. 
76.93.
    (e) Technical safety requirements in accordance with Sec. 76.87. A 
summary statement of the bases or reasons for the requirements, other 
than those covering administrative controls, must also be included in 
the application, but will not be considered part of the technical safety 
requirements.
    (f) An emergency plan that meets the requirements of Sec. 76.91.
    (g) A compliance status report that includes the status of various 
State, local and Federal permits, licenses, approvals, and other 
entitlements, as described in Sec. 51.45(d) of this chapter. The report 
must include environmental and effluent monitoring data.
    (h) A fundamental nuclear material control plan which describes the 
measures used to control and account for special nuclear material that 
the Corporation uses, possesses, or has access to. The plan must 
describe, as appropriate:
    (1) How formula quantities of strategic special nuclear material 
will be controlled and accounted for in accordance with the relevant 
requirements of subpart E;
    (2) How special nuclear material of moderate strategic significance 
will be controlled and accounted for in accordance with the relevant 
requirements of subpart E; and
    (3) How special nuclear material of low strategic significance will 
be controlled and accounted for in accordance with the relevant 
requirements of subpart E.
    (i) A transportation protection plan which describes the measures 
used to protect shipments of special nuclear material of low strategic 
significance in accordance with the relevant requirements of subpart E 
when in transit offsite.
    (j) A physical protection plan which describes the measures used to 
protect special nuclear material that the Corporation uses, possesses, 
or has access to at fixed sites. The plan must describe, as appropriate:
    (1) How formula quantities of special nuclear material will be 
protected against both theft and radiological sabotage in accordance 
with the relevant requirements of subpart E;
    (2) How special nuclear material of moderate strategic significance 
will be protected in accordance with the relevant requirements of 
subpart E;
    (3) How special nuclear material of low strategic significance will 
be protected in accordance with the relevant requirements of subpart E; 
and
    (4) The measures used to protect special nuclear material while in 
transit between protected areas, all of which are located on a single 
fixed site under the control of the applicant. The level of protection 
afforded the material while in transit may not be less than that 
afforded the same material while it was within the protected area from 
which transit began.
    (k) A plan describing the facility's proposed security procedures 
and controls as set forth in Sec. 95.15(b) of this chapter for 
protection of classified matter.
    (l)(1) In response to a written request by the Commission, each 
applicant for a certificate and each recipient of a certificate shall 
submit facility information, as described in Sec. 75.10 of this 
chapter, on Form N-71 and associated forms and site information on DOC/
NRC Form AP-A and associated forms;
    (2) As required by the Additional Protocol, shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms; and
    (3) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA); and shall take other

[[Page 637]]

action as may be necessary to implement the US/IAEA Safeguards 
Agreement, as described in Part 75 of this chapter.
    (m) A description of the program, as appropriate, for processing, 
management, and disposal of mixed and radioactive wastes and depleted 
uranium generated by operations. This description must be limited to 
processing, management, and disposal activities conducted during 
operation of the facilities while under lease to the Corporation. The 
application must also include a description of the waste streams 
generated by enrichment operations, annual volumes of depleted uranium 
and waste expected, identification of radioisotopes contained in the 
waste, physical and chemical forms of the depleted uranium and waste, 
plans for managing the depleted uranium and waste, and plans for 
ultimate disposition of the waste and depleted uranium before turnover 
of the facilities to the Department of Energy under the terms of the 
lease agreement between the United States Enrichment Corporation and the 
Department.
    (n) A description of the funding program to be established to ensure 
that funds will be set aside and available for those aspects of the 
ultimate disposal of waste and depleted uranium, decontamination and 
decommissioning, relating to the gaseous diffusion plants leased to the 
Corporation by the Department of Energy, which are the financial 
responsibility of the Corporation. The Corporation shall establish 
financial surety arrangements to ensure that sufficient funds will be 
available for the ultimate disposal of waste and depleted uranium, and 
decontamination and decommissioning activities which are the financial 
responsibility of the Corporation. The funding mechanism, such as 
prepayment, surety, insurance, or external sinking fund, must ensure 
availability of funds for any activities which are required to be 
completed both before or after the return of the gaseous diffusion 
facilities to the department of Energy in accordance with the lease 
between the Department and the Corporation. The funding program must 
contain a basis for cost estimates used to establish funding levels and 
must contain means of adjusting cost estimates and associated funding 
levels over the duration of the lease. The funding program need not 
address funding for those aspects of decontamination and decommissioning 
of the gaseous diffusion plants assigned to the Department of Energy 
under the Atomic Energy Act of 1954, as amended. The Corporation should 
address the adequacy of the financing mechanism selected in its periodic 
application for certification.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997; 
64 FR 44649, Aug. 17, 1999; 73 FR 78614, Dec. 23, 2008]



Sec. 76.36  Renewals.

    (a) The Corporation shall file periodic applications for renewal, as 
required by Sec. 76.31.
    (b) Information contained in previous applications, statements, or 
reports filed with the Commission may be referenced as part of the 
application, provided that the reference is clear and specific.
    (c) An application for renewal is subject to the requirements in 
Sec. 76.33 and must contain the following information:
    (1) The information specified in Sec. 76.35; or,
    (2) A statement by the Corporation that the NRC may rely upon the 
information provided in the previous application(s) upon which the 
existing certificate is based, except for:
    (i) Any proposed changes in the existing certificate of compliance 
conditions or technical safety requirements;
    (ii) Any proposed changes to the documents submitted with the 
previous application in accordance with Sec. 76.35;
    (iii) Any changes which the Corporation has made without prior NRC 
approval pursuant to Sec. 76.68; and,
    (iv) Any changes to certificate conditions or technical safety 
requirements for which the Corporation has sought and received 
Commission approval pursuant to Sec. 76.45.
    (d) The changes which are submitted as part of an application for 
renewal in accordance with paragraph (c)(2) of this section, must be in 
the form of specific changes to the documentation specified

[[Page 638]]

in Sec. 76.35. The changes must be marked and dated for easy 
identification.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997; 
64 FR 44649, Aug. 17, 1999]



Sec. 76.37  Federal Register notice.

    The Director may, at his or her discretion, publish in the Federal 
Register:
    (a) A notice of the filing of an application specifying that copies 
of the application, except for Restricted Data, Unclassified Controlled 
Nuclear Information, Classified National Security Information, 
Safeguards Information, Proprietary Data, or other withholdable 
information will be made available for the public inspection at the NRC 
Web site, http://www.nrc.gov;
    (b) A notice of opportunity for written public comment on the 
application for renewal; and
    (c) The date of any scheduled public meeting regarding the 
application for renewal.

[64 FR 44649, Aug. 17, 1999, as amended at 64 FR 48955, Sept. 9, 1999]



Sec. 76.39  Public meeting.

    (a) A public meeting will be held on an application for renewal if 
the Director, in his or her discretion, determines that a meeting is in 
the public interest with respect to a decision on the application for 
renewal.
    (b) Conduct of public meeting.
    (1) The Director shall conduct any public meeting held on the 
application for renewal.
    (2) Public meetings will take place near the locale of the subject 
plant, unless otherwise specified by the Director.
    (3) A public meeting will be open to all interested members of the 
public and be conducted as deemed appropriate by the Director.
    (4) Members of the public will be given an opportunity during a 
public meeting to make their views regarding the application for renewal 
known to the Director.
    (5) A transcript will be kept of each public meeting.
    (6) No Restricted Data, Classified National Security Information, 
Unclassified Controlled Nuclear Information, Safeguards Information, 
Proprietary Data, or other withholdable information may be introduced at 
the meeting.

[59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44649, Aug. 17, 1999]



Sec. 76.41  Record underlying decisions.

    (a) Any decision of the Commission or its designee under this part 
in any proceeding regarding an application for a certificate must be 
based on information in the record and facts officially noticed in the 
proceeding.
    (b) All public comments and correspondence in any proceeding 
regarding an application for a certificate must be made a part of the 
public docket of the proceeding, except as provided under 10 CFR 2.390.

[59 FR 48960, Sept. 23, 1994, as amended at 69 FR 2281, Jan. 14, 2004]



Sec. 76.43  Date for decision.

    The Director will render a decision on an application within 6 
months of the receipt of the application unless the Director alters the 
date for decisions and publishes notice of the new date in the Federal 
Register.

[62 FR 6670, Feb. 12, 1997]



Sec. 76.45  Application for amendment of certificate.

    (a) Contents of an amendment application. In addition to the 
application for certification submitted under Sec. 76.31, the 
Corporation may at any time apply for an amendment of the certificate to 
cover proposed new or modified activities. The amendment application 
should contain sufficient information for the NRC to make findings of 
compliance or acceptability for the proposed activities in the same 
manner as was required for the original certificate.
    (b) Oath or affirmation. An application for an amendment of the 
certificate of compliance must be executed in a signed original by the 
Corporation under oath or affirmation.
    (c) Amendment application determinations. If the NRC staff approves 
an application for a certificate amendment, it will be effective on a 
date specified by the NRC staff. If an application for a certificate 
amendment is not approved by the NRC staff, the Corporation will be 
informed in writing. The

[[Page 639]]

NRC staff may, at its discretion, publish notice of its determination on 
an amendment application in the Federal Register.
    (d) Request for review of staff's determination on an amendment 
application. The Corporation, or any person whose interest may be 
affected, may file a petition requesting the Director's review of an NRC 
staff determination on an amendment application. A petition requesting 
the Director's review may not exceed 30 pages and must be filed within 
30 days after the date of the NRC staff's determination. Any person 
described in this paragraph may file a written response to a petition 
requesting the Director's review. This response may not exceed 30 pages 
and must be filed within 15 days after the filing date of the petition 
requesting the Director's review. The Director may adopt, modify, or set 
aside the findings, conclusions, conditions, or terms in the NRC staff's 
amendment determination by providing a written basis for the action. If 
the Director does not issue a decision or take other appropriate action 
within 60 days after receiving the petition for review, the NRC staff's 
determination on the amendment application remains in effect.
    (e) Request for review of a Director's decision. The Corporation, or 
any person whose interest may be affected and who filed a petition for 
review or filed a response to a petition for review under Sec. 
76.45(d), may file a petition requesting the Commission's review of a 
Director's decision on an amendment application.
    (1) A petition requesting the Commission's review may not exceed 30 
pages and must be filed within 30 days after the date of the Director's 
decision. A petition requesting the Commission's review may be either:
    (i) Delivered to the Rulemakings and Adjudications Staff of the 
Office of the Secretary at One White Flint North, 11555 Rockville Pike, 
Rockville, MD 20852; or
    (ii) Sent by mail or telegram to the Secretary, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings 
and Adjudications Staff.
    (2) Any person described in paragraph (e) of this section may file a 
written response to a petition requesting the Commission's review. This 
response may not exceed 30 pages and must be filed within 15 days after 
the filing date of the petition requesting the Commission's review.
    (3) The Commission may adopt, by order, further procedures that, in 
its judgment, would serve the purpose of review of the Director's 
decision. The Commission may adopt, modify, or set aside the findings, 
conclusions, conditions, or terms in the Director's amendment review 
decision and will state the basis of its action in writing. If the 
Commission does not issue a decision or take other appropriate action 
within 90 days after receiving the petition for review, the Director's 
decision, under Sec. 76.45(d), on the amendment application remains in 
effect.

[64 FR 44649, Aug. 17, 1999]



                         Subpart C_Certification



Sec. 76.51  Conditions of certification.

    The Corporation shall comply with the certificate of compliance, any 
approved compliance plan, and the requirements set forth and referenced 
in this part, except as may be modified by the certificate or approved 
compliance plan.



Sec. 76.53  Consultation with Environmental Protection Agency.

    In reviewing an application for a certificate, including the 
provisions of any compliance plan, the Director shall consult with the 
Environmental Protection Agency and solicit the Environmental Protection 
Agency's written comments on the application.



Sec. 76.55  Timely renewal.

    In any case in which the Corporation has timely filed a sufficient 
application for a certificate of compliance, the existing certificate of 
compliance or approved compliance plan does not expire until the 
application for a certificate of compliance has been finally determined 
by the NRC. For purposes of this rule, a sufficient application is one 
that addresses all elements of Sec. 76.36.

[62 FR 6670, Feb. 12, 1997]

[[Page 640]]



Sec. 76.60  Regulatory requirements which apply.

    The Nuclear Regulatory Commission will use the following 
requirements for certification of the Corporation for operation of the 
gaseous diffusion plants:
    (a) The Corporation shall provide for adequate protection of the 
public health and safety and common defense and security.
    (b) The Corporation shall comply with the provisions of this part.
    (c) The Corporation shall comply with the applicable provisions of 
10 CFR part 19, ``Notices, Instructions and Reports to Workers: 
Inspection and Investigations,'' with the following modifications:
    (1) [Reserved]
    (2) The Corporation shall post NRC Form 3 during the term of the 
certificate and for 30 days following certificate termination.
    (d) The Corporation shall comply with the applicable provisions of 
10 CFR part 20, ``Standards for Protection Against Radiation,'' with the 
following modifications:
    (1) [Reserved]
    (2) The Corporation shall comply with the requirements in this part 
or as specified in an approved plan for achieving compliance.
    (e) The Corporation shall comply with the applicable provisions of 
10 CFR part 21, ``Reporting of Defects and Noncompliance,'' with the 
following modifications:
    (1) The Corporation shall comply with the requirements in Sec. Sec. 
21.6 and 21.21.
    (2) Under Sec. 21.31, procurement documents issued by the 
Corporation must specify that the provisions of 10 CFR Part 21 apply.
    (f) The Corporation shall comply with the applicable provisions of 
10 CFR Part 26, ``Fitness-for-Duty Programs.'' The requirements of this 
section apply only if the Corporation elects to engage in activities 
involving formula quantities of strategic special nuclear material. When 
applicable, the requirements apply only to the Corporation and personnel 
carrying out the activities specified in Sec. 26.4(d)(1) through (5), 
of this chapter.
    (g) The Corporation shall comply with the applicable provisions of 
10 CFR part 71, ``Packaging and Transportation of Radioactive 
Material.''
    (h) The Corporation shall comply with the applicable provisions for 
physical security and material control and accounting as specified in 
subpart E to this part and contained in 10 CFR part 70, ``Domestic 
Licensing of Special Nuclear Material,'' part 73, ``Physical Protection 
of Plants and Materials,'' and part 74, ``Material Control and 
Accounting of Special Nuclear Material.'' The requirements in these 
parts address safeguards for three different kinds of nuclear material: 
Special nuclear material of low strategic significance (Category III), 
special nuclear material of moderate strategic significance (Category 
II), and formula quantities of strategic special nuclear material 
(Category I). The requirements for Category III material apply to the 
production of low enriched uranium. The requirements for Category II and 
Category I material apply only if the Corporation elects to engage in 
activities that involve these kinds of material and then only to the 
situations and locations that involve these kinds of material.
    (i) The Corporation shall comply with the applicable provisions of 
10 CFR part 95, ``Security Facility Approval and Safeguarding of 
National Security Information and Restricted Data,'' as specified in 
subpart E to this part.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997; 
64 FR 44650, Aug. 17, 1999; 74 FR 45545, Sept. 3, 2009]



Sec. 76.62  Issuance of certificate and/or approval of compliance plan.

    (a) Upon a finding of compliance with the Commission's regulations 
for issuance of a certificate and/or approval of a compliance plan, the 
Director shall issue a written decision explaining the decision. The 
Director may issue a certificate of compliance covering those areas 
where the Corporation is in compliance with applicable Commission 
requirements and approve a compliance plan for the remaining areas, if 
any, of noncompliance. The Director may impose any appropriate terms and 
conditions.

[[Page 641]]

    (b) The Director shall publish notice of the decision in the Federal 
Register.
    (c) The Corporation, or any person whose interest may be affected, 
may file a petition, not to exceed 30 pages, requesting review of the 
Director's decision. This petition must be filed with the Commission not 
later than 30 days after publication of the Federal Register notice. Any 
person described in this paragraph may file a response to any petition 
for review, not to exceed 30 pages, within 15 days after the filing of 
the petition. If the Commission does not issue a decision or take other 
appropriate action within 90 days after the publication of the Federal 
Register notice, the Director's decision remains in effect. The 
Commission may adopt, by order, further procedures that, in its 
judgment, would serve the purpose of review of the Director's decision.
    (d) The Commission may adopt, modify, or set aside the findings, 
conclusions, conditions, or terms in the Director's decision and will 
state the basis of its action in writing.

[59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44650, Aug. 17, 1999]



Sec. 76.64  Denial of certificate or compliance plan.

    (a) The Director may deny an application for a certificate of 
compliance or not approve a compliance plan upon a written finding that 
the application is in noncompliance with one or more of the Commission's 
requirements for the plant, or that the compliance plan is inadequate to 
protect the public health and safety or the common defense and security.
    (b) The Director shall publish notice of the decision in the Federal 
Register.
    (c) Before a denial of an application for a certificate of 
compliance, the Director shall advise the Corporation and the Department 
in writing of any areas of noncompliance with the Commission's 
regulations and offer the Department or the Corporation an opportunity 
to submit a proposed compliance plan prepared by the Department 
regarding the identified areas of noncompliance. The Director shall take 
this action even if the Department or the Corporation has previously 
submitted a proposed compliance plan addressing in whole or in part the 
identified areas of noncompliance.
    (d) The Corporation, or any person whose interest may be affected, 
may file a petition for review, not to exceed 30 pages, requesting 
review of the Director's decision. This petition for review must be 
filed with the Commission not later than 30 days after publication of 
the Federal Register notice. Any person described in this paragraph may 
file a response to any petition for review, not to exceed 30 pages, 
within 15 days after the filing of the petition for review. If the 
Commission does not issue a decision or take other appropriate action 
within 90 days after the publication of the Federal Register notice, the 
Director's decision remains in effect. The Commission may adopt, by 
order, further procedures that, in its judgment, would serve the purpose 
of review of the Director's decision.
    (e) The Commission may adopt, modify, or set aside the findings, 
conclusions, conditions, or terms in the Director's decision and will 
state the basis of its action in writing.

[59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44650, Aug. 17, 1999]



Sec. 76.65  Inalienability of certificates.

    The certificate granted under the regulations in this part may not 
be transferred, assigned, or in any manner disposed of, either 
voluntarily or involuntarily, directly or indirectly, through transfer 
of control of any certificate to any person unless the Commission, after 
securing full information, finds that the transfer is in accordance with 
the provisions of the Act, and consents in writing.



Sec. 76.66  Expiration and termination of certificates.

    (a) Except as provided in Sec. 76.55, each certificate or approval 
issued pursuant to this part expires at the end of the day, in the month 
and year stated in the certificate or approval.
    (b) The Corporation shall notify the Commission promptly, in writing 
under Sec. 76.5, when the Corporation decides to terminate operation at 
either of the

[[Page 642]]

gaseous diffusion plants and other activities authorized under the 
certificate.
    (c) If the Corporation does not submit a renewal application under 
Sec. 76.36, the Corporation shall, on or before the expiration date 
specified in the existing certificate, terminate operation of the 
gaseous diffusion plants.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997]



Sec. 76.68  Plant changes.

    (a) The Corporation may make changes to the plant or to the plant's 
operations as described in the safety analysis report without prior 
Commission approval provided all the provisions of this section are met:
    (1) The Corporation shall conduct a written safety analysis which 
demonstrates that the changes would not result in undue risk to public 
health and safety, the common defense and security, or to the 
environment.
    (2) The changes must be authorized by responsible management and 
approved by a safety review committee.
    (3) The changes may not decrease effectiveness of the plant's 
safety, safeguards, and security programs.
    (4) The changes may not involve a change in any condition to the 
certificate of compliance.
    (5) The changes may not involve a change to any condition to the 
approved compliance plan.
    (6) The changes may not involve an unreviewed safety question.
    (b) To ensure that the approved application remains current with 
respect to the actual site description and that the plant's programs, 
plans, policies, and operations are in place, the Corporation shall 
submit revised pages to the approved application and safety analysis 
report, marked and dated to indicate each change. The Corporation shall 
evaluate any as-found conditions that do not agree with the plant's 
programs, plans, policies, and operations in accordance with paragraph 
(a) of this section. These revisions must be submitted before April 15 
of each calendar year, or at a shorter interval as may be specified in 
the certificate. If a renewal application for a certificate is filed in 
accordance with Sec. 76.36 of this part, the revisions shall be 
incorporated into the application.
    (c) The Corporation shall maintain records of changes in the plant 
and of changes in the programs, plans, policies, procedures and 
operations described in the approved application, and copies of the 
safety analyses on which the changes were based. The records of plant 
changes must be retained until the end of the duration of the lease. The 
records of changes in programs, plans, policies, procedures, and 
operations and copies of the safety analysis on which the changes were 
based must be retained for a period of 2 years.
    (d) The Corporation may at any time apply under Sec. 76.45 for 
amendment of the certificate to cover proposed new or modified 
activities not permitted by paragraph (a) of this section.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997]



Sec. 76.70  Post issuance.

    (a) Amendment of certificate terms and conditions. The terms and 
conditions of a certificate of compliance or an approved compliance plan 
are subject to modification by reason of amendments to the Act, or by 
reason of rules, regulations, or orders issued in accordance with the 
Act.
    (b) Revocation, suspension, or amendments for cause. A certificate 
of compliance or a compliance plan may be revoked, suspended, or 
amended, in whole or in part for:
    (1) Any material false statement in the application or statement of 
fact required by the Commission in connection with the application;
    (2) Conditions revealed by the application, or any report, record, 
inspection, or other means which would warrant the Commission to refuse 
to grant a certificate or approve a compliance plan on an original 
application; and
    (3) Violation of, or failure to observe any of, the applicable terms 
and conditions of the Act, or the certificate of compliance, the 
compliance plan, or any rule, regulation, or order of the Commission.
    (c) Procedures governing amendment, revocation, suspension, or 
imposing requirements by order. (1) Except in cases of willfulness or 
those in which the

[[Page 643]]

public health interest, common defense and security, or safety requires 
otherwise, no certificate of compliance or compliance plan may be 
amended, suspended, or revoked unless before the institution of 
proceedings therefore, facts or conduct which may warrant the action 
must have been called to the attention of the Corporation in writing and 
the Corporation shall have been accorded an opportunity to demonstrate 
or achieve compliance with the lawful requirements related to such 
action.
    (2) The Commission may institute a proceeding to modify, suspend, or 
revoke a certificate or take such other action as may be proper by 
serving on the Corporation or other person subject to the jurisdiction 
of the Commission an order that will:
    (i) Allege the violations with which the Corporation or other person 
subject to the Commission's jurisdiction is charged, or the potentially 
hazardous conditions or other facts deemed to be sufficient ground for 
the proposed action, and specify the action proposed;
    (ii) Provide that the Corporation or other person who is charged 
must, and other interested persons may, submit a written response to the 
order within a reasonable period after publication of the order as may 
be specified in the order;
    (iii) Specify the issues for resolution should the order be 
contested;
    (iv) State the effective date of the order; if the Commission finds 
the public health, common defense and security, or safety, so require or 
that the violation or conduct causing the violation is willful, the 
order may provide that the proposed action be immediately effective 
pending further order and include a statement of reasons for making the 
proposed action immediately effective;
    (v) Provide that the Commission may make a final decision after 
consideration of the written submissions or may in its discretion adopt 
by order, upon the Commission's own initiative or at the request of the 
Corporation or an interested person, further procedures for a hearing of 
the issues before making a final enforcement decision. These procedures 
may include requirements for further participation in the proceeding, 
such as the requirements for intervention under Part 2, subparts C, G or 
L of this chapter. Submission of written comments by interested persons 
do not constitute entitlement to further participation in the 
proceeding. Further procedures will not normally be provided for at the 
request of an interested person unless the person is adversely affected 
by the order.
    (3) The Corporation or other person to whom the Commission has 
issued an immediately effective order may, in addition to submitting a 
written response, move the Commission to set aside the immediate 
effectiveness of the order on the ground that the order, including the 
need for immediate effectiveness, is not based on adequate evidence but 
on mere suspicion, unfounded allegations, or error. The motion must 
state with particularity the reasons why the order is not based on 
adequate evidence and must be accompanied by affidavits or other 
evidence relied on. The NRC staff shall respond within 5 days of the 
receipt of the motion.
    (d) Notice of violation. (1) In response to an alleged violation of 
any provision of the Act or NRC regulations or the conditions of a 
certificate, compliance plan, or an order issued by the Commission, the 
Commission may serve on the Corporation or other person subject to the 
jurisdiction of the Commission a written notice of violation. A separate 
notice may be omitted if an order or demand for information pursuant to 
this section is issued that otherwise identifies the apparent violation. 
The notice of violation will concisely state the alleged violation and 
will require the Corporation or other person subject to it, within 
twenty (20) days of the date of the notice or other specified time, to 
submit a written explanation or statement in reply including:
    (i) Corrective steps which have been taken by the Corporation or 
other person and the results achieved;
    (ii) Corrective steps which will be taken; and
    (iii) The date when full compliance will be achieved.
    (2) The notice may require the Corporation or other person subject 
to the jurisdiction of the Commission to admit or deny the violation and 
to state the reasons for the violation, if

[[Page 644]]

admitted. It may provide that, if an adequate reply is not received 
within the time specified in the notice, the Commission may issue an 
order or a demand for information as to why the certificate should not 
be modified, suspended, or revoked or why such other action as may be 
proper should not be taken.
    (e) Additional information. At any time after the granting of a 
certificate of compliance or approval of a compliance plan, the 
Commission may require further statements from the Corporation, signed 
under oath or affirmation, in order to enable the Commission to 
determine whether the certificate or approved compliance plan should be 
modified or revoked.

[59 FR 48960, Sept. 23, 1994, as amended at 69 FR 2281, Jan. 14, 2004]



Sec. 76.72  Miscellaneous procedural matters.

    (a) The filing of any petitions for review or any responses to these 
petitions are governed by the procedural requirements set forth in 10 
CFR 2.302(a) and (c), 2.304, 2.305, 2.306, and 2.307. Additional 
guidance regarding the filing and service of petitions for review of the 
Director's decision and responses to these petitions may be provided in 
the Director's decision or by order of the Commission.
    (b) The Secretary of the Commission has the authority to rule on 
procedural matters set forth in 10 CFR 2.346.
    (c) There are no restrictions on ex parte communications or on the 
ability of the NRC staff and the Commission to communicate with one 
another at any stage of the regulatory process, with the exception that 
the rules on ex parte communications and separation of functions set 
forth in 10 CFR 2.347 and 2.348 apply to proceedings under 10 CFR Part 2 
for imposition of a civil penalty.
    (d) The procedures set forth in 10 CFR 2.205, and in 10 CFR part 2, 
subparts C, G, L and N will be applied in connection with NRC action to 
impose a civil penalty pursuant to Section 234 of the Atomic Energy Act 
of 1954, as amended, or Section 206 of the Energy Reorganization Act of 
1974 and the implementing regulations in 10 CFR part 21 (Reporting of 
Defects and Noncompliance), as authorized by section 1312(e) of the 
Atomic Energy Act of 1954, as amended.
    (e) The procedures set forth in 10 CFR 2.206 apply to a request by 
any person to institute a proceeding pursuant to Sec. 76.70 to amend, 
revoke, or suspend a certificate of compliance or approved compliance 
plan, or for such other action as may be proper.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6670, Feb. 12, 1997; 
69 FR 2281, Jan. 14, 2004]



Sec. 76.74  Computation and extension of time.

    (a) In computing any period of time, the day of the act, event or 
default after which the designated period of time begins to run is not 
included. The last day of the period so computed is included unless it 
is a Saturday, Sunday, or legal holiday at the place where the action or 
event is to occur, in which event the period runs until the end of the 
next day which is neither a Saturday, Sunday, nor holiday.
    (b) Except as otherwise provided by law, whenever an act is required 
or allowed to be done at or within a specified time, the time fixed or 
the period of time prescribed may for good cause be extended or 
shortened by the Commission.



Sec. 76.76  Backfitting.

    (a)(1) Backfitting is defined as the modification of, or addition 
to, systems, structures, or components of a plant; or to the procedures 
or organization required to operate a plant; any of which may result 
from a new or amended provision in the Commission rules or the 
imposition of a regulatory staff position interpreting the Commission 
rules that is either new or different from a previous NRC staff 
position.
    (2) Except as provided in paragraph (a)(4) of this section, the 
Commission shall require a systematic and documented analysis pursuant 
to paragraph (b) of this section for backfits which it seeks to impose.
    (3) Except as provided in paragraph (a)(4) of this section, the 
Commission shall require the backfitting of a plant only when it 
determines, based on the analysis described in paragraph (b) of

[[Page 645]]

this section, that there is a substantial increase in the overall 
protection of the public health and safety or the common defense and 
security to be derived from the backfit and that the direct and indirect 
costs of implementation for that plant are justified in view of this 
increased protection.
    (4) The provisions of paragraphs (a)(2) and (a)(3) of this section 
are inapplicable and, therefore, backfit analysis is not required and 
the standards in paragraph (a)(3) of this section do not apply where the 
Commission or staff, as appropriate, finds and declares, with 
appropriately documented evaluation for its finding, any of the 
following:
    (i) That a modification is necessary to bring a plant into 
compliance with a certificate or the rules or orders of the Commission, 
or into conformance with written commitments by the Corporation; or
    (ii) That regulatory action is necessary to ensure that the plant 
provides adequate protection to the health and safety of the public and 
is in accord with the common defense and security; or
    (iii) That the regulatory action involves defining or redefining 
what level of protection to the public health and safety or common 
defense and security should be regarded as adequate.
    (5) The Commission shall always require the backfitting of a plant 
if it determines that the regulatory action is necessary to ensure that 
the plant provides adequate protection to the health and safety of the 
public and is in accord with the common defense and security.
    (6) The documented evaluation required by paragraph (a)(4) of this 
section must include a statement of the objectives of and reasons for 
the modification and the basis for invoking the exception. If immediate 
effective regulatory action is required, then the documented evaluation 
may follow, rather than precede, the regulatory action.
    (7) If there are two or more ways to achieve compliance with a 
certificate or the rules or orders of the Commission, or with written 
Corporation commitments, or there are two or more ways to reach a level 
of protection which is adequate, then ordinarily the Corporation is free 
to choose the way which best suits its purposes. However, should it be 
necessary or appropriate for the Commission to prescribe a specific way 
to comply with its requirements or to achieve adequate protection, then 
cost may be a factor in selecting the way, provided that the objective 
of compliance or adequate protection is met.
    (b) In reaching the determination required by paragraph (a)(3) of 
this section, the Commission will consider how the backfit should be 
scheduled in light of other ongoing regulatory activities at the plant 
and, in addition, will consider information available concerning any of 
the following factors as may be appropriate and any other information 
relevant and material to the proposed backfit:
    (1) Statement of the specific objectives that the proposed backfit 
is designed to achieve;
    (2) General description of the activity that would be required by 
the Corporation in order to complete the backfit;
    (3) Potential change in the risk to the public from the accidental 
release of radioactive material;
    (4) Potential impact on radiological exposure of facility employees;
    (5) Installation and continuing costs associated with the backfit, 
including the cost of plant downtime;
    (6) The potential safety impact of changes in plant or operational 
complexity, including the relationship to proposed and existing 
regulatory requirements;
    (7) The estimated resource burden on the NRC associated with the 
proposed backfit and the availability of such resources;
    (8) The potential impact of differences in plant type, design, or 
age on the relevancy and practicality of the proposed backfit; and
    (9) Whether the proposed backfit is interim or final and, if 
interim, the justification for imposing the proposed backfit on an 
interim basis.
    (c) No certificate will be withheld during the pendency of backfit 
analyses required by the Commission's rules.
    (d) The Executive Director for Operations shall be responsible for 
implementation of this section, and all analyses required by this 
section shall be

[[Page 646]]

approved by the Executive Director for Operations or his or her 
designee.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6671, Feb. 12, 1997]



                            Subpart D_Safety



Sec. 76.81  Authorized use of radioactive material.

    Unless otherwise authorized by law, the Corporation shall confine 
its possession and use of radioactive material to the locations and 
purposes covered by the certificate and/or approved compliance plan. 
Except as otherwise provided, the certificate or approved compliance 
plan issued pursuant to the requirements in this part entitles the 
Corporation to receive title to, own, acquire, receive, possess, and use 
radioactive material in accordance with the certificate.



Sec. 76.83  Transfer of radioactive material.

    (a) The Corporation may not transfer radioactive material except as 
authorized pursuant to this section.
    (b) Except as otherwise provided and subject to the provisions of 
paragraphs (c) and (d) of this section, the Corporation may transfer 
radioactive material:
    (1) From one component of the Corporation to another;
    (2) To the Department;
    (3) To the agency in any Agreement State which regulates radioactive 
materials pursuant to an agreement with the Commission under Section 274 
of the Act, if the quantity transferred is not sufficient to form a 
critical mass;
    (4) To any person exempt from the licensing requirements of the Act 
and requirements in this part, to the extent permitted under the 
exemption;
    (5) To any person in an Agreement State, subject to the jurisdiction 
of that State, who has been exempted from the licensing requirements and 
regulations of that State, to the extent permitted under the exemption;
    (6) To any person authorized to receive the radioactive material 
under terms of a specific license or a general license or their 
equivalents issued by the Commission or an Agreement State;
    (7) To any person abroad pursuant to an export license issued under 
part 110 of this chapter; or
    (8) As otherwise authorized by the Commission in writing.
    (c) Before transferring radioactive material to any party specified 
in paragraph (b) of this section, the Corporation shall verify that the 
transferee is authorized to receive the type, form, and quantity of 
radioactive material to be transferred.
    (d) The following methods for the verification required by paragraph 
(c) of this section are acceptable:
    (1) The Corporation may have in its possession and read a current 
copy of the transferee's specific license or confirmation of 
registration. The Corporation shall retain a copy of each license or 
confirmation for 3 years from the date that it was obtained.
    (2) The Corporation may have in its possession a written 
confirmation by the transferee that the transferee is authorized by 
license or registration confirmation to receive the type, form, and 
quantity of special nuclear material to be transferred, specifying the 
license or registration confirmation number, issuing agency, and 
expiration date. The Corporation shall retain the written confirmation 
as a record for 3 years from the date of receipt of the confirmation;
    (3) For emergency shipments, the Corporation may accept a 
certification by the transferee that he or she is authorized by license 
or registration certification to receive the type, form, and quantity of 
special nuclear material to be transferred, specifying the license or 
registration number, issuing agency, and expiration date, provided that 
the oral confirmation is confirmed in writing within 10 days. The 
Corporation shall retain the written confirmation of the oral 
certification for 3 years from the date of receipt of the confirmation;
    (4) The Corporation may obtain other sources of information compiled 
by a reporting service from official records of the Commission or the 
licensing agency of an Agreement State as to the identity of licensees 
and the scope and expiration dates of licenses and registrations. The 
Corporation shall retain the compilation of information as

[[Page 647]]

a record for 3 years from the date that it was obtained; or
    (5) When none of the methods of verification described in paragraphs 
(d) (1) to (4) of this section are readily available or when the 
Corporation desires to verify that information received by one of these 
methods is correct or up to date, the Corporation may obtain and record 
confirmation from the Commission or the licensing agency of an Agreement 
State that the transferee is licensed to receive the special nuclear 
material. The Corporation shall retain the record of confirmation for 3 
years from the date the record is made.



Sec. 76.85  Assessment of accidents.

    The Corporation shall perform an analysis of potential accidents and 
consequences to establish the basis for limiting conditions for 
operation of the plant with respect to the potential for releases of 
radioactive material. Special attention must be directed to assurance 
that plant operation will be conducted in a manner to prevent or to 
mitigate the consequences from a reasonable spectrum of postulated 
accidents which include internal and external events and natural 
phenomena in order to ensure adequate protection of the public health 
and safety. Plant operating history relevant to the assessment should be 
included. In performing this assessment, the full range of operations 
should be considered including, but not necessarily limited to, 
operation at the maximum capacity contemplated. The assessment must be 
performed using an expected release rate resulting from anticipated 
operational occurrences and accidents with existing systems and 
procedures intended to mitigate the release consequences, along with 
site characteristics, including meteorology, to evaluate the offsite 
radiological consequences.



Sec. 76.87  Technical safety requirements.

    (a) The Corporation shall establish technical safety requirements. 
In establishing the requirements, the Corporation shall consider the 
analyses and results of the safety analysis report submitted pursuant to 
Sec. 76.35.
    (b) The format for the technical safety requirements must be 
appropriate for each individual requirement.
    (c) Appropriate references to established procedures and/or 
equipment to address each of the following safety topics must be 
included in technical safety requirements:
    (1) Effects of natural phenomena;
    (2) Building and process ventilation and offgas;
    (3) Criticality prevention;
    (4) Fire prevention;
    (5) Radiation protection;
    (6) Radioactive waste management;
    (7) Maintenance;
    (8) Environmental protection;
    (9) Packaging and transporting nuclear materials;
    (10) Accident analysis;
    (11) Chemical safety;
    (12) Sharing of facilities, structures, systems and components;
    (13) Utilities essential to radiological safety; and
    (14) Operations.
    (d) Technical safety requirements must include items in the 
following categories:
    (1) Safety limits. (i) If any safety limit is exceeded, corrective 
action must be taken as stated in the response procedures associated 
with the technical safety requirements or the affected part of the 
process must be shut down unless this action would increase the risk to 
the health and safety of the public or plant personnel.
    (ii) If any safety limit is exceeded, the Corporation shall notify 
the Commission if required by Sec. 76.120, review the matter, and 
record the results of the review, including the cause of the condition 
and the basis for corrective action taken to preclude recurrence.
    (iii) The Corporation shall retain the record of the results of each 
review until the Commission no longer has certification authority.
    (2) Limiting control settings. (i) Where a limiting control setting 
is specified for a variable on which a safety limit has been placed, the 
setting must be so chosen that protective action, either automatic or 
manual, will correct the abnormal situation before a safety limit is 
exceeded. If, during operation,

[[Page 648]]

the automatic alarm or protective devices do not function as required, 
appropriate action must be taken to maintain the variables within the 
limiting control-setting values and to repair promptly the automatic 
devices or to shut down the affected part of the process.
    (ii) If, during operation, an automatic alarm or protective device 
does not function as required, the Corporation shall notify the 
Commission if required by 76.120, review the matter, and record the 
results of the review, including the cause of the condition and the 
basis for corrective action taken to preclude recurrence.
    (iii) The Corporation shall retain the record of the results of each 
review until the Commission no longer has certification authority.
    (3) Limiting conditions for operation. When a limiting condition for 
operation of any process step in the system is not met, the Corporation 
shall shut down that part of the operation or follow any remedial action 
permitted by the technical safety requirements until the condition can 
be met.
    (i) If a limiting condition for operation of any process step in the 
system is not met, the Corporation shall notify the Commission if 
required by Sec. 76.120, review the matter, and record the results of 
the review, including the cause of the condition and the basis for 
corrective action taken to preclude recurrence.
    (ii) The Corporation shall retain the record of the results of each 
review until the Commission no longer has certification authority.
    (4) Design features. Design features to be included are those 
systems, components, or structures of the plant which, if altered or 
modified, would have a significant effect on safety and are not covered 
in categories described in paragraphs (d) (1), (2), and (3) of this 
section.
    (5) Surveillance requirement.
    (6) Administrative controls.



Sec. 76.89  Criticality accident requirements.

    (a) The Corporation must maintain and operate a criticality 
monitoring and audible alarm system meeting the requirements of 
paragraph (b) of this section in all areas of the facility. The 
Corporation may describe for the approval of the Commission defined 
areas to be excluded from the monitoring requirement. This submittal 
must describe the measures that will be used to ensure against 
criticality, including kinds and quantities of material that will be 
permitted and measures that will be used to control those kinds and 
quantities of material.
    (b) The system must detect and annunciate a criticality that 
produces an absorbed dose in soft tissue of 20 rads of combined neutron 
and gamma radiation at an unshielded distance of 2 meters from the 
reacting material within 1 minute. Coverage of all monitored areas must 
be provided by two detectors.



Sec. 76.91  Emergency planning.

    The Corporation shall establish, maintain, and be prepared to follow 
a written emergency plan. The emergency plan submitted under Sec. 
76.35(f) must include the following information:
    (a) Plant description. A brief description of the plant and area 
near the plant site.
    (b) Types of accidents. An identification of each type of 
radioactive materials accident for which protective actions may be 
needed.
    (c) Classification of accidents. A system for classifying accidents 
as alerts or site area emergencies.
    (d) Detection of accidents. Identification of the means of detecting 
each type of accident in a timely manner.
    (e) Mitigation of consequences. A brief description of the means and 
equipment for mitigating the consequences of each type of accident, 
including those provided to protect workers onsite, and a description of 
the program for maintaining the equipment.
    (f) Assessment of releases. A brief description of the methods and 
equipment to assess releases of radioactive materials.
    (g) Responsibilities. A brief description of the responsibilities of 
all individuals supporting emergency response should an accident occur, 
including identification of personnel responsible for promptly notifying 
offsite response organizations and the NRC, as well as a

[[Page 649]]

brief description of responsibilities for developing, maintaining, and 
updating the plan.
    (h) Notification and coordination. A commitment to and a brief 
description of the means to promptly notify offsite response 
organizations, including the request for offsite assistance and medical 
assistance for the treatment of contaminated injured onsite workers when 
appropriate. A control point must be established. The notification and 
coordination must be planned so that unavailability of some personnel, 
parts of the plant, and some equipment does not prevent the notification 
and coordination. The Corporation shall also commit to notify the NRC 
Operations Center immediately after notification of the appropriate 
offsite response organizations and not later than 1 hour after the 
Corporation declares an emergency. These reporting requirements do not 
supersede or release the Corporation from complying with the 
requirements under the Emergency Planning and Community Right-to-Know 
Act of 1986, Title III, Public Law 99-499, or other State or Federal 
reporting requirements.
    (i) Information to be communicated. A brief description of the plant 
status, radioactive releases, and recommended protective actions, if 
necessary, to be provided to offsite response organizations and to the 
NRC.
    (j) Training. A brief description of the frequency, performance 
objectives, and plans for the training that the Corporation will provide 
workers on how to respond to an emergency including any special 
instructions, briefings, and orientation tours the Corporation would 
offer to fire, police, medical, and other emergency personnel. The 
training must familiarize personnel with site-specific emergency 
procedures. The training must also prepare site personnel for their 
responsibilities for the accident scenarios postulated as most probable 
for the specific site, including the use of team training for these 
accident scenarios.
    (k) Safe shutdown. A brief description of the means of restoring the 
plant to a safe condition after an accident.
    (l) Exercises. Provisions for conducting quarterly communications 
checks with offsite response organizations and biennial onsite exercises 
to test response to simulated emergencies. Quarterly communications 
checks with offsite response organizations must include the check and 
update of all necessary telephone numbers. The Corporation shall invite 
offsite response organizations to participate in the biennial exercises. 
Participation of offsite response organizations in biennial exercises, 
although recommended, is not required. Exercises must use accident 
scenarios postulated as most probable for the specific site and the 
accident scenarios must not be made known to most exercise participants. 
The Corporation shall critique each exercise using individuals that do 
not have direct implementation responsibility for the plan. Critiques of 
exercises must evaluate the appropriateness of the plan, emergency 
procedures, facilities, equipment, training of personnel, and overall 
effectiveness of the response. Deficiencies found by the critiques must 
be corrected.
    (m) Hazardous chemicals. Confirmation that the Corporation has met 
its responsibilities under the Emergency Planning and Community Right-
to-Know Act of 1986, Title III, Public Law 99-499, if applicable to the 
Corporation's activities at the proposed place of use of the special 
nuclear material.
    (n) Comment from offsite response organizations. The Corporation 
shall allow the offsite response organizations that are expected to 
respond in case of an accident 60 days to comment on the emergency plan 
before submitting it to NRC. The Corporation shall provide any comments 
received within the 60 days to the NRC with the emergency plan.
    (o) Changes to emergency plan. The Corporation may make changes to 
the emergency plan without prior Commission approval if the changes do 
not decrease the effectiveness of the plan. The Corporation shall 
furnish these changes to the NRC in accordance with Sec. 76.5 and to 
affected offsite response organizations within 6 months after the change 
is made.

[59 FR 48960, Sept. 23, 1994, as amended at 64 FR 44650, Aug. 17, 1999]

[[Page 650]]



Sec. 76.93  Quality assurance.

    The Corporation shall establish, maintain, and execute a quality 
assurance program satisfying each of the applicable requirements of ASME 
NQA-1-1989, ``Quality Assurance Program Requirements for Nuclear 
Facilities,'' or satisfying acceptable alternatives to the applicable 
requirements. The Corporation shall execute the criteria in a graded 
approach to an extent that is commensurate with the importance to 
safety.



Sec. 76.95  Training.

    A training program must be established, implemented, and maintained 
for individuals relied upon to operate, maintain, or modify the GDPs in 
a safe manner. The training program shall be based on a systems approach 
to training that includes the following:
    (a) Systematic analysis of the jobs to be performed.
    (b) Learning objectives derived from the analysis which describe 
desired performance after training.
    (c) Training design and implementation based on the learning 
objectives.
    (d) Evaluation of trainee mastery of the objectives during training.
    (e) Evaluation and revision of the training based on the performance 
of trained personnel in the job setting.



                    Subpart E_Safeguards and Security



Sec. 76.111  Physical security, material control and accounting,
and protection of certain information.

    Nuclear Regulatory Commission regulations that will be used for 
certification of the Corporation \2\ for physical security and material 
control and accounting are contained in title 10 of the Code of Federal 
Regulations as described in this subpart. The regulations referenced in 
this subpart contain requirements for physical security and material 
control and accounting for formula quantities of strategic special 
nuclear material (Category I), special nuclear material of moderate 
strategic significance (Category II), and special nuclear material of 
low strategic significance (Category III), and for protection of 
Restricted Data, National Security Information, Safeguards Information, 
and information designated by the U.S. Department of Energy as 
Unclassified Controlled Nuclear Information.
---------------------------------------------------------------------------

    \2\ For the purpose of this subpart, the terms ``licensee'' or 
``license'' used in parts 70, 73, and 74 of this chapter, mean, 
respectively, the Corporation, or the certificate of compliance or 
approved compliance plan.

[62 FR 6671, Feb. 12, 1997]



Sec. 76.113  Formula quantities of strategic special nuclear material
--Category I.

    (a) The requirements for material control and accounting for formula 
quantities of strategic special nuclear material (Category I) are 
contained in Sec. Sec. 74.11, 74.13, 74.15, 74.17, 74.19, 74.51, 74.53, 
74.55, 74.57, 74.59, 74.81, and 74.82 of this chapter.
    (b) The requirements for physical security for formula quantities of 
strategic special nuclear material (Category I) are contained in 
Sec. Sec. 70.22(h), 73.20, 73.40, 73.45, 73.46, 73.70, and 73.71.
    (c) The requirements for the protection of Safeguards Information 
pertaining to formula quantities of strategic special nuclear material 
(Category I) are contained in Sec. Sec. 73.21 and 73.22 of this 
chapter. Information designated by the U.S. Department of Energy (DOE) 
as Unclassified Controlled Nuclear Information must be protected in 
accordance with DOE requirements.
    (d) The Corporation may neither transport Category I material 
offsite nor deliver Category I material to a carrier for transport 
offsite.

[59 FR 48960, Sept. 23, 1994, as amended at 62 FR 6671, Feb. 12, 1997; 
67 FR 78149, Dec. 23, 2002; 73 FR 63581, Oct. 24, 2008]



Sec. 76.115  Special nuclear material of moderate strategic 
significance--Category II.

    (a) The requirements for material control and accounting for special 
nuclear material of moderate strategic significance (Category II) are 
contained in Sec. Sec. 74.11. 74.13, 74.15, 74.17, 74.19, 74.41, 74.43, 
74.45, 74.81, and 74.82 of this chapter.
    (b) The requirements for physical security for special nuclear 
material of

[[Page 651]]

moderate strategic significance (Category II) are contained in 
Sec. Sec. 73.67, and 73.71 of this chapter.
    (c) The Corporation may neither transport Category II material 
offsite nor deliver Category II material to a carrier for transport 
offsite.
    (d) The requirements for the protection of Safeguards Information 
pertaining to special nuclear material of moderate strategic 
significance--Category II are contained in Sec. Sec. 73.21 and 73.22 of 
this chapter. Information designated by the U.S. Department of Energy 
(DOE) as Unclassified Controlled Nuclear Information must be protected 
in accordance with DOE requirements.

[59 FR 48960, Sept. 23, 1994, as amended at 67 FR 78149, Dec. 23, 2002; 
73 FR 63581, Oct. 24, 2008]



Sec. 76.117  Special nuclear material of low strategic significance
--Category III.

    (a) The requirements for material control and accounting for special 
nuclear material of low strategic significance (Category III) are 
contained in Sec. Sec. 74.11, 74.13, 74.15, 74.17, 74.19, 74.33, 74.81, 
and 74.82 of this chapter. However, inventories of uranium outside of 
the enrichment processing equipment conducted at least every 370 days 
are deemed to satisfy the requirements of Sec. 74.19(c).
    (b) The requirements for physical security for special nuclear 
material of low strategic significance (Category III) are contained in 
Sec. Sec. 73.67, 73.71, and 73.74 of this chapter.
    (c) The requirements for the protection of Safeguards Information 
pertaining to special nuclear material of low strategic significance--
Category III are contained in Sec. Sec. 73.21 and 73.22 of this 
chapter. Information designated by the U.S. Department of Energy (DOE) 
as Unclassified Controlled Nuclear Information must be protected in 
accordance with DOE requirements.

[59 FR 48960, Sept. 23, 1994, as amended at 67 FR 78149, Dec. 23, 2002; 
73 FR 63581, Oct. 24, 2008]



Sec. 76.119  Security facility approval and safeguarding of National
Security Information and Restricted Data.

    The requirements for security facility approval and for safeguarding 
of classified matter are contained in part 95 of this chapter. For the 
purpose of this subpart, the term ``licensee'' or ``license'' used in 
part 95 of this chapter means, respectively, the corporation, or the 
certificate of compliance or approved compliance plan.



                    Subpart F_Reports and Inspections



Sec. 76.120  Reporting requirements.

    (a) Immediate report. The Corporation shall notify the NRC 
Operations Center \3\ within 1 hour after discovery of:
---------------------------------------------------------------------------

    \3\ The commercial telephone number for the NRC Operations Center is 
(301) 816-5100 or (301) 951-0550, FAX (301) 816-5151.
---------------------------------------------------------------------------

    (1) A criticality event;
    (2) Any loss, other than normal operating loss, of special nuclear 
material;
    (3) Any theft or unlawful diversion of special nuclear material 
which the Corporation is authorized to possess or any incident in which 
an attempt has been made or is believed to have been made to commit a 
theft or unlawful diversion of special nuclear material; or
    (4) An emergency condition that has been declared an alert or site 
area emergency.
    (b) Four-hour report. The Corporation shall notify the NRC 
Operations Center as soon as possible but not later than 4 hours after 
discovery of an event \4\ that prevents immediate protective actions 
necessary to avoid releases or exposures to radiation or radioactive 
materials that could exceed regulatory limits.
---------------------------------------------------------------------------

    \4\ Events may include fires, explosions, radiological releases, 
etc.
---------------------------------------------------------------------------

    (c) Twenty-four hour report. The Corporation shall notify the NRC 
Operations Center within 24 hours after the discovery of any of the 
following events involving radioactive material:
    (1) An unplanned contamination event that:
    (i) Requires access to the contaminated area, by workers or the 
public, to be restricted for more than 24 hours by imposing additional 
radiological controls or by prohibiting entry into the area;

[[Page 652]]

    (ii) Involves a quantity of material greater than five times the 
lowest annual limit on intake specified in appendix B to Sec. Sec. 
20.1001 through 20.2402 of 10 CFR part 20 for the material; and
    (iii) Causes access to the contaminated area to be restricted for 
any reason other than to allow isotopes with a half-life of less than 24 
hours to decay prior to decontamination.
    (2) An event in which equipment is disabled or fails to function as 
designed when:
    (i) The equipment is required by a Technical Safety Requirement to 
prevent releases, prevent exposures to radiation and radioactive 
materials exceeding specified limits, mitigate the consequences of an 
accident, or restore this facility to a preestablished safe condition 
after an accident;
    (ii) The equipment is required by a Technical Safety Requirement to 
be available and operable and either should have been operating or 
should have operated on demand; and
    (iii) No redundant equipment is available and operable to perform 
the required safety function.
    (3) An event that requires unplanned medical treatment at a medical 
facility of an individual with radioactive contamination on the 
individual's clothing or body.
    (4) A fire or explosion damaging any radioactive material or any 
device, container, or equipment containing radioactive material when:
    (i) The quantity of material involved is greater than five times the 
lowest annual limit on intake specified in appendix B to Sec. Sec. 
20.1001 through 20.2402 of 10 CFR part 20 for the material; and
    (ii) The damage affects the integrity of the radioactive material or 
its container.
    (d) Preparation and submission of reports. Reports made by the 
Corporation in response to the requirements of this section must be made 
as follows:
    (1) Operations Center reports. The Corporation shall make reports 
required by paragraphs (a), (b), and (c) of this section by telephone to 
the NRC Operations Center. To the extent that the information is 
available at the time of notification, the information provided in these 
reports must include:
    (i) The caller's name and call back telephone number;
    (ii) A description of the event, including date and time;
    (iii) The exact location of the event;
    (iv) The isotopes, quantities, and chemical and physical form of the 
material involved;
    (v) Any personnel radiation exposure data available; and
    (vi) A description of any actions taken in response to the event.
    (2) Written report. A report required by paragraph (a), (b) or (c) 
of this section must be followed by a written report within 30 days of 
the initial report. Written reports prepared pursuant to other 
regulations may be submitted to fulfill this requirement if the reports 
contain all of the necessary information and the appropriate 
distribution is made. These written reports must be sent to the NRC by 
an appropriate method listed in Sec. 76.5. The reports must include the 
following information:
    (i) A description of the event, including the probable cause and the 
manufacturer and model number (if applicable) of any equipment that 
failed or malfunctioned;
    (ii) The exact location of the event;
    (iii) A description of isotopes, quantities and chemical and 
physical form of the material involved;
    (iv) The date and time of the event;
    (v) The causes, including the direct cause, the contributing cause, 
and the root cause;
    (vi) Corrective actions taken or planned and the results of any 
evaluations or assessments;
    (vii) The extent of exposure of individuals to radiation or to 
radioactive materials without identification of individuals by name; and
    (viii) Lessons learned from the event.

[59 FR 48960, Sept. 23, 1994, as amended at 68 FR 58822, Oct. 10, 2003]



Sec. 76.121  Inspections.

    (a) The Corporation shall afford to the Commission opportunity to 
inspect the premises and plants under the Corporation's control where 
radioactive material is used, produced, or stored.
    (b) The Corporation shall make available to the Commission for 
inspection

[[Page 653]]

records kept pertaining to receipt, possession, use, acquisition, 
import, export, or transfer of radioactive material.
    (c)(1) The Corporation shall provide rent-free office space for the 
exclusive use of Commission inspection personnel upon request by the 
Director, Office of Nuclear Material Safety and Safeguards, or the NRC 
Region III Administrator. Heat, air conditioning, light, electrical 
outlets, and janitorial services must be furnished by the Corporation. 
The office must be convenient to and have full access to the plant, and 
must provide the inspector both visual and acoustic privacy.
    (2) The space provided must be adequate to accommodate the NRC 
resident inspection staff, a part-time secretary, and transient NRC 
personnel. Space must be generally commensurate with other office 
facilities at the site. The office space that is provided must be 
subject to the approval of the Director, Office of Nuclear Material 
Safety and Safeguards, or the NRC Region III Office. All furniture, 
supplies, and communication equipment will be furnished by the 
Commission.
    (3) The Corporation shall afford any NRC resident inspector assigned 
to that site or other NRC inspectors identified by the Director, Office 
of Nuclear Material Safety and Safeguards, or the NRC Region III 
Administrator, as likely to inspect the plant, immediate, unfettered 
access equivalent to access provided regular plant employees, following 
proper identification and compliance with applicable access control 
measures for security, radiological protection, and personal safety.



Sec. 76.123  Tests.

    The Corporation shall perform, or permit the Commission to perform, 
any tests the Commission deems appropriate or necessary for 
administration of the requirements in this part. These tests include 
tests of:
    (a) Radioactive material;
    (b) Facilities where radioactive material is utilized, produced or 
stored;
    (c) Radiation detection and monitoring instruments; and
    (d) Other equipment and devices used in connection with the 
production, utilization, or storage of radioactive material.



                          Subpart G_Enforcement



Sec. 76.131  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of:
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended;
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under Section 234 of the Atomic Energy Act of 
1954, as amended, or under Section 1312(e) of the Atomic Energy Act of 
1954, as amended, and Section 206 of the Energy Reorganization Act of 
1974, as amended, for violations of:
    (1) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, 109, or 
1701 of the Atomic Energy Act of 1954, as amended;
    (2) Section 206 of the Energy Reorganization Act;
    (3) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1) of this section;
    (4) Any term, condition, or limitation of any certificate of 
compliance or approved compliance plan issued under the sections 
specified in paragraph (b)(1) of this section.

[62 FR 6671, Feb. 12, 1997]



Sec. 76.133  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
Section 161b or 161i of the Act. For purposes of Section 223, all the 
regulations in part 76 are issued under Section 161b or 161i except for 
the sections listed in paragraph (b) of this section.
    (b) The regulations in part 76 that are not issued under Section 
161b or 161i for the purposes of Section 223 are as follows: Sec. Sec. 
76.1, 76.2, 76.4, 76.5, 76.6, 76.23, 76.33, 76.35, 76.37, 76.39, 76.41, 
76.43, 76.45, 76.53, 76.55, 76.60, 76.62, 76.64, 76.70, 76.72, 76.131, 
and 76.133.

[[Page 654]]



PART 81_STANDARD SPECIFICATIONS FOR THE GRANTING OF PATENT LICENSES
--Table of Contents



                           General Provisions

Sec.
81.1 Purpose.
81.2 Definitions.
81.3 Communications.
81.4 Interpretations.
81.8 Information collection requirements: OMB approval.

             NRC-Owned Inventions--Patents and Applications

81.10 Authority.
81.11 Policy.
81.13 Publication of NRC inventions available for licensing.
81.20 Nonexclusive licenses.
81.30 Limited exclusive licenses.
81.31 Selection of an exclusive licensee.
81.32 Terms of exclusive license grant.
81.35 Notices to public of exclusive licenses.
81.40 Contents of a license application.
81.50 Additional licenses.
81.51 Appeals.
81.52 Appeals Board.
81.53 Review by the Board.

    Authority: Atomic Energy Act of 1954, secs. 156, 161 (42 U.S.C. 
2186, 2201); Energy Reorganization Act of 1974, sec. 201 (42 U.S.C. 
5841); 44 U.S.C. 3504 note.

    Source: 38 FR 7318, Mar. 20, 1973, unless otherwise noted.

                           General Provisions



Sec. 81.1  Purpose.

    The regulations of this part establish the standard specifications 
for the issuance of licenses to rights in inventions covered by patents 
or patent applications vested in the United States of America, as 
represented by or in the custody of the Commission and other patents in 
which the Commission has the right to accord or require the grant of 
licenses.

[40 FR 8793, Mar. 3, 1975]



Sec. 81.2  Definitions.

    As used in this part:
    (a) Act means the Atomic Energy Act of 1954 (68 Stat. 619), 
including any amendments thereto;
    (b) Commission means the Nuclear Regulatory Commission as 
established by the Act, or its duly authorized designee. The Assistant 
General Counsel for Patents is the designee of the Commission under this 
subpart;
    (c) NRC invention means an invention covered by a U.S. patent or 
patent application that is vested in the Government of the United 
States, as represented by or in the custody of the Commission, or in 
which the Government of the United States of America, as represented by 
the Commission, has the right to accord or require the grant of licenses 
where such invention is designated by the Commission as appropriate for 
the grant of a nonexclusive or exclusive license; and
    (d) To the point of practical application means to manufacture in 
the case of composition, machine or product, to practice in the case of 
a process, or to operate in the case of a machine, under such conditions 
as to establish that the invention is being worked and that its benefits 
are reasonably accessible to the public.
    (e) NRC foreign invention means an invention covered by a patent, or 
an application for a patent, issued by a government or authority of a 
country other than the United States that is vested in the Government of 
the United States, as represented by the Commission.

[38 FR 7318, Mar. 20, 1973, as amended at 38 FR 8241, Mar. 30, 1973]



Sec. 81.3  Communications.

    All communications concerning the regulations in this part, 
including applications for licenses, should be sent to the NRC either by 
mail addressed to the U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; by hand delivery to the NRC's offices at 11555 Rockville 
Pike, Rockville, Maryland; or, where practicable, by electronic 
submission, for example, via Electronic Information Exchange, or CD-ROM. 
Electronic submissions must be made in a manner that enables the NRC to 
receive, read, authenticate, distribute, and archive the submission, and 
process and retrieve it a single page at a time. Detailed guidance on 
making electronic submissions can be obtained by visiting the NRC's Web 
site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing

[[Page 655]]

the Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. The guidance discusses, among 
other topics, the formats the NRC can accept, the use of electronic 
signatures, and the treatment of nonpublic information.

[68 FR 58823, Oct. 10, 2003, as amended at 74 FR 62685, Dec. 1, 2009; 80 
FR 74982, Dec. 1, 2015]



Sec. 81.4  Interpretations.

    Except as specifically authorized by the Commission in writing and 
by Sec. 81.53, no interpretation of the meaning of the regulations in 
this part by an officer or employee of the Commission other than a 
written interpretation by the General Counsel will be recognized to be 
binding upon the Commission.



Sec. 81.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0121.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 81.20, 81.32, and 81.40.

[55 FR 23422, June 8, 1990, as amended at 62 FR 52190, Oct. 6, 1997]

             NRC-Owned Inventions--Patents and Applications



Sec. 81.10  Authority.

    The regulations of this subpart governing the licensing or rights in 
NRC inventions are issued pursuant to the authority of the Commission 
under 42 U.S.C. 2186 (sec. 156 of the Act), 42 U.S.C. 2201g (sec. 161g. 
of the Act), and according to regulations issued by the Administrator of 
General Services pursuant to the Memorandum and Statement of Government 
Patent Policy issued by President Nixon on August 23, 1971 (36 FR 
16887).



Sec. 81.11  Policy.

    (a) The inventions covered by the U.S. patents and patent 
applications vested in the Government of the United States of America, 
as represented by or in the custody of the Commission, normally will 
best serve the public interest when they are developed to the point of 
practical application and made available to the public in the shortest 
time possible.
    (b) The Commission generally prefers to make these inventions 
available to all interested parties through the granting of nonexclusive 
licenses. However, the Commission recognizes that to obtain commercial 
utilization of an invention, it may be necessary to grant an exclusive 
license for a limited period of time as an incentive for the investment 
of risk capital to achieve practical application of an invention.
    (c) Whenever the Commission deems it appropriate to grant an 
exclusive license, the license will be negotiated on terms and 
conditions most favorable to the interests of the public and the 
Government. In considering the accord of such a license, due weight will 
be given to assisting small business and minority business enterprises, 
as well as economically depressed, low income and labor surplus areas 
within the United States.
    (d) All licenses shall be by express written instruments. No license 
shall be granted or implied in an NRC invention except as provided for 
in these regulations or in patent rights articles under Commission 
procurement regulations, pursuant to the Act, or pursuant to any 
existing or future treaty or agreement between the United States and any 
foreign government or intergovernmental organization.
    (e) No grant of a license under this subpart shall be construed to 
confer upon any licensee any immunity from the antitrust laws or from 
liability for patent misuse, and the acquisition and use of rights 
pursuant to this subpart shall not be immunized from the operation of 
State or Federal law by reason of the source of the grant.

[[Page 656]]

    (f) No grant of a license under this subpart shall be construed to 
confer any authorization under chapters 4, 5, 6, 7, 8, 10, or any other 
chapter or section of the Act (42 U.S.C., sec. 2011-2296) for which 
separate application for a license must be made in accordance with the 
Act or other Commission regulations.



Sec. 81.13  Publication of NRC inventions available for licensing.

    (a) The Commission will have published periodically a list of the 
NRC inventions available for licensing under this subpart in the Federal 
Register, the U.S. Patent Office Official Gazette, and in one other 
publication which it is determined will best serve the public interest 
and, where advisable, in other publications.
    (b) Interested persons may obtain copies of such lists by 
communicating with the Commission, Washington, DC 20555. Copies of U.S. 
patents may be obtained from the U.S. Patent Office. Copies of U.S. 
patent application specifications, or microfiche reproductions thereof, 
may be secured at reasonable cost from the National Technical 
Information Service (NTIS) or from the U.S. Patent Office with 
Commission approval.

[38 FR 7318, Mar. 20, 1973, as amended at 40 FR 8793, Mar. 3, 1975]



Sec. 81.20  Nonexclusive licenses.

    (a) NRC inventions will normally be made available for the grant of 
nonexclusive licenses to responsible applicants who will practice the 
invention and make its benefits reasonably accessible to the public.
    (1) The nonexclusive license will be revocable, at the option of the 
Commission, if the licensee does not comply with all the terms and 
conditions of the license agreement.
    (2) The duration of the license shall be for a specified period and/
or such additional period as may be provided for in the license 
agreement.
    (3) The license shall require the licensee to bring the invention to 
the point of practical application within a period specified in the 
license agreement, or as the period may be extended by the Commission, 
and then to continue to make the benefits of the invention reasonably 
accessible to the public.
    (4) The license shall be granted for all of the fields of use of the 
invention, or only such fields of use as may be specified in the license 
agreement, and throughout the United States of America, its territories 
and possessions, Puerto Rico, and the District of Columbia or in any 
lesser geographic portion thereof as may be specified in the license 
agreement.
    (5) The licensee shall be required to submit periodic reports on his 
efforts to bring the invention to a point of practical application and 
the extent to which he continues to make the benefits of the invention 
reasonably accessible to the public. Unless otherwise specified in the 
license, such periodic reports will be required annually prior to the 
anniversary date of the grant of the license. The reports shall contain 
information within the licensee's knowledge, or which the licensee may 
acquire under normal business practices, pertaining to the commercial 
use being made of the invention, and other information which the 
Commission may determine to be pertinent to the licensing activity of 
the Commission and specified in the license agreement.
    (6) Normally a royalty shall not be charged U.S. citizens and U.S. 
corporations for nonexclusive licenses on NRC inventions.
    (7) The license may extend to wholly-owned subsidiaries of the 
licensee but shall be nonassignable, or otherwise nontransferable, 
without approval of the Commission.
    (8) The Commission may revoke the license (i) for failure of the 
licensee to bring the invention to the point of practical application or 
to continue to make the benefits of the invention reasonably accessible 
to the public, (ii) if the licensee defaults in making any periodic 
report required by the license, or (iii) if the licensee commits any 
breach of any covenant or agreement therein contained, or (iv) if the 
licensee willfully makes, or has made, a false statement of a material 
fact or omitted a material fact in the license application submitted 
pursuant to Sec. 81.40(a) or in any report required by the license 
agreement.

[[Page 657]]

    (9) The Commission may restrict the licensee to the particular 
fields of use and/or geographical areas in which the licensee has 
brought the invention to the point of practical application and continue 
to make the benefits of the invention reasonably accessible to the 
public.
    (10) Before revoking or restricting any license granted pursuant to 
this subpart, the Commission shall mail to the licensee and any 
sublicensee of record, at the last address filed with the Commission, a 
written notice of the Commission's intention to revoke or restrict the 
license, and the licensee and any sublicensee shall be allowed thirty 
(30) days after the mailing of such notice, or within such period as may 
be granted by the Commission, to remedy any breach of any covenant or 
agreement as referred to in paragraph (a)(8)(iii) of this section, or to 
show cause why the license should not be revoked or restricted.
    (11) Subject to the rights reserved to the Government in this 
section, the licensee shall be granted the nonexclusive rights to make, 
use, and/or sell the invention in accordance with the terms and 
conditions specified in the license agreement.
    (12) The license may be subject to such other terms and conditions 
as the Commission may deem in the public interest.



Sec. 81.30  Limited exclusive licenses.

    (a) An NRC invention may be made available for the grant of a 
limited exclusive license provided that:
    (1) The invention has been published as available for licensing 
pursuant to Sec. 81.13 for a period of at least six (6) months.
    (2) The Commission has determined that (i) the invention may be 
brought to the point of practical application in certain fields of use 
or in certain geographical locations by exclusive licensing, (ii) the 
desired practical application has not been achieved under any 
nonexclusive license granted on the invention, and (iii) the desired 
practical application is not likely to be achieved expeditiously in the 
public interest under a nonexclusive license or as a result of further 
Government-funded research or development.
    (3) Notice of the selection of a prospective licensee to be granted 
a limited exclusive license of a specified duration and scope shall have 
been transmitted to the Attorney General of the United States and shall 
have been published for at least sixty (60) days in the Federal Register 
with a statement advising of the rights of license applicants or third 
parties to apply for nonexclusive licenses or bring information to the 
attention of the Commission under the next paragraph.
    (4) After expiration of the period in paragraph (a)(3) of this 
section, the Commission has determined (i) that no applicant for a 
nonexclusive license has brought or will bring the invention to the 
point of practical application as specified in the prospective exclusive 
license within a reasonable period under a nonexclusive license, and 
(ii) that the granting of the license would be in the public interest 
and not be inconsistent with the Act after consideration of all the 
facts and any written evidence and argument which third parties may 
present to the Commission within sixty (60) days of the publication of 
the notices of the selection of the licensee under paragraph (a)(3) of 
this section.
    (5) The Commission shall record and make available for public 
inspection, upon request, all decisions and the basis thereof under this 
section.



Sec. 81.31  Selection of an exclusive licensee.

    An exclusive licensee will be selected by the Commission on bases 
consistent with the policy set forth in Sec. 81.11 of this subpart in 
accordance with the procedures herein, based upon the information 
supplied to the Commission in a license application under Sec. 81.40. 
Consideration will be given to: (a) The capabilities of the applicant to 
further the technical and market development of the invention to bring 
the same to the point of practical application, (b) the applicant's plan 
to undertake development of the invention, (c) the projected impact on 
competition, (d) the benefit to the Government and the public, as well 
as (e) assistance to small business and minority business enterprises 
and economically depressed, low income and labor surplus areas, and (f)

[[Page 658]]

whether the applicant is a U.S. citizen or corporation.



Sec. 81.32  Terms of exclusive license grant.

    (a) NRC inventions may be made available for the grant of limited 
exclusive licenses to responsible applicants who will bring the 
invention to the point of practical application and make its benefits 
reasonably accessible to the public.
    (1) The license may be granted for all or less than all fields of 
use of the invention, and throughout the United States of America, its 
territories and possessions, Puerto Rico, and the District of Columbia, 
or any lesser geographical portion thereof.
    (2) The duration of the license will be negotiated and shall include 
(i) a period of exclusivity specified in the license, which shall be 
related to the period necessary to provide a reasonable incentive for 
the licensee to invest the necessary risk capital to bring the invention 
to the point of practical application and which shall not exceed 5 years 
or be extended unless the Commission determines on the basis of a 
written submission supported by a factual showing that a longer period 
is reasonably necessary to permit the licensee to enter the market and 
recoup his investment in bringing the invention to the point of 
practical application; and (ii) a terminal portion, sufficient to make 
the invention reasonably available for the granting of nonexclusive 
licenses under Sec. 81.20, during which the licensee may have a 
nonexclusive license if the licensee continues to make the invention 
reasonably accessible to the public.
    (3) The license shall require the licensee to bring the invention to 
the point of practical application within a period specified in the 
license agreement, or, subject to the approval of the Commission, within 
a longer period, and then to continue to make the benefits of the 
invention reasonably accessible to the public.
    (4) The license shall require the licensee to expand a specified 
minimum sum of money and/or to take other specified action, within 
indicated periods as specified in the license, in an effort to bring the 
invention to the point of practical application. Reasonable royalties 
shall be charged by the Commission, as specified in the license 
agreement, unless the Commission determines that it would not be in the 
public interest to charge royalties.
    (5) The license shall be subject to an irrevocable, royalty-free 
right of the Government of the United States to practice and have 
practiced the invention by or on behalf of the Government of the United 
States and on behalf of any foreign Government or intergovernmental 
organization pursuant to any existing or future treaty or agreement with 
the United States.
    (6) The license shall reserve to the Commission the right to require 
the licensee to grant sublicenses to responsible applicants to practice 
the invention on terms that are reasonable under the circumstances, (i) 
to the extent that the invention is required for public use by 
governmental regulations, or (ii) as may be necessary to fulfill health 
or safety needs, or (iii) if the invention is useful in the production 
or utilization of special nuclear material or atomic energy and the 
licensing of such invention is of importance to effectuate the policies 
and purposes of the Act, (iv) for other public purposes as stipulated in 
the license agreement. In the event that the licensee and the Commission 
cannot agree upon reasonable terms for such sublicenses, the terms, 
including a reasonable royalty, may be fixed pursuant to the procedure 
set forth in section 157(c) of the Act.
    (7) Subject to the right reserved to the Government in paragraphs 
(a) (5) and (6) of this section, the licensee shall be granted the 
exclusive right to make, use, and/or sell the invention in accordance 
with the terms and conditions specified in the license agreement.
    (8) The license may extend to wholly owned subsidiaries of the 
licensee but shall be nonassignable and otherwise nontransferable 
without approval of the Commission, except assignment may be made, upon 
notice to the Commission, to successors of that part of the licensee's 
business to which the invention pertains.
    (9) An exclusive licensee may grant sublicenses under his license 
only with

[[Page 659]]

the approval of the Commission. Any sublicense or assignment granted by 
an exclusive licensee shall be subject to the terms and conditions of 
the exclusive license, including the rights retained by the Government 
thereunder, and a copy of each such sublicense or assignment shall be 
furnished to the Commission.
    (10) The license shall require the licensee to submit periodic 
reports on his efforts to achieve practical application of the invention 
and the extent to which he continues to make the benefits of the 
invention reasonably accessible to the public. Unless otherwise 
specified in the license, such reports will be required annually on the 
anniversary date of the grant of the license. The report shall contain 
information within the licensee's knowledge, or which the licensee may 
acquire under normal business practices, pertaining to the commercial 
use being made of the invention, and other information which the 
Commission may determine to be pertinent to the licensing activity of 
the Commission as is specified in the license agreement.
    (11) The Commission may modify or revoke the license (i) for failure 
of the licensee to bring the invention to the point of practical 
application within the period specified in the license agreement or to 
continue to make the benefits of the invention reasonably accessible to 
the public; (ii) if the licensee fails to expend the minimum sum of 
money or to take any other action specified in the license agreement 
within the periods specified in the license agreement in an effort to 
bring the invention to the point of practical application; (iii) if the 
licensee defaults in making any payments or periodic reports required by 
the license; or (iv) if the licensee commits any breach of any covenant 
or agreement therein contained; or (v) if the licensee willfully makes, 
or has made, a false statement of a material fact or willfully omitted a 
material fact in the license application submitted pursuant to Sec. 
81.40 or in any report required by the license agreement.
    (12) Before modifying or revoking any license granted pursuant to 
this subpart for any cause, the Commission shall mail to the licensee 
and any sublicensee of record at the last address filed with the 
Commission a written notice of the Commission's intention to modify or 
revoke the license, and the licensee and any sublicensee shall be 
allowed thirty (30) days after the mailing of such notice, or within 
such period as may be granted by the Commission, to remedy any breach of 
any covenant or agreement referred to in paragraph (a)(11)(iv) of this 
section or to show cause why the license should not be modified or 
revoked.
    (13) An exclusive licensee shall be granted the right to sue at his 
own expense any party who infringes the rights set forth in his license 
and covered by the licensed patent. The licensee may join the Government 
of the United States, upon consent of the Attorney General, as a party 
complainant in such suit, but without expense to the Government and the 
licensee shall pay costs and any final judgment or decree that may be 
rendered against the Government in such suit. The Government shall have 
an absolute right to intervene in any such suit at its own expense. The 
licensee shall be obligated to furnish promptly to the Government, upon 
request, copies of all pleadings and other papers filed in any such suit 
and of evidence adduced in proceedings relating to the licensed patent, 
including, but not limited to, negotiations or settlements and 
agreements settling claims by a licensee based on the licensed patent, 
and all other books, documents, papers, and records pertaining to such 
suit. If, as a result of any such litigation, the patent shall be 
declared invalid, the licensee shall have the right to surrender his 
license and be relieved from any further obligation thereunder.
    (14) A licensee may surrender his license at any time prior to 
termination of the license upon notice thereof to the Commission, and 
upon approval of the Commission, but the licensee shall not be relieved 
of the obligations thereunder without specific approval of the 
Commission.
    (15) The license may be subject to such other terms and conditions 
as the Commission may deem in the public interest.

[[Page 660]]



Sec. 81.35  Notices to public of exclusive licenses.

    The Commission will have published in the Federal Register notices 
of the granting, revocation, or modification in duration and/or scope, 
of limited exclusive licenses under these regulations. Such notices 
shall identify the invention and shall include, directly, or by 
reference to previous notice(s) in the Federal Register pursuant to 
Sec. 81.13 or Sec. 81.30(a)(3) the following:
    (a) Identification of the licensee.
    (b) Duration and scope of the exclusive license.
    (c) That such a license is being granted or revoked, or the nature 
of the modification of the license.
    (d) The effective date of the grant, modification, or revocation.



Sec. 81.40  Contents of a license application.

    (a) Nonexclusive license application. An application for a 
nonexclusive license under an NRC invention should be accompanied by a 
fee of ten dollars ($10) for processing the application and must include 
the following information:
    (1) Identification of the invention for which the license is 
desired, including the patent application serial number or the patent 
number, title, and date, if known, and any other identification of the 
invention;
    (2) Name and address of the person, company, or organization 
applying for a license and the citizenship or State of incorporation 
thereof;
    (3) Name and address of a representative of applicant to whom 
correspondence should be sent and any notices served;
    (4) Nature and type of applicant's business;
    (5) Identification of the source of applicant's information 
concerning the availability of a license on the invention;
    (6) Purpose for which the license is desired, and a brief 
description of applicant's plan to achieve that purpose;
    (7) A statement of the field and the field(s) of use in which 
applicant intends to practice the invention; and
    (8) A statement of the geographical area(s) in which the applicant 
will practice the invention.
    (b) Exclusive license application. An application for a limited 
exclusive license should include, in addition to the information 
indicated above for a nonexclusive license application, the following 
information:
    (1) Applicant's status, if any, in any one or more of the following 
categories:
    (i) Small business firm;
    (ii) Minority business enterprise;
    (iii) Location in a surplus labor area;
    (iv) Location in a low income area; and
    (v) Location in an economically depressed area.
    (2) A statement describing the time, expenditure, and other acts 
which the applicant considers necessary to bring the invention to a 
point of practical application, and the applicant's offer to invest that 
time and sum, and to perform such acts, if the license is granted.
    (3) A statement of applicant's capability to undertake the 
development and/or marketing required to bring the invention to the 
point of practical application.
    (4) A statement that contains applicant's best knowledge of the 
extent to which the invention is being practiced by private industry and 
the Government; and
    (5) Any other facts which the applicant believes to show it to be in 
the public interest for the Commission to grant an exclusive license 
rather than a nonexclusive license and that such exclusive license 
should be granted to the applicant.



Sec. 81.50  Additional licenses.

    Subject to any outstanding licenses, nothing in this subpart shall 
preclude the Commission from granting additional nonexclusive and 
limited exclusive licenses for inventions covered by this subpart when 
the Commission determines that to do so would provide for an equitable 
exchange of patent rights. The following exemplify circumstances wherein 
such licenses may be granted:
    (a) In consideration of the settlement of interferences;
    (b) In consideration of a release of any claims;

[[Page 661]]

    (c) In exchange for or as part of the consideration for a license 
under adversely held patent(s); or
    (d) In consideration for the settlement or resolution of any 
proceeding under the Act or other statute.



Sec. 81.51  Appeals.

    An applicant for a license, a licensee, or a third party who has 
participated under Sec. 81.30(a)(3) shall have the right to appeal in 
accordance with the appeal procedures of this subpart any decision of 
the Commission concerning the grant, denial, interpretation, 
modification, or revocation of a license under this subpart, by filing a 
notice of appeal with the Commission within thirty (30) days from the 
date of the mailing of a notice by the Commission of the decision or, if 
no such notice to the person desiring to appeal, then thirty (30) days 
from publication in the Federal Register of the facts which show such a 
decision. The notice of appeal shall specify the portion of the decision 
from which the appeal is taken, and the reasons why the decision is 
erroneous. A statement of fact and argument in the form of a brief in 
support of the appeal may be submitted with the notice of appeal or, if 
the appellant prefers, may be filed with the Commission within fifteen 
(15) days after the filing of the notice of appeal. If a statement of 
fact and argument in the form of a brief in support of the appeal is not 
submitted with the notice, the appellant shall state in the notice 
whether such a statement of fact and argument in the form of a brief in 
support of the appeal will be filed.



Sec. 81.52  Appeals Board.

    (a) NRC Invention Licensing Appeal Board. Upon notice of an appeal 
in accordance with Sec. 81.51, the Executive Director for Operations of 
the Nuclear Regulatory Commission will designate within thirty (30) days 
an Invention Licensing Appeal Board (hereinafter, Board) to decide such 
an appeal.
    (b) Composition of the Board. The Invention Licensing Appeal Board 
shall consist of three members having equal voting power, one of whom 
will be designated as Chairman.
    (c) Notice of designation of the Board. The Executive Director for 
Operations of the Nuclear Regulatory Commission will advise the 
appellant of the designation of the Board, its composition, and 
Chairman.

[40 FR 8793, Mar. 3, 1975]



Sec. 81.53  Review by the Board.

    (a) The Board shall determine the propriety of any decision 
concerning the grant, denial, interpretation, modification, or 
revocation of a license according to the policy and criteria of these 
regulations, including Sec. 81.11, on the record and evidence submitted 
by an appellant and the Commission to the Board.
    (b) A hearing may be requested by the Commission or an appellant 
within fifteen (15) days after the notice set forth under Sec. 
81.52(c). An appellant and the Commission shall be given a minimum of 
fifteen (15) days' notice of the time and place of a hearing. The 
Commission and the appellant shall have an opportunity to make oral 
arguments before the Board.
    (c) The Board shall make findings of fact and reach a conclusion 
with respect to the propriety of the decision of the Commission, which 
conclusion shall constitute the final action of the Commission.



PART 95_FACILITY SECURITY CLEARANCE AND SAFEGUARDING OF NATIONAL 
SECURITY INFORMATION AND RESTRICTED DATA--Table of Contents



                           General Provisions

Sec.
95.1 Purpose.
95.3 Scope.
95.5 Definitions.
95.7 Interpretations.
95.8 Information collection requirements: OMB approval.
95.9 Communications.
95.11 Specific exemptions.
95.13 Maintenance of records.

                            Physical Security

95.15 Approval for processing licensees and others for facility 
          clearance.
95.17 Processing facility clearance.
95.18 Key personnel.
95.19 Changes to security practices and procedures.
95.20 Grant, denial or termination of facility clearance.

[[Page 662]]

95.21 Withdrawal of requests for facility security clearance.
95.23 Termination of facility clearance.
95.25 Protection of National Security Information and Restricted Data in 
          storage.
95.27 Protection while in use.
95.29 Establishment of Restricted or Closed areas.
95.31 Protective personnel.
95.33 Security education.
95.34 Control of visitors.

                         Control of Information

95.35 Access to matter classified as National Security Information and 
          Restricted Data.
95.36 Access by representatives of the International Atomic Energy 
          Agency or by participants in other international agreements.
95.37 Classification and preparation of documents.
95.39 External transmission of documents and material.
95.41 External receipt and dispatch records.
95.43 Authority to reproduce.
95.45 Changes in classification.
95.47 Destruction of matter containing classified information.
95.49 Security of automatic data processing (ADP) systems.
95.51 Retrieval of classified matter following suspension or revocation 
          of access authorization.
95.53 Termination of facility clearance.
95.55 Continued applicability of the regulations in this part.
95.57 Reports.
95.59 Inspections.

                               Violations

95.61 Violations.
95.63 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 145, 161, 223, 234 (42 
U.S.C. 2165, 2201, 2273, 2282); Energy Reorganization Act of 1974, sec. 
201 (42 U.S.C. 5841); 44 U.S.C. 3504 note; E.O. 10865, as amended, 25 FR 
1583, 3 CFR, 1959-1963 Comp., p. 398; E.O. 12829, 58 FR 3479, 3 CFR, 
1993 Comp., p. 570; E.O. 12968, 60 FR 40245, 3 CFR, 1995 Comp., p. 391; 
E.O. 13526, 75 FR 707, 3 CFR, 2009 Comp., p. 298.

    Source: 45 FR 14483, Mar. 5, 1980, unless otherwise noted.

                           General Provisions



Sec. 95.1  Purpose.

    The regulations in this part establish procedures for obtaining 
facility security clearance and for safeguarding Secret and Confidential 
National Security Information and Restricted Data received or developed 
in conjunction with activities licensed, certified or regulated by the 
Commission. This part does not apply to Top Secret information because 
Top Secret information may not be forwarded to licensees, certificate 
holders, or others within the scope of an NRC license or certificate.

[62 FR 17690, Apr. 11, 1997, as amended at 68 FR 41222, July 11, 2003]



Sec. 95.3  Scope.

    The regulations in this part apply to licensees, certificate holders 
and others who may require access to classified National Security 
Information and/or Restricted Data and/or Formerly Restricted Data (FRD) 
that is used, processed, stored, reproduced, transmitted, transported, 
or handled in connection with a license or certificate or an application 
for a license or certificate, or other activities as the Commission may 
determine.

[70 FR 32227, June 2, 2005]



Sec. 95.5  Definitions.

    Access authorization means an administrative determination that an 
individual (including a consultant) who is employed by or an applicant 
for employment with the NRC, NRC contractors, agents, licensees and 
certificate holders, or other persons designated by the Executive 
Director for Operations, is eligible for a security clearance for access 
to classified information.
    Act means the Atomic Energy Act of 1954 (68 Stat. 919), as amended.
    Classified mail address means a mail address established for each 
facility approved by the NRC, to which all classified information for 
the facility is to be sent.
    Classified matter means documents or material containing classified 
information.
    Classified National Security Information means information that has 
been determined under E.O. 13526, as amended, or any predecessor or 
successor order to require protection against unauthorized disclosure 
and that is so designated.
    Classified shipping address means an address established for a 
facility, approved by the NRC to which classified

[[Page 663]]

material that cannot be transmitted as normal mail is to be sent.
    Closed area means an area that meets the requirements of the CSA, 
for the purpose of safeguarding classified material that, because of its 
size, nature, or operational necessity, cannot be adequately protected 
by the normal safeguards or stored during nonworking hours in approved 
containers.
    Cognizant Security Agency (CSA) means agencies of the Executive 
Branch that have been authorized by E.O. 12829 to establish an 
industrial security program for the purpose of safeguarding classified 
information under the jurisdiction of those agencies when disclosed or 
released or released to U.S. industry. These agencies are the Department 
of Defense, the department of Energy, the Central Intelligence Agency, 
and the Nuclear Regulatory Commission. A facility has a CSA which 
exercises primary authority for the protection of classified information 
at the facility. The CSA for the facility provides security 
representation for other government agencies with security interests at 
the facility. The Secretary of Defense has been as Executive Agent for 
the National Industrial Security Program.
    Combination lock means a three position, manipulation resistant, 
dial type lock bearing an Underwriters' Laboratories, Inc. certification 
that it is a Group 1 or Group IR unit.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    Facility (Security) Clearance (FCL) means an administrative 
determination that, from a security viewpoint, a facility is eligible 
for access to classified information of a certain category (and all 
lower categories).
    Foreign ownership, control, or influence (FOCI) means a foreign 
interest that has the power, direct or indirect, whether or not 
exercised, and whether or not exercisable through the ownership of a 
U.S. company's securities, by contractual arrangements or other means, 
to direct or decide matters affecting the management or operations of 
that company in a manner which may result in unauthorized access to 
classified information or may affect adversely the performance of 
classified contracts.
    Infraction means any knowing, willful, or negligent action contrary 
to the requirements of E.O. 13526, as amended, or any predecessor or 
successor order, or its implementing directives that does not comprise a 
``violation,'' as defined in this section.
    Intrusion alarm means a tamper-indicating electrical, electro-
mechanical, electro-optical, electronic or similar device which will 
detect unauthorized intrusion by an individual into a building, 
protected area, security area, vital area, or material access area, and 
alert guards or watchmen by means of actuated visible and audible 
signals.
    License means a license issued under 10 CFR parts 50, 52, 54, 60, 
63, 70, or 72.
    Material means chemical substance without regard to form; fabricated 
or processed item; or assembly, machinery or equipment.
    Matter means documents or material.
    National security means the national defense or foreign relations of 
the United States.
    Need-to-know means a determination made by an authorized holder of 
classified information that a prospective recipient requires access to 
specific classified information in order to perform or assist in a 
lawful and authorized governmental function under the cognizance of the 
Commission.
    NRC ``L'' access authorization means an access authorization granted 
by the Commission normally based on a national agency check with law and 
credit investigation (NACLC) or an access national agency check and 
inquiries investigation (ANACI)) conducted by the Office of Personnel 
Management.
    NRC ``Q'' access authorization means an access authorization granted 
by the Commission normally based on a single scope background 
investigation conducted by the Office of Personnel Management, the 
Federal Bureau of Investigation, or other U.S. Government agency that 
conducts personnel security investigations.
    Person means (1) any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
government agency other than the Commission or the Department of Energy 
(DOE), except that

[[Page 664]]

the DOE shall be considered a person to the extent that its facilities 
are subject to the licensing and related regulatory authority of the 
Commission pursuant to section 202 of the Energy Reorganization Act of 
1974 and sections 104, 105 and 202 of the Uranium Mill Tailings 
Radiation Control Act of 1978, any State or any political subdivision 
of, or any political entity within a State, any foreign government or 
nation or any political subdivision of any such government or nation, or 
other entity; and (2) any legal successor, representative, agent or 
agency of the foregoing.
    Protective personnel means guards or watchmen as defined in 10 CFR 
part 73 or other persons designated responsibility for the protection of 
classified matter.
    Restricted area means a controlled access area established to 
safeguard classified material, that, because of its size or nature, 
cannot be adequately protected during working hours by the usual 
safeguards, but that is capable of being stored during non-working hours 
in an approved repository or secured by other methods approved by the 
CSA.
    Restricted data means all data concerning design, manufacture or 
utilization of atomic weapons, the production of special nuclear 
material, or the use of special nuclear material in the production of 
energy, but shall not include data declassified or removed from the 
Restricted Data category pursuant to section 142 of the Act.
    Security area means a physically defined space containing classified 
matter and subject to physical protection and personnel access controls.
    Security container includes any of the following repositories:
    (1) A security filing cabinet--one that bears a Test Certification 
Label on the side of the locking drawer, inside wall adjacent to the 
locking drawer, or interior door plate, or is marked, ``General Services 
Administration Approved Security Container'' on the exterior of the top 
drawer or door.
    (2) A safe--burglar-resistive cabinet or chest which bears a label 
of the Underwriters' Laboratories, Inc., certifying the unit to be a TL-
15, TL-30, or TRTL-30, and has a body fabricated of not less than 1 inch 
of steel and a door fabricated of not less than 1\1/2\ inches of steel 
exclusive of the combination lock and bolt work; or bears a Test 
Certification Label on the inside of the door, or is marked ``General 
Services Administration Approved Security Container'' and has a body of 
steel at least \1/2\ inch thick, and a combination locked steel door at 
least 1 inch thick, exclusive of bolt work and locking devices; and an 
automatic unit locking mechanism.
    (3) A vault--a windowless enclosure constructed with walls, floor, 
roof, and door(s) that will delay penetration sufficient to enable the 
arrival of emergency response forces capable of preventing theft, 
diversion, damage, or compromise of classified information or matter, 
when delay time is assessed in conjunction with detection and 
communication subsystems of the physical protection system.
    (4) A vault-type room--a room that has a combination lock door and 
is protected by an intrusion alarm system that alarms upon the 
unauthorized penetration of a person anywhere into the room.
    (5) Other repositories that would provide comparable physical 
protection in the judgment of the Division of Facilities and Security.
    Security facility--any facility which has been approved by NRC for 
using, processing, storing, reproducing, transmitting or handling 
classified matter.
    Security reviews means aperiodic security reviews of cleared 
facilities conducted to ensure that safeguards employed by licensees and 
others are adequate for the protection of classified information.
    Supplemental protection means additional security procedures such as 
intrusion detection systems, security guards, and access control 
systems.
    Violation means any knowing, willful, or negligent action that could 
reasonably be expected to result in an unauthorized disclosure of 
classified information or any knowing, willful, or negligent action to 
classify or continue the classification of information contrary to the 
requirements of E.O. 12958,

[[Page 665]]

as amended, or its implementing directives.

[45 FR 14483, Mar. 5, 1980, as amended at 46 FR 58284, Dec. 1, 1981; 47 
FR 38683, Sept. 2, 1982; 48 FR 24320, June 1, 1983; 50 FR 36984, Sept. 
11, 1985; 55 FR 11575, Mar. 29, 1990; 55 FR 14379, Apr. 17, 1990; 59 FR 
48974, Sept. 23, 1994; 62 FR 17691, Apr. 11, 1997; 64 FR 15649, Apr. 1, 
1999; 70 FR 32227, June 2, 2005; 72 FR 49562, Aug. 28, 2007; 75 FR 
73945, Nov. 30, 2010]



Sec. 95.7  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 95.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0047.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 95.11, 95.15, 95.17, 95.18, 95.21, 95.25, 
95.33, 95.34, 95.36, 95.37, 95.39, 95.41, 95.43, 95.45, 95.47, 95.53, 
and 95.57.

[62 FR 52190, Oct. 6, 1997, as amended at 64 FR 15650, Apr. 1, 1999]



Sec. 95.9  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part should be submitted as follows:
    (a) By mail addressed to: ATTN: Document Control Desk, Director, 
Division of Security Operations, Office of Nuclear Security and Incident 
Response, U.S Nuclear Regulatory Commission, Washington, DC 20555-0001;
    (b) By hand delivery to the NRC's offices at 11555 Rockville Pike, 
Rockville, Maryland; or
    (c) Where practicable, by electronic submission, for example, 
Electronic Information Exchange, or CD-ROM. Electronic submissions must 
be made in a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.
    (d) Classified communications shall be transmitted in accordance 
with Sec. 95.39 of this chapter to the NRC Headquarters' classified 
mailing address listed in appendix A to part 73 of this chapter or 
delivered by hand in accordance with Sec. 95.39 of this chapter to the 
NRC Headquarters' street address listed in appendix A to part 73 of this 
chapter.

[68 FR 58823, Oct. 10, 2003, as amended at 74 FR 62685, Dec. 1, 2009]



Sec. 95.11  Specific exemptions.

    The NRC may, upon application by any interested person or upon its 
own initiative, grant exemptions from the requirements of the 
regulations of this part, that are--
    (a) Authorized by law, will not present an undue risk to the public 
health and safety, and are consistent with the common defense and 
security; or
    (b) Coincidental with one or more of the following:
    (1) An application of the regulation in the particular circumstances 
conflicts with other rules or requirements of the NRC;
    (2) An application of the regulation in the particular circumstances 
would not serve the underlying purpose of the rule or is not necessary 
to achieve the underlying purpose of the rule;

[[Page 666]]

    (3) When compliance would result in undue hardship or other costs 
that are significantly in excess of those contemplated when the 
regulation was adopted, or that are significantly in excess of those 
incurred by others similarly situated;
    (4) When the exemption would result in benefit to the common defense 
and security that compensates for any decrease in security that may 
result from the grant of the exemption;
    (5) When the exemption would provide only temporary relief from the 
applicable regulation and the licensee or applicant has made good faith 
efforts to comply with the regulation;
    (6) When there is any other material circumstance not considered 
when the regulation was adopted for which it would be in the public 
interest to grant an exemption. If such a condition is relied on 
exclusively for satisfying paragraph (b) of this section, the exemption 
may not be granted until the Executive Director for Operations has 
consulted with the Commission.

[64 FR 15650, Apr. 1, 1999]



Sec. 95.13  Maintenance of records.

    (a) Each licensee, certificate holder or other person granted 
facility clearance under this part shall maintain records as prescribed 
within the part. These records are subject to review and inspection by 
CSA representatives during security reviews.
    (b) Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform provided that the 
copy or microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period. The record may also be stored in electronic media with 
the capability for producing legible, accurate, and complete records 
during the required retention period. Records such as letters, drawings, 
or specifications must include all pertinent information such as stamps, 
initials, and signatures. The licensee, certificate holder, or other 
person shall maintain adequate safeguards against tampering with and 
loss of records.

[53 FR 19263, May 27, 1988, as amended at 62 FR 17691, Apr. 11, 1997; 72 
FR 49562, Aug. 28, 2007]

                            Physical Security



Sec. 95.15  Approval for processing licensees and others for facility
clearance.

    (a) A licensee, certificate holder, or other person who has a need 
to use, process, store, reproduce, transmit, transport, or handle NRC 
classified information at any location in connection with Commission-
related activities shall promptly request an NRC facility clearance. 
This specifically includes situations where a licensee, certificate 
holder, or other person needs a contractor or consultant to have access 
to NRC classified information. Also included are others who require 
access to classified information in connection with NRC regulated 
activities but do not require use, storage, or possession of classified 
information outside of NRC facilities. However, it is not necessary for 
a licensee, certificate holder, or other person to request an NRC 
facility clearance for access to another agency's classified information 
at that agency's facilities or to store that agency's classified 
information at their facility, provided no NRC classified information is 
involved and they meet the security requirements of the other agency. If 
NRC classified information is involved, the requirements of Sec. 95.17 
apply.
    (b) The request must include the name of the facility, the location 
of the facility and an identification of any facility clearance issued 
by another government agency. If there is no existing facility 
clearance, the request must include a security Standard Practice 
Procedures Plan that outlines the facility's proposed security 
procedures and controls for the protection of classified information, a 
floor plan of the area in which the matter is to be used, processed, 
stored, reproduced, transmitted, transported or handled; and Foreign 
Ownership, Control or Influence information.

[[Page 667]]

    (c) NRC will promptly inform applicants of the acceptability of the 
request for further processing and will notify the licensee or other 
person of their decision in writing.

[45 FR 14483, Mar. 5, 1980, as amended at 48 FR 24321, June 1, 1983; 50 
FR 36984, Sept. 11, 1985; 59 FR 48974, Sept. 23, 1994; 62 FR 17691, Apr. 
11, 1997; 64 FR 15650, Apr. 1, 1999]



Sec. 95.17  Processing facility clearance.

    (a) Following the receipt of an acceptable request for facility 
clearance, the NRC will either accept an existing facility clearance 
granted by a current CSA and authorize possession of license or 
certificate related classified information, or process the facility for 
a facility clearance. Processing will include--
    (1) A determination based on review and approval of a Standard 
Practice Procedures Plan that granting of the Facility Clearance would 
not be inconsistent with the national interest, including a finding that 
the facility is not under foreign ownership, control, or influence to 
such a degree that a determination could not be made. An NRC finding of 
foreign ownership, control, or influence is based on factors concerning 
the foreign intelligence threat, risk of unauthorized technology 
transfer, type and sensitivity of the information that requires 
protection, the extent of foreign influence, record of compliance with 
pertinent laws, and the nature of international security and information 
exchange agreements. The licensee, certificate holder, or other person 
must advise the NRC within 30 days of any significant events or changes 
that may affect its status concerning foreign ownership, control, or 
influence (e.g., changes in ownership; changes that affect the company's 
answers to original FOCI questions; indebtedness; and changes in the 
required form that identifies owners, officers, directors, and executive 
personnel).
    (2) An acceptable security review conducted by the NRC;
    (3) Submitting key management personnel for personnel clearances 
(PCLs); and
    (4) Appointing a U.S. citizen employee as the facility security 
officer.
    (b) An interim Facility Clearance may be granted by the CSA on a 
temporary basis pending completion of the full investigative 
requirements.

[62 FR 17692, Apr. 11, 1997, as amended at 64 FR 15650, Apr. 1, 1999]



Sec. 95.18  Key personnel.

    The senior management official and the Facility Security Officer 
must always be cleared to a level commensurate with the Facility 
Clearance. Other key management officials, as determined by the CSA, 
must be granted an access authorization or be excluded from classified 
access. When formal exclusion action is required, the organization's 
board of directors or similar executive body shall affirm the following, 
as appropriate.
    (a) Officers, directors, partners, regents, or trustees (designated 
by name) that are excluded may not require, may not have, and can be 
effectively excluded from access to all classified information disclosed 
to the organization. These individuals also may not occupy positions 
that would enable them to adversely affect the organization's policies 
or practices in the performance of activities involving classified 
information. This action will be made a matter of record by the 
organization's executive body. A copy of the resolution must be 
furnished to the CSA.
    (b) Officers, directors, partners, regents, or trustees (designated 
by name) that are excluded may not require, may not have, and can be 
effectively denied access to higher-level classified information 
(specify which higher level(s)). These individuals may not occupy 
positions that would enable them to adversely affect the organization's 
policies or practices in the protection of classified information. This 
action will be made a matter of record by the organization's executive 
body. A copy of the resolution must be furnished to the CSA.

[62 FR 17692, Apr. 11, 1997]



Sec. 95.19  Changes to security practices and procedures.

    (a) Except as specified in paragraph (b) of this section, each 
licensee, certificate holder, or other person shall

[[Page 668]]

obtain prior CSA approval for any proposed change to the name, location, 
security procedures and controls, or floor plan of the approved 
facility. A written description of the proposed change must be furnished 
to the CSA and the NRC Regional Administrator of the cognizant Regional 
Office listed in appendix A to part 73 of this chapter, and, if the NRC 
is not the CSA, also to the Director, Division of Security Operations, 
Office of Nuclear Security and Incident Response; the communications to 
NRC personnel should be by an appropriate method listed in Sec. 95.9. 
These substantive changes to the Standard Practice Procedures Plan that 
affect the security of the facility must be submitted to the NRC 
Division of Security Operations, or CSA, at least 30 days prior to the 
change so that they may be evaluated. The CSA shall promptly respond in 
writing to all such proposals. Some examples of substantive changes 
requiring prior CSA approval include--
    (1) A change in the approved facility's classified mail address; or
    (2) A temporary or permanent change in the location of the approved 
facility (e.g., moving or relocating NRC's classified interest from one 
room or building to another). Approved changes will be reflected in a 
revised Standard Practice Procedures Plan submission within 30 days of 
approval. Page changes rather than a complete rewrite of the plan may be 
submitted.
    (b) A licensee, certificate holder, or other person may effect a 
minor, non-substantive change to an approved Standard Practice 
Procedures Plan for the safeguarding of classified information without 
receiving prior CSA approval. These minor changes that do not affect the 
security of the facility may be submitted to the addressees noted in 
paragraph (a) of this section within 30 days of the change. Page changes 
rather than a complete rewrite of the plan may be submitted. Some 
examples of minor, non-substantive changes to the Standard Practice 
Procedures Plan include--
    (1) The designation/appointment of a new facility security officer; 
or
    (2) A revision to a protective personnel patrol routine, provided 
the new routine continues to meet the minimum requirements of this part.
    (c) A licensee, certificate holder, or other person must update its 
NRC facility clearance every five years either by submitting a complete 
Standard Practice Procedures Plan or a certification that the existing 
plan is fully current to the Division of Security Operations.

[64 FR 15650, Apr. 1, 1999, as amended at 68 FR 41222, July 11, 2003; 68 
FR 58823, Oct. 10, 2003; 72 FR 49562, Aug. 28, 2007; 74 FR 62685, Dec. 
1, 2009]



Sec. 95.20  Grant, denial or termination of facility clearance.

    The Division of Security Operations shall provide notification in 
writing (or orally with written confirmation) to the licensee, 
certificate holder, or other person of the Commission's grant, 
acceptance of another agency's facility clearance, denial, or 
termination of facility clearance. This information must also be 
furnished to representatives of the NRC, NRC contractors, licensees, 
certificate holders, or other person, or other Federal agencies having a 
need to transmit classified information to the licensees or other 
person.

[72 FR 49562, Aug. 28, 2007, as amended at 74 FR 62685, Dec. 1, 2009]



Sec. 95.21  Withdrawal of requests for facility security clearance.

    When a request for facility clearance is to be withdrawn or 
canceled, the requester shall notify the NRC Division of Security 
Operations in the most expeditious manner so that processing for this 
approval may be terminated. The notification must identify the full name 
of the individual requesting discontinuance, his or her position with 
the facility, and the full identification of the facility. The requestor 
shall confirm the telephone notification promptly in writing.

[64 FR 15651, Apr. 1, 1999, as amended at 68 FR 41222, July 11, 2003; 74 
FR 62685, Dec. 1, 2009]



Sec. 95.23  Termination of facility clearance.

    (a) Facility clearance will be terminated when--

[[Page 669]]

    (1) There is no longer a need to use, process, store, reproduce, 
transmit, transport or handle classified matter at the facility; or
    (2) The Commission makes a determination that continued facility 
clearance is not in the interest of national security.
    (b) When facility clearance is terminated, the licensee, certificate 
holder, or other person will be notified in writing of the determination 
and the procedures outlined in Sec. 95.53 apply.

[62 FR 17692, Apr. 11, 1997, as amended at 72 FR 49562, Aug. 28, 2007]



Sec. 95.25  Protection of National Security Information and Restricted
Data in storage.

    (a) Secret matter, while unattended or not in actual use, must be 
stored in--
    (1) A safe, steel file cabinet, or safe-type steel file container 
that has an automatic unit locking mechanism. All such receptacles will 
be accorded supplemental protection during non-working hours; or
    (2) Any steel file cabinet that has four sides and a top and bottom 
(all permanently attached by welding, rivets, or peened bolts so the 
contents cannot be removed without leaving visible evidence of entry) 
and is secured by a rigid metal lock bar and an approved key operated or 
combination padlock. The keepers of the rigid metal lock bar must be 
secured to the cabinet by welding, rivets, or bolts, so they cannot be 
removed and replaced without leaving evidence of the entry. The drawers 
of the container must be held securely so their contents cannot be 
removed without forcing open the drawer. This type of cabinet will be 
accorded supplemental protection during non-working hours.
    (b) Confidential matter while unattended or not in use must be 
stored in the same manner as SECRET matter except that no supplemental 
protection is required.
    (c) Classified lock combinations. (1) A minimum number of authorized 
persons may know the combinations to authorized storage containers. 
Security containers, vaults, cabinets, and other authorized storage 
containers must be kept locked when not under the direct supervision of 
an authorized person entrusted with the contents.
    (2) Combinations must be changed by a person authorized access to 
the contents of the container, by the Facility Security Officer, or his 
or her designee.
    (d) Records of combinations. If a record is made of a combination, 
the record must be marked with the highest classification of material 
authorized for storage in the container. Superseded combinations must be 
destroyed.
    (e) Selections of combinations. Each combination must be randomly 
selected and require the use of at least three different numbers. In 
selecting combinations, multiples, simple arithmetical ascending or 
descending series, telephone numbers, social security numbers, car 
license numbers, and calendar dates such as birthdates and 
anniversaries, shall be avoided.
    (f) Combinations will be changed only by persons authorized access 
to Secret or Confidential National Security Information and/or 
Restricted Data depending upon the matter authorized to be stored in the 
security container.
    (g) Posted information. Containers may not bear external markings 
indicating the level of classified matter authorized for storage. A 
record of the names of persons having knowledge of the combination must 
be posted inside the container.
    (h) End of day security checks. (1) Facilities that store classified 
matter shall establish a system of security checks at the close of each 
working day to ensure that all classified matter and security 
repositories have been appropriately secured.
    (2) Facilities operating with multiple work shifts shall perform the 
security checks at the end of the last working shift in which classified 
matter had been removed from storage for use. The checks are not 
required during continuous 24-hour operations.
    (i) Unattended security container found opened. If an unattended 
security container housing classified matter is found unlocked, the 
custodian or an alternate must be notified immediately. Also, the 
container must be secured by protective personnel. An effort must be 
made to determine if the contents were

[[Page 670]]

compromised not later than the next day.
    (j) Supervision of keys and padlocks. Use of key-operated padlocks 
are subject to the following requirements:
    (1) A key and lock custodian shall be appointed to ensure proper 
custody and handling of keys and locks used for protection of classified 
matter;
    (2) A key and lock control register must be maintained to identify 
keys for each lock and their current location and custody;
    (3) Keys and locks must be audited each month;
    (4) Keys must be inventoried with each change of custody;
    (5) Keys must not be removed from the premises;
    (6) Keys and spare locks must be protected equivalent to the level 
of classified matter involved;
    (7) Locks must be changed or rotated at least every 12 months, and 
must be replaced after loss or compromise of their operable keys; and
    (8) Master keys may not be made.

[45 FR 14483, Mar. 5, 1980, as amended at 47 FR 9196, Mar. 4, 1982; 50 
FR 36985, Sept. 11, 1985; 53 FR 19263, May 27, 1988; 59 FR 48975, Sept. 
23, 1994; 62 FR 17693, Apr. 11, 1997; 64 FR 15651, Apr. 1, 1999]



Sec. 95.27  Protection while in use.

    While in use, classified matter must be under the direct control of 
an authorized individual to preclude physical, audio, and visual access 
by persons who do not have the prescribed access authorization or other 
written CSA disclosure authorization (see Sec. 95.36 for additional 
information concerning disclosure authorizations).

[64 FR 15651, Apr. 1, 1999]



Sec. 95.29  Establishment of Restricted or Closed areas.

    (a) If, because of its nature, sensitivity or importance, classified 
matter cannot otherwise be effectively controlled in accordance with the 
provisions of Sec. Sec. 95.25 and 95.27, a Restricted or Closed area 
must be established to protect this matter.
    (b) The following measures apply to Restricted Areas:
    (1) Restricted areas must be separated from adjacent areas by a 
physical barrier designed to prevent unauthorized access (physical, 
audio, and visual) into these areas.
    (2) Controls must be established to prevent unauthorized access to 
and removal of classified matter.
    (3) Access to classified matter must be limited to persons who 
possess appropriate access authorization or other written CSA disclosure 
authorization and who require access in the performance of their 
official duties or regulatory obligations.
    (4) Persons without appropriate access authorization for the area 
visited must be escorted by an appropriate CSA access authorized person 
at all times while within Restricted or Closed Areas.
    (5) Each individual authorized to enter a Restricted or Closed Area 
must be issued a distinctive form of identification (e.g., badge) when 
the number of employees assigned to the area exceeds thirty per shift.
    (6) During nonworking hours, admittance must be controlled by 
protective personnel. Protective personnel shall conduct patrols during 
nonworking hours at least every 8 hours and more frequently if necessary 
to maintain a commensurate level of protection. Entrances must be 
continuously monitored by protective personnel or by an approved alarm 
system.
    (c) Due to the size and nature of the classified material, or 
operational necessity, it may be necessary to construct Closed Areas for 
storage because GSA-approved containers or vaults are unsuitable or 
impractical. Closed Areas must be approved by the CSA. The following 
measures apply to Closed Areas:
    (1) Access to Closed Areas must be controlled to preclude 
unauthorized access. This may be accomplished through the use of a 
cleared employee or by a CSA approved access control device or system.
    (2) Access must be limited to authorized persons who have an 
appropriate security clearance and a need-to-know for the classified 
matter within the area. Persons without the appropriate level of 
clearance and/or need-to-know must be escorted at all times by an 
authorized person where inadvertent or unauthorized exposure to 
classified information cannot otherwise be effectively prevented.

[[Page 671]]

    (3) The Closed Area must be accorded supplemental protection during 
non-working hours. During these hours, admittance to the area must be 
controlled by locked entrances and exits secured by either an approved 
built-in combination lock or an approved combination or key-operated 
padlock. However, doors secured from the inside with a panic bolt (for 
example, actuated by a panic bar), a dead bolt, a rigid wood or metal 
bar, or other means approved by the CSA, do not require additional 
locking devices.
    (4) Open shelf or bin storage of classified matter in Closed Areas 
requires CSA approval. Only areas protected by an approved intrusion 
detection system will qualify for approval.

[62 FR 17693, Apr. 11, 1997, as amended at 64 FR 15652, Apr. 1, 1999]



Sec. 95.31  Protective personnel.

    Whenever protective personnel are used to protect classified 
information they shall:
    (a) Possess an ``L'' access authorization (or CSA equivalent) if the 
licensee, certificate holder, or other person possesses information 
classified Confidential National Security Information, Confidential 
Restricted Data or Secret National Security Information.
    (b) Possess a ``Q'' access authorization (or CSA equivalent) if the 
licensee, certificate holder, or other person possesses Secret 
Restricted Data related to nuclear weapons design, manufacturing and 
vulnerability information; and certain particularly sensitive Naval 
Nuclear Propulsion Program information (e.g., fuel manufacturing 
technology) and the protective personnel require access as part of their 
regular duties.

[72 FR 49562, Aug. 28, 2007]



Sec. 95.33  Security education.

    All cleared employees must be provided with security training and 
briefings commensurate with their involvement with classified 
information. The facility official(s) responsible for the program shall 
determine the means and methods for providing security education and 
training. A licensee or other entity subject to part 95 may obtain 
defensive security, threat awareness, and other education and training 
information and material from their Cognizant Security Agency (CSA) or 
other appropriate sources.
    (a) Facility Security Officer training. Licensees or other entities 
subject to part 95 are responsible for ensuring that the Facility 
Security Officer, and other personnel performing security duties, 
complete security training deemed appropriate by the CSA. Training 
requirements must be based on the facility's involvement with classified 
information and may include a Facility Security Officer Orientation 
Course and, for Facility Security Officers at facilities with 
safeguarding capability, a Facility Security Officer Program Management 
Course. Training, if required, should be completed within 1 year of 
appointment to the position of Facility Security Officer.
    (b) Government-provided briefings. The CSA is responsible for 
providing initial security briefings to the Facility Security Officer, 
and for ensuring that other briefings required for special categories of 
information are provided.
    (c) Temporary help suppliers. A temporary help supplier, or other 
contractor who employs cleared individuals solely for dispatch 
elsewhere, is responsible for ensuring that required briefings are 
provided to their cleared personnel. The temporary help supplier or the 
using licensee's, certificate holder's, or other person's facility may 
conduct these briefings.
    (d) Classified Information Nondisclosure Agreement (SF-312). The SF-
312 is an agreement between the United States and an individual who is 
cleared for access to classified information. An employee issued an 
initial access authorization must, in accordance with the requirements 
of Sec. 25.23 of this chapter, execute an SF-312 before being granted 
access to classified information. The Facility Security Officer shall 
forward the executed SF-312 to the CSA for retention. If the employee 
refuses to execute the SF-312, the licensee or other facility shall deny 
the employee access to classified information and submit a report to the 
CSA. The SF-312 must be signed and dated by the employee and witnessed. 
The employee's and witness' signatures must bear the same date.

[[Page 672]]

    (e) Access to classified information. Employees may have access to 
classified information only if:
    (1) A favorable determination of eligibility for access has been 
made with respect to such employee by the CSA;
    (2) The employee has signed an approved non-disclosure agreement; 
and
    (3) The employee has a need-to-know the information.
    (f) Initial security briefings. Initial training shall be provided 
to every employee who has met the standards for access to classified 
information in accordance with paragraph (e) of this section before the 
employee is granted access to classified information. The initial 
training shall include the following topics:
    (1) A Threat Awareness Briefing;
    (2) A Defensive Security Briefing;
    (3) An overview of the security classification system;
    (4) Employee reporting obligations and requirements; and
    (5) Security procedures and duties applicable to the employee's job.
    (g) Refresher briefings. The licensee or other entities subject to 
part 95 shall conduct refresher briefings for all cleared employees at 
least annually. As a minimum, the refresher briefing must reinforce the 
information provided during the initial briefing and inform employees of 
appropriate changes in security regulations. This requirement may be 
satisfied by use of audio/video materials and/or by issuing written 
materials to cleared employees.
    (h) Persons who apply derivative classification markings shall 
receive training specific to the proper application of the derivative 
classification principles of Executive Order 13526, Classified National 
Security Information (75 FR 707; January 5, 2010), before derivatively 
classifying information and at least once every 2 years thereafter.
    (i) Debriefings. Licensee and other facilities shall debrief cleared 
employees at the time of termination of employment (discharge, 
resignation, or retirement); when an employee's access authorization is 
terminated, suspended, or revoked; and upon termination of the Facility 
Clearance.
    (j) Records reflecting an individual's initial and refresher 
security orientations and security termination must be maintained for 3 
years after termination of the individual's access authorization.

[78 FR 48041, Aug. 7, 2013]



Sec. 95.34  Control of visitors.

    (a) Uncleared visitors. Licensees, certificate holders, or other 
persons subject to this part shall take measures to preclude access to 
classified information by uncleared visitors.
    (b) Foreign visitors. Licensees, certificate holders, or other 
persons subject to this part shall take measures as may be necessary to 
preclude access to classified information by foreign visitors. The 
licensee, certificate holder, or other person shall retain records of 
visits for 5 years beyond the date of the visit.

[72 FR 49563, Aug. 28, 2007]

                         Control of Information



Sec. 95.35  Access to matter classified as National Security 
Information and Restricted Data.

    (a) Except as the Commission may authorize, no licensee, certificate 
holder or other person subject to the regulations in this part may 
receive or may permit any other licensee, certificate holder, or other 
person to have access to matter revealing Secret or Confidential 
National Security Information or Restricted Data unless the individual 
has:
    (1)(i) A ``Q'' access authorization which permits access to matter 
classified as Secret and Confidential Restricted Data or Secret and 
Confidential National Security Information which includes intelligence 
information, CRYPTO (i.e., cryptographic information) or other 
classified communications security (COMSEC) information, or
    (ii) An ``L'' access authorization which permits access to matter 
classified as Confidential Restricted Data and Secret and Confidential 
National Security Information other than that noted in paragraph 
(a)(1)(i) of this section except that access to certain Confidential 
COMSEC information is permitted as authorized by a National 
Communications Security Committee waiver dated February 14, 1984.

[[Page 673]]

    (2) An established ``need-to-know'' for the matter (See Definitions, 
Sec. 95.5).
    (3) NRC-approved storage facilities if classified documents or 
material are to be transmitted to the licensee, certificate holder, or 
other person.
    (b) Matter classified as National Security Information or Restricted 
Data shall not be released by a licensee or other person subject to part 
95 to any personnel other than properly access authorized Commission 
licensee employees, or other individuals authorized access by the 
Commission.
    (c) Access to matter which is National Security Information at NRC-
licensed facilities or NRC-certified facilities by authorized 
representatives of IAEA is permitted in accordance with Sec. 95.36.

[59 FR 48975, Sept. 23, 1994, as amended at 72 FR 49563, Aug. 28, 2007]



Sec. 95.36  Access by representatives of the International Atomic 
Energy Agency or by participants in other international agreements.

    (a) Based upon written disclosure authorization from the NRC Office 
of Nuclear Material Safety and Safeguards that an individual is an 
authorized representative of the International Atomic Energy Agency 
(IAEA) or other international organization and that the individual is 
authorized to make visits under an established agreement with the United 
States Government, an applicant, licensee, certificate holder, or other 
person subject to this part shall permit the individual (upon 
presentation of the credentials specified in Sec. 75.8(c) of this 
chapter and any other credentials identified in the disclosure 
authorization) to have access to matter classified as National Security 
Information that is relevant to the conduct of a visit or inspection. A 
disclosure authorization under this section does not authorize a 
licensee, certificate holder, or other person subject to this part to 
provide access to Restricted Data.
    (b) For purposes of this section, classified National Security 
Information is relevant to the conduct of a visit or inspection if--
    (1) In the case of a visit, this information is needed to verify 
information according to Sec. 75.8 of this chapter; or
    (2) In the case of an inspection, an inspector is entitled to have 
access to the information under Sec. 75.8 of this chapter.
    (c) In accordance with the specific disclosure authorization 
provided by the Division of Security Operations, licensees, certificate 
holders, or other persons subject to this part are authorized to release 
(i.e., transfer possession of) copies of documents that contain 
classified National Security Information directly to IAEA inspectors and 
other representatives officially designated to request and receive 
classified National Security Information documents. These documents must 
be marked specifically for release to IAEA or other international 
organizations in accordance with instructions contained in the NRC's 
disclosure authorization letter. Licensees, certificate holders, and 
other persons subject to this part may also forward these documents 
through the NRC to the international organization's headquarters in 
accordance with the NRC disclosure authorization. Licensees, certificate 
holders, and other persons may not reproduce documents containing 
classified National Security Information except as provided in Sec. 
95.43.
    (d) Records regarding these visits and inspections must be 
maintained for 5 years beyond the date of the visit or inspection. These 
records must specifically identify each document released to an 
authorized representative and indicate the date of the release. These 
records must also identify (in such detail as the Division of Security 
Operations, by letter, may require) the categories of documents that the 
authorized representative has had access and the date of this access. A 
licensee, certificate holder, or other person subject to this part shall 
also retain Division of Security Operations disclosure authorizations 
for 5 years beyond the date of any visit or inspection when access to 
classified information was permitted.
    (e) Licensees, certificate holders, or other persons subject to this 
part shall take such measures as may be necessary to preclude access to 
classified matter by participants of other international agreements 
unless specifically

[[Page 674]]

provided for under the terms of a specific agreement.

[62 FR 17694, Apr. 11, 1997, as amended at 64 FR 15652, Apr. 1, 1999; 68 
FR 41222, July 11, 2003; 72 FR 49563, Aug. 28, 2007; 73 FR 78614, Dec. 
23, 2008; 74 FR 62686, Dec. 1, 2009]



Sec. 95.37  Classification and preparation of documents.

    (a) Classification. Classified information generated or possessed by 
a licensee, certificate holder, or other person must be appropriately 
marked. Classified material which is not conducive to markings (e.g., 
equipment) may be exempt from this requirement. These exemptions are 
subject to the approval of the CSA on a case-by-case basis. If a person 
or facility generates or possesses information that is believed to be 
classified based on guidance provided by the NRC or by derivation from 
classified documents, but which no authorized classifier has determined 
to be classified, the information must be protected and marked with the 
appropriate classification markings pending review and signature of an 
NRC authorized classifier. This information shall be protected as 
classified information pending final determination.
    (b) Classification consistent with content. Each document containing 
classified information shall be classified Secret or Confidential 
according to its content. NRC licensees, certificate holders, or other 
persons subject to the requirements of 10 CFR part 95 may not make 
original classification decisions.
    (c) Markings required on face of documents. (1) For derivative 
classification of classified National Security Information:
    (i) Derivative classifications of classified National Security 
Information must contain the identity of the source document or the 
classification guide, including the agency and office of origin, on the 
``Derived From'' line and its classification date. If more than one 
source is cited, the ``Derived From'' line should indicate ``Multiple 
Sources.'' The derivative classifier shall maintain the identification 
of each source with the file or record copy of the derivatively 
classified document.
    (ii) Declassification instructions. When marking derivatively 
classified documents, the ``DECLASSIFY ON'' line must carry forward the 
declassification instructions as reflected in the original document. If 
multiple sources are used, the instructions will carry forward the 
longest duration.
    (iii) An example of the marking stamp is as follows:

 Derived from___________________________________________________________
 (Source/Date)

 Reason:________________________________________________________________

 Declassify On:_________________________________________________________

 (Date/Event/Exemption)

 Classifier:____________________________________________________________
 (Name/Title/Number)
    (2) For Restricted Data documents:
    (i) Identity of the classifier. The identity of the classifier must 
be shown by completion of the ``Derivative Classifier'' line. The 
``Derivative Classifier'' line must show the name of the person 
classifying the document and the basis for the classification. Dates for 
downgrading or declassification do not apply.
    (ii) Classification designation (e.g., Secret, Confidential) and 
Restricted Data. NOTE: No ``Declassification'' instructions will be 
placed on documents containing Restricted Data.
    (d) Placement of markings. The highest classification marking 
assigned to a document must be placed in a conspicuous fashion in 
letters at the top and bottom of the outside of the front covers and 
title pages, if any, and first and last pages on which text appears, on 
both bound and unbound documents, and on the outside of back covers of 
bound documents. The balance of the pages must be marked at the top and 
bottom with:
    (1) The overall classification marking assigned to the document;
    (2) The highest classification marking required by content of the 
page; or
    (3) The marking UNCLASSIFIED if they have no classified content.
    (e) Additional markings. (1) If the document contains any form of 
Restricted Data, it must bear the appropriate marking on the first page 
of text, on the front cover and title page, if any. For example: ``This 
document contains Restricted Data as defined in the

[[Page 675]]

Atomic Energy Act of 1954. Unauthorized disclosure subject to 
Administrative and Criminal Sanctions.''
    (2) Limitation on reproduction or dissemination. If the originator 
or classifier determines that reproduction or further dissemination of a 
document should be restricted, the following additional wording may be 
placed on the face of the document:

Reproduction or Further Dissemination Requires Approval of
________________________________________________________________________
If any portion of this additional marking does not apply, it should be 
crossed out.

    (f) Portion markings. In addition to the information required on the 
face of the document, each classified document is required, by marking 
or other means, to indicate clearly which portions are classified (e.g., 
paragraphs or pages) and which portions are not classified. The symbols 
(S) for Secret, (C) for Confidential, (U) for Unclassified, or (RD) for 
Restricted Data may be used immediately preceding or following the text 
to which it applies, except that the designation must follow titles or 
subjects. (Portion marking of paragraphs is not required for documents 
containing Restricted Data.) If this type of portion marking is not 
practicable, the document must contain a description sufficient to 
identify the classified information and the unclassified information.

                                 Example

Pages 1-3 Secret
Pages 4-19 Unclassified
Pages 20-26 Secret
Pages 27-32 Confidential

    (g) Transmittal document. If a document transmitting classified 
information contains no classified information or the classification 
level of the transmittal document is not as high as the highest 
classification level of its enclosures, then the document must be marked 
at the top and bottom with a classification at least as high as its 
highest classified enclosure. The classification may be higher if the 
enclosures, when combined, warrant a higher classification than any 
individual enclosure. When the contents of the transmittal document 
warrants a lower classification than the highest classified enclosure(s) 
or combination of enclosures or requires no classification, a stamp or 
marking such as the following must also be used on the transmittal 
document:

    UPON REMOVAL OF ATTACHMENTS THIS DOCUMENT IS:

(Classification level of transmittal document standing alone or the word 
``UNCLASSIFIED'' if the transmittal document contains no classified 
information.)

    (h) Classification challenges. Licensees, certificate holders, or 
other persons in authorized possession of classified National Security 
Information who in good faith believe that the information's 
classification status (i.e., that the document), is classified at either 
too high a level for its content (overclassification) or too low for its 
content (underclassification) are expected to challenge its 
classification status. Licensees, certificate holders, or other persons 
who wish to challenge a classification status shall--
    (1) Refer the document or information to the originator or to an 
authorized NRC classifier for review. The authorized classifier shall 
review the document and render a written classification decision to the 
holder of the information.
    (2) In the event of a question regarding classification review, the 
holder of the information or the authorized classifier shall consult the 
NRC Division of Facilities and Security, Information Security Branch, 
for assistance.
    (3) Licensees, certificate holders, or other persons who challenge 
classification decisions have the right to appeal the classification 
decision to the Interagency Security Classification Appeals Panel.
    (4) Licensees, certificate holders, or other persons seeking to 
challenge the classification of information will not be the subject of 
retribution.
    (i) Files, folders or group of documents. Files, folders, binders, 
or groups of physically connected documents must be marked at least as 
high as the highest classified document which they contain.
    (j) Drafts and working papers. Drafts of documents and working 
papers which contain, or which are believed to contain, classified 
information must be marked as classified information.

[[Page 676]]

    (k) Classification guidance. Licensees, certificate holders, or 
other persons subject to this part shall classify and mark classified 
matter as National Security Information or Restricted Data, as 
appropriate, in accordance with classification guidance provided by the 
NRC as part of the facility clearance process.

[62 FR 17695, Apr. 11, 1997, as amended at 64 FR 15652, Apr. 1, 1999; 68 
FR 41222, July 11, 2003; 72 FR 49563, Aug. 28, 2007]



Sec. 95.39  External transmission of documents and material.

    (a) Restrictions. Documents and material containing classified 
information received or originated in connection with an NRC license, 
certificate, or standard design approval or standard design 
certification under part 52 of this chapter must be transmitted only to 
CSA approved security facilities.
    (b) Preparation of documents. Documents containing classified 
information must be prepared in accordance with the following when 
transmitted outside an individual installation.
    (1) The documents must be enclosed in two sealed opaque envelopes or 
wrappers.
    (2) The inner envelope or wrapper must contain the addressee's 
classified mail address and the name of the intended recipient. The 
appropriate classification must be placed on both sides of the envelope 
(top and bottom) and the additional markings, as appropriate, referred 
to in Sec. 95.37(e) must be placed on the side bearing the address.
    (3) The outer envelope or wrapper must contain the addressee's 
classified mailing address. The outer envelope or wrapper may not 
contain any classification, additional marking or other notation that 
indicate that the enclosed document contains classified information. The 
Classified Mailing Address shall be uniquely designated for the receipt 
of classified information. The classified shipping address for the 
receipt of material (e.g., equipment) should be different from the 
classified mailing address for the receipt of classified documents.
    (4) A receipt that contains an unclassified description of the 
document, the document number, if any, date of the document, 
classification, the date of transfer, the recipient and the person 
transferring the document must be enclosed within the inner envelope 
containing the document and be signed by the recipient and returned to 
the sender whenever the custody of a Secret document is transferred. 
This receipt process is at the option of the sender for Confidential 
information.
    (c) Methods of transportation. (1) Secret matter may be transported 
only by one of the following methods within and directly between the 
U.S., Puerto Rico, or a U.S. possession or trust territory:
    (i) U.S. Postal Service Express Mail and U.S. Postal Service 
Registered Mail.

    Note: The ``Waiver of Signature and Indemnity'' block on the U.S. 
Postal Service Express Mail Label 11-B may not be executed and the use 
of external (street side) express mail collection boxes is prohibited.

    (ii) A cleared ``Commercial Carrier.''
    (iii) A cleared commercial messenger service engaged in the 
intracity/local area delivery (same day delivery only) of classified 
material.
    (iv) A commercial delivery company, approved by the CSA, that 
provides nationwide, overnight service with computer tracing and 
reporting features. These companies need not be security cleared.
    (v) Other methods as directed, in writing, by the CSA.
    (2) Confidential matter may be transported by one of the methods set 
forth in paragraph (c)(1) of this section, by U.S. express or certified 
mail. Express or certified mail may be used in transmission of 
Confidential documents to Puerto Rico or any United States territory or 
possession.
    (d) Telecommunication of classified information. Classified 
information may not be telecommunicated unless the telecommunication 
system has been approved by the CSA. Licensees, certificate holders or 
other persons who may require a secure telecommunication system shall 
submit a telecommunication plan as part of their request for facility 
clearance, as outlined in Sec. 95.15, or as an amendment to their 
existing Standard Practice Procedures Plan for the protection of 
classified information.

[[Page 677]]

    (e) Security of classified information in transit. Classified matter 
that, because of its nature, cannot be transported in accordance with 
Sec. 95.39(c), may only be transported in accordance with procedures 
approved by the CSA. Procedures for transporting classified matter are 
based on a satisfactory transportation plan submitted as part of the 
licensee's, certificate holder, or other person's request for facility 
clearance or submitted as an amendment to its existing Standard Practice 
Procedures Plan.

[62 FR 17696, Apr. 11, 1997, as amended at 64 FR 15652, Apr. 1, 1999; 72 
FR 49564, Aug. 28, 2007]



Sec. 95.41  External receipt and dispatch records.

    Each licensee, certificate holder or other person possessing 
classified information shall maintain a record that reflects:
    (a) The date of the material;
    (b) The date of receipt or dispatch;
    (c) The classification;
    (d) An unclassified description of the material; and
    (e) The identity of the sender from which the material was received 
or recipient to which the material was dispatched. receipt and dispatch 
records must be retained for 2 years.

[62 FR 17697, Apr. 11, 1997]



Sec. 95.43  Authority to reproduce.

    (a) Each licensee, certificate holder, or other person possessing 
classified information shall establish a reproduction control system to 
ensure that reproduction of classified material is held to the minimum 
consistent with operational requirements. Classified reproduction must 
be accomplished by authorized employees knowledgeable of the procedures 
for classified reproduction. The use of technology that prevents, 
discourages, or detects the unauthorized reproduction of classified 
documents is encouraged.
    (b) Unless restricted by the CSA, Secret and Confidential documents 
may be reproduced. Reproduced copies of classified documents are subject 
to the same protection as the original documents.
    (c) All reproductions of classified material must be conspicuously 
marked with the same classification markings as the material being 
reproduced. Copies of classified material must be reviewed after the 
reproduction process to ensure that these markings are visible.

[62 FR 17697, Apr. 11, 1997, as amended at 72 FR 49564, Aug. 28, 2007]



Sec. 95.45  Changes in classification.

    (a) Documents containing classified National Security Information 
must be downgraded or declassified as authorized by the NRC 
classification guides or as determined by the NRC. Requests for 
downgrading or declassifying any NRC classified information should be 
forwarded to the NRC's Division of Security Operations, Nuclear Security 
and Incident Response, using an appropriate method listed in Sec. 95.9. 
Requests for downgrading or declassifying of Restricted Data will be 
forwarded to the NRC Division of Security Operations for coordination 
with the Department of Energy.
    (b) If a change of classification or declassification is approved, 
the previous classification marking must be canceled and the following 
statement, properly completed, must be placed on the first page of the 
document:

    Classification canceled (or changed to)

________________________________________________________________________
(Insert appropriate classification)
    By authority of

________________________________________________________________________
(Person authorizing change in classification)
    By

________________________________________________________________________
(Signature of person making change and date thereof)

    (c) New markings reflecting the current classification status of the 
document will be applied in accordance with the requirements of Sec. 
95.37.
    (d) Any licensee, certificate holder, or other person making a 
change in classification or receiving notice of such a change shall 
forward notice of the change in classification to holders of all copies 
as shown on their records.

[62 FR 17697, Apr. 11, 1997, as amended at 64 FR 15653, Apr. 1, 1999; 68 
FR 41222, July 11, 2003; 68 FR 58823, Oct. 10, 2003; 72 FR 49564, Aug. 
28, 2007; 74 FR 62686, Dec. 1, 2009]

[[Page 678]]



Sec. 95.47  Destruction of matter containing classified information.

    Documents containing classified information may be destroyed by 
burning, pulping, or another method that ensures complete destruction of 
the information that they contain. The method of destruction must 
preclude recognition or reconstruction of the classified information. 
Any doubts on methods should be referred to the CSA.

[64 FR 15653, Apr. 1, 1999]



Sec. 95.49  Security of automatic data processing (ADP) systems.

    Classified data or information may not be processed or produced on 
an ADP system unless the system and procedures to protect the classified 
data or information have been approved by the CSA. Approval of the ADP 
system and procedures is based on a satisfactory ADP security proposal 
submitted as part of the licensee's, certificate holder's, or other 
person's request for facility clearance outlined in Sec. 95.15 or 
submitted as an amendment to its existing Standard Practice Procedures 
Plan for the protection of classified information.

[72 FR 49564, Aug. 28, 2007]



Sec. 95.51  Retrieval of classified matter following suspension
or revocation of access authorization.

    In any case where the access authorization of an individual is 
suspended or revoked in accordance with the procedures set forth in part 
25 of this chapter, or other relevant CSA procedures, the licensee, 
certificate holder, or other person shall, upon due notice from the 
Commission of such suspension or revocation, retrieve all classified 
information possessed by the individual and take the action necessary to 
preclude that individual having further access to the information.

[72 FR 49564, Aug. 28, 2007]



Sec. 95.53  Termination of facility clearance.

    (a) If the need to use, process, store, reproduce, transmit, 
transport, or handle classified matter no longer exists, the facility 
clearance will be terminated. The licensee, certificate holder, or other 
person for the facility may deliver all documents and matter containing 
classified information to the Commission, or to a person authorized to 
receive them, or must destroy all classified documents and matter. In 
either case, the licensee, certificate holder, or other person for the 
facility shall submit a certification of nonpossession of classified 
information to the NRC Division of Security Operations within 30 days of 
the termination of the facility clearance.
    (b) In any instance where a facility clearance has been terminated 
based on a determination of the CSA that further possession of 
classified matter by the facility would not be in the interest of the 
national security, the licensee, certificate holder, or other person for 
the facility shall, upon notice from the CSA, dispose of classified 
documents in a manner specified by the CSA.

[72 FR 49564, Aug. 28, 2007, as amended at 74 FR 62686, Dec. 1, 2009]



Sec. 95.55  Continued applicability of the regulations in this part.

    The suspension, revocation or other termination of access 
authorization or the termination of facility clearance does not relieve 
any person from compliance with the regulations in this part.

[62 FR 17698, Apr. 11, 1997]



Sec. 95.57  Reports.

    Each licensee, certificate holder, or other person having a facility 
clearance shall report to the CSA and the Regional Administrator of the 
appropriate NRC Regional Office listed in 10 CFR part 73, appendix A:
    (a) Any alleged or suspected violation of the Atomic Energy Act, 
Espionage Act, or other Federal statutes related to classified 
information (e.g., deliberate disclosure of classified information to 
persons not authorized to receive it, theft of classified information). 
Incidents such as this must be reported within 1 hour of the event 
followed by written confirmation within 30 days of the incident; and
    (b) Any infractions, losses, compromises, or possible compromise of 
classified information or classified documents not falling within 
paragraph

[[Page 679]]

(a) of this section. Incidents such as these must be entered into a 
written log. A copy of the log must be provided to the NRC on a monthly 
basis. Details of security infractions including corrective action taken 
must be available to the CSA upon request.
    (c) In addition, NRC requires records for all classification actions 
(documents classified, declassified, or downgraded) to be submitted to 
the NRC Division of Security Operations. These may be submitted either 
on an ``as completed'' basis or monthly. The information may be 
submitted either electronically by an on-line system (NRC prefers the 
use of a dial-in automated system connected to the Division of Security 
Operations) or by paper copy using NRC Form 790.

[64 FR 15653, Apr. 1, 1999, as amended at 68 FR 41222, July 11, 2003; 72 
FR 49564, Aug. 28, 2007; 74 FR 62686, Dec. 1, 2009]



Sec. 95.59  Inspections.

    The Commission shall make inspections and reviews of the premises, 
activities, records and procedures of any licensee, certificate holder, 
or other person subject to the regulations in this part as the 
Commission and CSA deem necessary to effect the purposes of the Act, 
E.O. 13526, as amended, or any predecessor or successor order, and/or 
NRC rules.

[75 FR 73945, Nov. 30, 2010]

                               Violations



Sec. 95.61  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
Section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55080, Nov. 24, 1992]



Sec. 95.63  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 95 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 95 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 95.1, 95.3, 95.5, 95.7, 95.8, 95.9, 95.11, 95.17, 95.19, 
95.21, 95.23, 95.55, 95.59, 95.61, and 95.63.

[57 FR 55080, Nov. 24, 1992]



PART 100_REACTOR SITE CRITERIA--Table of Contents



Sec.
100.1 Purpose.
100.2 Scope.
100.3 Definitions.
100.4 Communications.
100.8 Information collection requirements: OMB approval.

     Subpart A_Evaluation Factors for Stationary Power Reactor Site 
      Applications Before January 10, 1997 and for Testing Reactors

100.10 Factors to be considered when evaluating sites.
100.11 Determination of exclusion area, low population zone, and 
          population center distance.

     Subpart B_Evaluation Factors for Stationary Power Reactor Site 
                Applications on or After January 10, 1997

100.20 Factors to be considered when evaluating sites.

[[Page 680]]

100.21 Non-seismic site criteria.
100.23 Geologic and seismic siting criteria.

Appendix A to Part 100--Seismic and Geologic Siting Criteria for Nuclear 
          Power Plants

    Authority: Atomic Energy Act of 1954, secs. 103, 104, 161, 182 (42 
U.S.C. 2133, 2134, 2201, 2232); Energy Reorganization Act of 1974, secs. 
201, 202 (42 U.S.C. 5841, 5842); 44 U.S.C. 3504 note.

    Source: 27 FR 3509, Apr. 12, 1962, unless otherwise noted.

    Editorial Note: Nomenclature changes to part 100 appear at 81 FR 
86910, Dec. 2, 2016.



Sec. 100.1  Purpose.

    (a) The purpose of this part is to establish approval requirements 
for proposed sites for stationary power and testing reactors subject to 
part 50 or part 52 of this chapter.
    (b) There exists a substantial base of knowledge regarding power 
reactor siting, design, construction and operation. This base reflects 
that the primary factors that determine public health and safety are the 
reactor design, construction and operation.
    (c) Siting factors and criteria are important in assuring that 
radiological doses from normal operation and postulated accidents will 
be acceptably low, that natural phenomena and potential man-made hazards 
will be appropriately accounted for in the design of the plant, that 
site characteristics are such that adequate security measures to protect 
the plant can be developed, and that physical characteristics unique to 
the proposed site that could pose a significant impediment to the 
development of emergency plans are identified.
    (d) This approach incorporates the appropriate standards and 
criteria for approval of stationary power and testing reactor sites. The 
Commission intends to carry out a traditional defense-in-depth approach 
with regard to reactor siting to ensure public safety. Siting away from 
densely populated centers has been and will continue to be an important 
factor in evaluating applications for site approval.

[61 FR 65175, Dec. 11, 1996]



Sec. 100.2  Scope.

    The siting requirements contained in this part apply to applications 
for site approval for the purpose of constructing and operating 
stationary power and testing reactors pursuant to the provisions of part 
50 or part 52 of this chapter.

[61 FR 65175, Dec. 11, 1996]



Sec. 100.3  Definitions.

    As used in this part:
    Combined license means a combined construction permit and operating 
license with conditions for a nuclear power facility issued pursuant to 
subpart C of part 52 of this chapter.
    Early Site Permit means a Commission approval, issued pursuant to 
subpart A of part 52 of this chapter, for a site or sites for one or 
more nuclear power facilities.
    Exclusion area means that area surrounding the reactor, in which the 
reactor licensee has the authority to determine all activities including 
exclusion or removal of personnel and property from the area. This area 
may be traversed by a highway, railroad, or waterway, provided these are 
not so close to the facility as to interfere with normal operations of 
the facility and provided appropriate and effective arrangements are 
made to control traffic on the highway, railroad, or waterway, in case 
of emergency, to protect the public health and safety. Residence within 
the exclusion area shall normally be prohibited. In any event, residents 
shall be subject to ready removal in case of necessity. Activities 
unrelated to operation of the reactor may be permitted in an exclusion 
area under appropriate limitations, provided that no significant hazards 
to the public health and safety will result.
    Low population zone means the area immediately surrounding the 
exclusion area which contains residents, the total number and density of 
which are such that there is a reasonable probability that appropriate 
protective measures could be taken in their behalf in the event of a 
serious accident. These guides do not specify a permissible population 
density or total population within this zone because the situation may 
vary from case to case. Whether a specific number of people can, for 
example, be evacuated from a specific area, or instructed to take 
shelter, on a timely basis will depend

[[Page 681]]

on many factors such as location, number and size of highways, scope and 
extent of advance planning, and actual distribution of residents within 
the area.
    Population center distance means the distance from the reactor to 
the nearest boundary of a densely populated center containing more than 
about 25,000 residents.
    Power reactor means a nuclear reactor of a type described in Sec. 
50.21(b) or Sec. 50.22 of this chapter designed to produce electrical 
or heat energy.
    Response spectrum is a plot of the maximum responses (acceleration, 
velocity, or displacement) of idealized single-degree-of-freedom 
oscillators as a function of the natural frequencies of the oscillators 
for a given damping value. The response spectrum is calculated for a 
specified vibratory motion input at the oscillators' supports.
    Safe Shutdown Earthquake Ground Motion is the vibratory ground 
motion for which certain structures, systems, and components must be 
designed pursuant to appendix S to part 50 of this chapter to remain 
functional.
    Surface deformation is distortion of geologic strata at or near the 
ground surface by the processes of folding or faulting as a result of 
various earth forces. Tectonic surface deformation is associated with 
earthquake processes.
    Testing reactor means a testing facility as defined in Sec. 50.2 of 
this chapter.

[61 FR 65175, Dec. 11, 1996]



Sec. 100.4  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed to: ATTN: Document Control Desk, 
Director, Office of Nuclear Reactor Regulation or Director, Office of 
New Reactors, as appropriate, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; by hand delivery to the NRC's offices at 
11555 Rockville Pike, Rockville, Maryland; or, where practicable, by 
electronic submission, for example, via Electronic Information Exchange, 
or CD-ROM. Electronic submissions must be made in a manner that enables 
the NRC to receive, read, authenticate, distribute, and archive the 
submission, and process and retrieve it a single page at a time. 
Detailed guidance on making electronic submissions can be obtained by 
visiting the NRC's Web site at http://www.nrc.gov/site-help/e-
submittals.html; by e-mail to [email protected]; or by writing the 
Office of the Chief Information Officer, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. The guidance discusses, among 
other topics, the formats the NRC can accept, the use of electronic 
signatures, and the treatment of nonpublic information. Copies should be 
sent to the appropriate Regional Office and Resident Inspector.

[73 FR 5726, Jan. 31, 2008, as amended at 74 FR 62686, Dec. 1, 2009; 80 
FR 74982, Dec. 1, 2015]



Sec. 100.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conductor 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0093.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 100.21, 100.23 and appendix A to this 
part.

[61 FR 65176, Dec. 11, 1996, as amended at 62 FR 52190, Oct. 6, 1997; 67 
FR 67101, Nov. 4, 2002]



     Subpart A_Evaluation Factors for Stationary Power Reactor Site 
      Applications Before January 10, 1997 and for Testing Reactors



Sec. 100.10  Factors to be considered when evaluating sites.

    Factors considered in the evaluation of sites include those relating 
both to the proposed reactor design and the characteristics peculiar to 
the site. It

[[Page 682]]

is expected that reactors will reflect through their design, 
construction and operation an extremely low probability for accidents 
that could result in release of significant quantities of radioactive 
fission products. In addition, the site location and the engineered 
features included as safeguards against the hazardous consequences of an 
accident, should one occur, should insure a low risk of public exposure. 
In particular, the Commission will take the following factors into 
consideration in determining the acceptability of a site for a power or 
testing reactor:
    (a) Characteristics of reactor design and proposed operation 
including:
    (1) Intended use of the reactor including the proposed maximum power 
level and the nature and inventory of contained radioactive materials;
    (2) The extent to which generally accepted engineering standards are 
applied to the design of the reactor;
    (3) The extent to which the reactor incorporates unique or unusual 
features having a significant bearing on the probability or consequences 
of accidental release of radioactive materials;
    (4) The safety features that are to be engineered into the facility 
and those barriers that must be breached as a result of an accident 
before a release of radioactive material to the environment can occur.
    (b) Population density and use characteristics of the site environs, 
including the exclusion area, low population zone, and population center 
distance.
    (c) Physical characteristics of the site, including seismology, 
meteorology, geology, and hydrology.
    (1) Appendix A, ``Seismic and Geologic Siting Criteria for Nuclear 
Power Plants,'' describes the nature of investigations required to 
obtain the geologic and seismic data necessary to determine site 
suitability and to provide reasonable assurance that a nuclear power 
plant can be constructed and operated at a proposed site without undue 
risk to the health and safety of the public. It describes procedures for 
determining the quantitative vibratory ground motion design basis at a 
site due to earthquakes and describes information needed to determine 
whether and to what extent a nuclear power plant need be designed to 
withstand the effects of surface faulting.
    (2) Meteorological conditions at the site and in the surrounding 
area should be considered.
    (3) Geological and hydrological characteristics of the proposed site 
may have a bearing on the consequences of an escape of radioactive 
material from the facility. Special precautions should be planned if a 
reactor is to be located at a site where a significant quantity of 
radioactive effluent might accidentally flow into nearby streams or 
rivers or might find ready access to underground water tables.
    (d) Where unfavorable physical characteristics of the site exist, 
the proposed site may nevertheless be found to be acceptable if the 
design of the facility includes appropriate and adequate compensating 
engineering safeguards.

[27 FR 3509, Apr. 12, 1962, as amended at 38 FR 31281, Nov. 13, 1973]



Sec. 100.11  Determination of exclusion area, low population zone, 
and population center distance.

    (a) As an aid in evaluating a proposed site, an applicant should 
assume a fission produce release \1\ from the core, the expected 
demonstrable leak rate from the containment and the meteorological 
conditions pertinent to his site to derive an exclusion area, a low 
population zone and population center distance. For the purpose of this 
analysis, which shall set forth the basis for the numerical values used, 
the applicant should determine the following:
---------------------------------------------------------------------------

    \1\ The fission product release assumed for these calculations 
should be based upon a major accident, hypothesized for purposes of site 
analysis or postulated from considerations of possible accidental 
events, that would result in potential hazards not exceeded by those 
from any accident considered credible. Such accidents have generally 
been assumed to result in substantial meltdown of the core with 
subsequent release of appreciable quantities of fission products.
---------------------------------------------------------------------------

    (1) An exclusion area of such size that an individual located at any 
point on its boundary for two hours immediately following onset of the 
postulated fission product release would not receive a total radiation 
dose to the

[[Page 683]]

whole body in excess of 25 rem \2\ or a total radiation dose in excess 
of 300 rem \2\ to the thyroid from iodine exposure.
---------------------------------------------------------------------------

    \2\ The whole body dose of 25 rem referred to above corresponds 
numerically to the once in a lifetime accidental or emergency dose for 
radiation workers which, according to NCRP recommendations may be 
disregarded in the determination of their radiation exposure status (see 
NBS Handbook 69 dated June 5, 1959). However, neither its use nor that 
of the 300 rem value for thyroid exposure as set forth in these site 
criteria guides are intended to imply that these numbers constitute 
acceptable limits for emergency doses to the public under accident 
conditions. Rather, this 25 rem whole body value and the 300 rem thyroid 
value have been set forth in these guides as reference values, which can 
be used in the evaluation of reactor sites with respect to potential 
reactor accidents of exceedingly low probability of occurrence, and low 
risk of public exposure to radiation.
---------------------------------------------------------------------------

    (2) A low population zone of such size that an individual located at 
any point on its outer boundary who is exposed to the radioactive cloud 
resulting from the postulated fission product release (during the entire 
period of its passage) would not receive a total radiation dose to the 
whole body in excess of 25 rem or a total radiation dose in excess of 
300 rem to the thyroid from iodine exposure.
    (3) A population center distance of at least one and one-third times 
the distance from the reactor to the outer boundary of the low 
population zone. In applying this guide, the boundary of the population 
center shall be determined upon consideration of population 
distribution. Political boundaries are not controlling in the 
application of this guide. Where very large cities are involved, a 
greater distance may be necessary because of total integrated population 
dose consideration.
    (b) For sites for multiple reactor facilities consideration should 
be given to the following:
    (1) If the reactors are independent to the extent that an accident 
in one reactor would not initiate an accident in another, the size of 
the exclusion area, low population zone and population center distance 
shall be fulfilled with respect to each reactor individually. The 
envelopes of the plan overlay of the areas so calculated shall then be 
taken as their respective boundaries.
    (2) If the reactors are interconnected to the extent that an 
accident in one reactor could affect the safety of operation of any 
other, the size of the exclusion area, low population zone and 
population center distance shall be based upon the assumption that all 
interconnected reactors emit their postulated fission product releases 
simultaneously. This requirement may be reduced in relation to the 
degree of coupling between reactors, the probability of concomitant 
accidents and the probability that an individual would not be exposed to 
the radiation effects from simultaneous releases. The applicant would be 
expected to justify to the satisfaction of the Commission the basis for 
such a reduction in the source term.
    (3) The applicant is expected to show that the simultaneous 
operation of multiple reactors at a site will not result in total 
radioactive effluent releases beyond the allowable limits of applicable 
regulations.

    Note: For further guidance in developing the exclusion area, the low 
population zone, and the population center distance, reference is made 
to Technical Information Document 14844, dated March 23, 1962, which 
contains a procedural method and a sample calculation that result in 
distances roughly reflecting current siting practices of the Commission. 
The calculations described in Technical Information Document 14844 may 
be used as a point of departure for consideration of particular site 
requirements which may result from evaluation of the characteristics of 
a particular reactor, its purpose and method of operation.

[27 FR 3509, Apr. 12, 1962, as amended at 31 FR 4670, Mar. 19, 1966; 38 
FR 1273, Jan. 11, 1973; 40 FR 8793, Mar. 3, 1975; 40 FR 26527, June 24, 
1975; 53 FR 43422, Oct. 27, 1988; 64 FR 48955, Sept. 9, 1999; 67 FR 
67101, Nov. 4, 2002]



     Subpart B_Evaluation Factors for Stationary Power Reactor Site 
                Applications on or After January 10, 1997

    Source: 61 FR 65176, Dec. 11, 1996, unless otherwise noted.

[[Page 684]]



Sec. 100.20  Factors to be considered when evaluating sites.

    The Commission will take the following factors into consideration in 
determining the acceptability of a site for a stationary power reactor:
    (a) Population density and use characteristics of the site environs, 
including the exclusion area, the population distribution, and site-
related characteristics must be evaluated to determine whether 
individual as well as societal risk of potential plant accidents is low, 
and that physical characteristics unique to the proposed site that could 
pose a significant impediment to the development of emergency plans are 
identified.
    (b) The nature and proximity of man-related hazards (e.g., airports, 
dams, transportation routes, military and chemical facilities) must be 
evaluated to establish site characteristics for use in determining 
whether a plant design can accommodate commonly occurring hazards, and 
whether the risk of other hazards is very low.
    (c) Physical characteristics of the site, including seismology, 
meteorology, geology, and hydrology.
    (1) Section 100.23, ``Geologic and seismic siting factors,'' 
describes the criteria and nature of investigations required to obtain 
the geologic and seismic data necessary to determine the suitability of 
the proposed site and the plant design bases.
    (2) Meteorological characteristics of the site that are necessary 
for safety analysis or that may have an impact upon plant design (such 
as maximum probable wind speed and precipitation) must be identified and 
characterized.
    (3) Factors important to hydrological radionuclide transport (such 
as soil, sediment, and rock characteristics, adsorption and retention 
coefficients, groundwater velocity, and distances to the nearest surface 
body of water) must be obtained from on-site measurements. The maximum 
probable flood along with the potential for seismically induced floods 
discussed in Sec. 100.23 (d)(3) must be estimated using historical 
data.

[61 FR 65176, Dec. 11, 1996, as amended at 78 FR 34250, June 7, 2013]



Sec. 100.21  Non-seismic siting criteria.

    Applications for site approval for commercial power reactors shall 
demonstrate that the proposed site meets the following criteria:
    (a) Every site must have an exclusion area and a low population 
zone, as defined in Sec. 100.3;
    (b) The population center distance, as defined in Sec. 100.3, must 
be at least one and one-third times the distance from the reactor to the 
outer boundary of the low population zone. In applying this guide, the 
boundary of the population center shall be determined upon consideration 
of population distribution. Political boundaries are not controlling in 
the application of this guide;
    (c) Site atmospheric dispersion characteristics must be evaluated 
and dispersion parameters established such that:
    (1) Radiological effluent release limits associated with normal 
operation from the type of facility proposed to be located at the site 
can be met for any individual located offsite; and
    (2) Radiological dose consequences of postulated accidents shall 
meet the criteria set forth in Sec. 50.34(a)(1) of this chapter for the 
type of facility proposed to be located at the site;
    (d) The physical characteristics of the site, including meteorology, 
geology, seismology, and hydrology must be evaluated and site 
characteristics established such that potential threats from such 
physical characteristics will pose no undue risk to the type of facility 
proposed to be located at the site;
    (e) Potential hazards associated with nearby transportation routes, 
industrial and military facilities must be evaluated and site 
characteristics established such that potential hazards from such routes 
and facilities will pose no undue risk to the type of facility proposed 
to be located at the site;
    (f) Site characteristics must be such that adequate security plans 
and measures can be developed;
    (g) Physical characteristics unique to the proposed site that could 
pose a significant impediment to the development of emergency plans must 
be identified;

[[Page 685]]

    (h) Reactor sites should be located away from very densely populated 
centers. Areas of low population density are, generally, preferred. 
However, in determining the acceptability of a particular site located 
away from a very densely populated center but not in an area of low 
density, consideration will be given to safety, environmental, economic, 
or other factors, which may result in the site being found acceptable 
\3\.
---------------------------------------------------------------------------

    \3\ Examples of these factors include, but are not limited to, such 
factors as the higher population density site having superior seismic 
characteristics, better access to skilled labor for construction, better 
rail and highway access, shorter transmission line requirements, or less 
environmental impact on undeveloped areas, wetlands or endangered 
species, etc. Some of these factors are included in, or impact, the 
other criteria included in this section.

[61 FR 65176, Dec. 11, 1996, as amended at 78 FR 34250, June 7, 2013]



Sec. 100.23  Geologic and seismic siting criteria.

    This section sets forth the principal geologic and seismic 
considerations that guide the Commission in its evaluation of the 
suitability of a proposed site and adequacy of the design bases 
established in consideration of the geologic and seismic characteristics 
of the proposed site, such that, there is a reasonable assurance that a 
nuclear power plant can be constructed and operated at the proposed site 
without undue risk to the health and safety of the public. Applications 
to engineering design are contained in appendix S to part 50 of this 
chapter.
    (a) Applicability. The requirements in paragraphs (c) and (d) of 
this section apply to applicants for an early site permit or combined 
license pursuant to Part 52 of this chapter, or a construction permit or 
operating license for a nuclear power plant pursuant to Part 50 of this 
chapter on or after January 10, 1997. However, for either an operating 
license applicant or holder whose construction permit was issued prior 
to January 10, 1997, the seismic and geologic siting criteria in 
Appendix A to Part 100 of this chapter continues to apply.
    (b) Commencement of construction. The investigations required in 
paragraph (c) of this section are not considered ``construction'' as 
defined in 10 CFR 50.10(a).
    (c) Geological, seismological, and engineering characteristics. The 
geological, seismological, and engineering characteristics of a site and 
its environs must be investigated in sufficient scope and detail to 
permit an adequate evaluation of the proposed site, to provide 
sufficient information to support evaluations performed to arrive at 
estimates of the Safe Shutdown Earthquake Ground Motion, and to permit 
adequate engineering solutions to actual or potential geologic and 
seismic effects at the proposed site. The size of the region to be 
investigated and the type of data pertinent to the investigations must 
be determined based on the nature of the region surrounding the proposed 
site. Data on the vibratory ground motion, tectonic surface deformation, 
nontectonic deformation, earthquake recurrence rates, fault geometry and 
slip rates, site foundation material, and seismically induced floods and 
water waves must be obtained by reviewing pertinent literature and 
carrying out field investigations. However, each applicant shall 
investigate all geologic and seismic factors (for example, volcanic 
activity) that may affect the design and operation of the proposed 
nuclear power plant irrespective of whether such factors are explicitly 
included in this section.
    (d) Geologic and seismic siting factors. The geologic and seismic 
siting factors considered for design must include a determination of the 
Safe Shutdown Earthquake Ground Motion for the site, the potential for 
surface tectonic and nontectonic deformations, the design bases for 
seismically induced floods and water waves, and other design conditions 
as stated in paragraph (d)(4) of this section.
    (1) Determination of the Safe Shutdown Earthquake Ground Motion. The 
Safe Shutdown Earthquake Ground Motion for the site is characterized by 
both horizontal and vertical free-field ground motion response spectra 
at the free ground surface. The Safe Shutdown Earthquake Ground Motion 
for

[[Page 686]]

the site is determined considering the results of the investigations 
required by paragraph (c) of this section. Uncertainties are inherent in 
such estimates. These uncertainties must be addressed through an 
appropriate analysis, such as a probabilistic seismic hazard analysis or 
suitable sensitivity analyses. Paragraph IV(a)(1) of appendix S to part 
50 of this chapter defines the minimum Safe Shutdown Earthquake Ground 
Motion for design.
    (2) Determination of the potential for surface tectonic and 
nontectonic deformations. Sufficient geological, seismological, and 
geophysical data must be provided to clearly establish whether there is 
a potential for surface deformation.
    (3) Determination of design bases for seismically induced floods and 
water waves. The size of seismically induced floods and water waves that 
could affect a site from either locally or distantly generated seismic 
activity must be determined.
    (4) Determination of siting factors for other design conditions. 
Siting factors for other design conditions that must be evaluated 
include soil and rock stability, liquefaction potential, natural and 
artificial slope stability, cooling water supply, and remote safety-
related structure siting. Each applicant shall evaluate all siting 
factors and potential causes of failure, such as, the physical 
properties of the materials underlying the site, ground disruption, and 
the effects of vibratory ground motion that may affect the design and 
operation of the proposed nuclear power plant.

[61 FR 65176, Dec. 11, 1996, as amended at 72 FR 57447, Oct. 9, 2007]



 Sec. Appendix A to Part 100--Seismic and Geologic Siting Criteria for 
                          Nuclear Power Plants

                               i. purpose

    General Design Criterion 2 of Appendix A to part 50 of this chapter 
requires that nuclear power plant structures, systems, and components 
important to safety be designed to withstand the effects of natural 
phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, 
and seiches without loss of capability to perform their safety 
functions. It is the purpose of these criteria to set forth the 
principal seismic and geologic considerations which guide the Commission 
in its evaluation of the suitability of proposed sites for nuclear power 
plants and the suitability of the plant design bases established in 
consideration of the seismic and geologic characteristics of the 
proposed sites.
    These criteria are based on the limited geophysical and geological 
information available to date concerning faults and earthquake 
occurrence and effect. They will be revised as necessary when more 
complete information becomes available.

                                ii. scope

    These criteria, which apply to nuclear power plants, describe the 
nature of the investigations required to obtain the geologic and seismic 
data necessary to determine site suitability and provide reasonable 
assurance that a nuclear power plant can be constructed and operated at 
a proposed site without undue risk to the health and safety of the 
public. They describe procedures for determining the quantitative 
vibratory ground motion design basis at a site due to earthquakes and 
describe information needed to determine whether and to what extent a 
nuclear power plant need be designed to withstand the effects of surface 
faulting. Other geologic and seismic factors required to be taken into 
account in the siting and design of nuclear power plants are identified.
    The investigations described in this appendix are within the scope 
of investigations permitted by Sec. 50.10(a)(2)(ii) of this chapter.
    Each applicant for a construction permit shall investigate all 
seismic and geologic factors that may affect the design and operation of 
the proposed nuclear power plant irrespective of whether such factors 
are explicitly included in these criteria. Additional investigations 
and/or more conservative determinations than those included in these 
criteria may be required for sites located in areas having complex 
geology or in areas of high seismicity. If an applicant believes that 
the particular seismology and geology of a site indicate that some of 
these criteria, or portions thereof, need not be satisfied, the specific 
sections of these criteria should be identified in the license 
application, and supporting data to justify clearly such departures 
should be presented.
    These criteria do not address investigations of volcanic phenomena 
required for sites located in areas of volcanic activity. Investigations 
of the volcanic aspects of such sites will be determined on a case-by-
case basis.

                            iii. definitions

    As used in these criteria:
    (a) The magnitude of an earthquake is a measure of the size of an 
earthquake and is related to the energy released in the form of

[[Page 687]]

seismic waves. Magnitude means the numerical value on a Richter scale.
    (b) The intensity of an earthquake is a measure of its effects on 
man, on man-built structures, and on the earth's surface at a particular 
location. Intensity means the numerical value on the Modified Mercalli 
scale.
    (c) The Safe Shutdown Earthquake \1\ is that earthquake which is 
based upon an evaluation of the maximum earthquake potential considering 
the regional and local geology and seismology and specific 
characteristics of local subsurface material. It is that earthquake 
which produces the maximum vibratory ground motion for which certain 
structures, systems, and components are designed to remain functional. 
These structures, systems, and components are those necessary to assure:
---------------------------------------------------------------------------

    \1\ The Safe Shutdown Earthquake defines that earthquake which has 
commonly been referred to as the Design Basis Earthquake.
---------------------------------------------------------------------------

    (1) The integrity of the reactor coolant pressure boundary,
    (2) The capability to shut down the reactor and maintain it in a 
safe shutdown condition, or
    (3) The capability to prevent or mitigate the consequences of 
accidents which could result in potential offsite exposures comparable 
to the guideline exposures of this part.
    (d) The Operating Basis Earthquake is that earthquake which, 
considering the regional and local geology and seismology and specific 
characteristics of local subsurface material, could reasonably be 
expected to affect the plant site during the operating life of the 
plant; it is that earthquake which produces the vibratory ground motion 
for which those features of the nuclear power plant necessary for 
continued operation without undue risk to the health and safety of the 
public are designed to remain functional.
    (e) A fault is a tectonic structure along which differential 
slippage of the adjacent earth materials has occurred parallel to the 
fracture plane. It is distinct from other types of ground disruptions 
such as landslides, fissures, and craters. A fault may have gouge or 
breccia between its two walls and includes any associated monoclinal 
flexure or other similar geologic structural feature.
    (f) Surface faulting is differential ground displacement at or near 
the surface caused directly by fault movement and is distinct from 
nontectonic types of ground disruptions, such as landslides, fissures, 
and craters.
    (g) A capable fault is a fault which has exhibited one or more of 
the following characteristics:
    (1) Movement at or near the ground surface at least once within the 
past 35,000 years or movement of a recurring nature within the past 
500,000 years.
    (2) Macro-seismicity instrumentally determined with records of 
sufficient precision to demonstrate a direct relationship with the 
fault.
    (3) A structural relationship to a capable fault according to 
characteristics (1) or (2) of this paragraph such that movement on one 
could be reasonably expected to be accompanied by movement on the other.
    In some cases, the geologic evidence of past activity at or near the 
ground surface along a particular fault may be obscured at a particular 
site. This might occur, for example, at a site having a deep overburden. 
For these cases, evidence may exist elsewhere along the fault from which 
an evaluation of its characteristics in the vicinity of the site can be 
reasonably based. Such evidence shall be used in determining whether the 
fault is a capable fault within this definition.
    Notwithstanding the foregoing paragraphs III(g) (1), (2) and (3), 
structural association of a fault with geologic structural features 
which are geologically old (at least pre-Quaternary) such as many of 
those found in the Eastern region of the United States shall, in the 
absence of conflicting evidence, demonstrate that the fault is not a 
capable fault within this definition.
    (h) A tectonic province is a region of the North American continent 
characterized by a relative consistency of the geologic structural 
features contained therein.
    (i) A tectonic structure is a large scale dislocation or distortion 
within the earth's crust. Its extent is measured in miles.
    (j) A zone requiring detailed faulting investigation is a zone 
within which a nuclear power reactor may not be located unless a 
detailed investigation of the regional and local geologic and seismic 
characteristics of the site demonstrates that the need to design for 
surface faulting has been properly determined.
    (k) The control width of a fault is the maximum width of the zone 
containing mapped fault traces, including all faults which can be 
reasonably inferred to have experienced differential movement during 
Quaternary times and which join or can reasonably be inferred to join 
the main fault trace, measured within 10 miles along the fault's trend 
in both directions from the point of nearest approach to the site. (See 
Figure 1 of this appendix.)
    (l) A response spectrum is a plot of the maximum responses 
(acceleration, velocity or displacement) of a family of idealized 
single-degree-of-freedom damped oscillators against natural frequencies 
(or periods) of the oscillators to a specified vibratory motion input at 
their supports.

[[Page 688]]

                       iv. required investigations

    The geologic, seismic and engineering characteristics of a site and 
its environs shall be investigated in sufficient scope and detail to 
provide reasonable assurance that they are sufficiently well understood 
to permit an adequate evaluation of the proposed site, and to provide 
sufficient information to support the determinations required by these 
criteria and to permit adequate engineering solutions to actual or 
potential geologic and seismic effects at the proposed site. The size of 
the region to be investigated and the type of data pertinent to the 
investigations shall be determined by the nature of the region 
surrounding the proposed site. The investigations shall be carried out 
by a review of the pertinent literature and field investigations and 
shall include the steps outlined in paragraphs (a) through (c) of this 
section.
    (a) Required Investigation for Vibratory Ground Motion. The purpose 
of the investigations required by this paragraph is to obtain 
information needed to describe the vibratory ground motion produced by 
the Safe Shutdown Earthquake. All of the steps in paragraphs (a)(5) 
through (a)(8) of this section need not be carried out if the Safe 
Shutdown Earthquake can be clearly established by investigations and 
determinations of a lesser scope. The investigations required by this 
paragraph provide an adequate basis for selection of an Operating Basis 
Earthquake. The investigations shall include the following:
    (1) Determination of the lithologic, stratigraphic, hydrologic, and 
structural geologic conditions of the site and the region surrounding 
the site, including its geologic history;
    (2) Identification and evaluation of tectonic structures underlying 
the site and the region surrounding the site, whether buried or 
expressed at the surface. The evaluation should consider the possible 
effects caused by man's activities such as withdrawal of fluid from or 
addition of fluid to the subsurface, extraction of minerals, or the 
loading effects of dams or reservoirs;
    (3) Evaluation of physical evidence concerning the behavior during 
prior earthquakes of the surficial geologic materials and the substrata 
underlying the site from the lithologic, stratigraphic, and structural 
geologic studies;
    (4) Determination of the static and dynamic engineering properties 
of the materials underlying the site. Included should be properties 
needed to determine the behavior of the underlying material during 
earthquakes and the characteristics of the underlying material in 
transmitting earthquake-induced motions to the foundations of the plant, 
such as seismic wave velocities, density, water content, porosity, and 
strength;
    (5) Listing of all historically reported earthquakes which have 
affected or which could reasonably be expected to have affected the 
site, including the date of occurrence and the following measured or 
estimated data: magnitude or highest intensity, and a plot of the 
epicenter or location of highest intensity. Where historically reported 
earthquakes could have caused a maximum ground acceleration of at least 
one-tenth the acceleration of gravity (0.1g) at the foundations of the 
proposed nuclear power plant structures, the acceleration or intensity 
and duration of ground shaking at these foundations shall also be 
estimated. Since earthquakes have been reported in terms of various 
parameters such as magnitude, intensity at a given location, and effect 
on ground, structures, and people at a specific location, some of these 
data may have to be estimated by use of appropriate empirical 
relationships. The comparative characteristics of the material 
underlying the epicentral location or region of highest intensity and of 
the material underlying the site in transmitting earthquake vibratory 
motion shall be considered;
    (6) Correlation of epicenters or locations of highest intensity of 
historically reported earthquakes, where possible, with tectonic 
structures any part of which is located within 200 miles of the site. 
Epicenters or locations of highest intensity which cannot be reasonably 
correlated with tectonic structures shall be identified with tectonic 
provinces any part of which is located within 200 miles of the site;
    (7) For faults, any part of which is within 200 miles \2\ of the 
site and which may be of significance in establishing the Safe Shutdown 
Earthquake, determination of whether these faults are to be considered 
as capable faults. \3 4\ This determination is required in order to 
permit appropriate consideration of the geologic history of such faults 
in establishing the Safe Shutdown Earthquake. For guidance in 
determining which faults may be

[[Page 689]]

of significance in determining the Safe Shutdown Earthquake, table 1 of 
this appendix presents the minimum length of fault to be considered 
versus distance from site. Capable faults of lesser length than those 
indicated in table 1 and faults which are not capable faults need not be 
considered in determining the Safe Shutdown Earthquake, except where 
unusual circumstances indicate such consideration is appropriate;
---------------------------------------------------------------------------

    \2\ If the Safe Shutdown Earthquake can be associated with a fault 
closer than 200 miles to the site, the procedures of paragraphs (a)(7) 
and (a)(8) of this section need not be carried out for successively more 
remote faults.
    \3\ In the absence of absolute dating, evidence of recency of 
movement may be obtained by applying relative dating technique to 
ruptured, offset, warped or otherwise structurally disturbed surface or 
near surface materials or geomorphic features.
    \4\ The applicant shall evaluate whether or not a fault is a capable 
fault with respect to the characteristics outlined in paragraphs 
III(g)(1), (2), and (3) by conducting a reasonable investigation using 
suitable geologic and geophysical techniques.

                                 Table 1
------------------------------------------------------------------------
                                                                Minimum
                                                              length \1\
------------------------------------------------------------------------
Distance from the site (miles):
  0 to 20...................................................           1
  Greater than 20 to 50.....................................           5
  Greater than 50 to 100....................................          10
  Greater than 100 to 150...................................          20
  Greater than 150 to 200...................................          40
------------------------------------------------------------------------
\1\ Minimum length of fault (miles) which shall be considered in
  establishing Safe Shutdown Earthquake.

    (8) For capable faults, any part of which is within 200 miles \2\ of 
the site and which may be of significance in establishing the Safe 
Shutdown Earthquake, determination of:
    (i) The length of the fault;
    (ii) The relationship of the fault to regional tectonic structures; 
and
    (iii) The nature, amount, and geologic history of displacements 
along the fault, including particularly the estimated amount of the 
maximum Quaternary displacement related to any one earthquake along the 
fault.
    (b) Required Investigation for Surface Faulting. The purpose of the 
investigations required by this paragraph is to obtain information to 
determine whether and to what extent the nuclear power plant need be 
designed for surface faulting. If the design basis for surface faulting 
can be clearly established by investigations of a lesser scope, not all 
of the steps in paragraphs (b)(4) through (b)(7) of this section need be 
carried out. The investigations shall include the following:
    (1) Determination of the lithologic, stratigraphic, hydrologic, and 
structural geologic conditions of the site and the area surrounding the 
site, including its geologic history;
    (2) Evaluation of tectonic structures underlying the site, whether 
buried or expressed at the surface, with regard to their potential for 
causing surface displacement at or near the site. The evaluation shall 
consider the possible effects caused by man's activities such as 
withdrawal of fluid from or addition of fluid to the subsurface, 
extraction of minerals, or the loading effects of dams or reservoirs;
    (3) Determination of geologic evidence of fault offset at or near 
the ground surface at or near the site;
    (4) For faults greater than 1000 feet long, any part of which is 
within 5 miles \5\ of the site, determination of whether these faults 
are to be considered as capable faults; \6 7\
---------------------------------------------------------------------------

    \5\ If the design basis for surface faulting can be determined from 
a fault closer than 5 miles to the site, the procedures of paragraphs 
(b)(4) through (b)(7) of this section need not be carried out for 
successively more remote faults.
    \6\ In the absence of absolute dating, evidence of recency of 
movement may be obtained by applying relative dating techniques to 
ruptured, offset, warped or otherwise structurally disturbed surface of 
near-surface materials or geomorphic features.
    \7\ The applicant shall evaluate whether or not a fault is a capable 
fault with respect to the characteristics outlined in paragraphs 
III(g)(1), (2), and (3) by conducting a reasonable investigation using 
suitable geological and geophysical techniques.
---------------------------------------------------------------------------

    (5) Listing of all historically reported earthquakes which can 
reasonably be associated with capable faults greater than 1000 feet 
long, any part of which is within 5 miles \5\ of the site, including the 
date of occurrence and the following measured or estimated data: 
magnitude or highest intensity, and a plot of the epicenter or region of 
highest intensity;
    (6) Correlation of epicenters or locations of highest intensity of 
historically reported earthquakes with capable faults greater than 1000 
feet long, any part of which is located within 5 miles \5\ of the site;
    (7) For capable faults greater than 1000 feet long, any part of 
which is within 5 miles \5\ of the site, determination of:
    (i) The length of the fault;
    (ii) The relationship of the fault to regional tectonic structures;
    (iii) The nature, amount, and geologic history of displacements 
along the fault, including particularly the estimated amount of the 
maximum Quaternary displacement related to any one earthquake along the 
fault; and
    (iv) The outer limits of the fault established by mapping Quaternary 
fault traces for 10 miles along its trend in both directions from the 
point of its nearest approach to the site.
    (c) Required Investigation for Seismically Induced Floods and Water 
Waves. (1) For coastal sites, the investigations shall include the 
determination of:
    (i) Information regarding distantly and locally generated waves or 
tsunami which have affected or could have affected the site. Available 
evidence regarding the runup and drawdown associated with historic 
tsunami in the same coastal region as the site shall also be included;
    (ii) Local features of coastal topography which might tend to modify 
tsunami runup

[[Page 690]]

or drawdown. Appropriate available evidence regarding historic local 
modifications in tsunami runup or drawndown at coastal locations having 
topography similar to that of the site shall also be obtained; and
    (iii) Appropriate geologic and seismic evidence to provide 
information for establishing the design basis for seismically induced 
floods or water waves from a local offshore earthquake, from local 
offshore effects of an onshore earthquake, or from coastal subsidence. 
This evidence shall be determined, to the extent practical, by a 
procedure similar to that required in paragraphs (a) and (b) of this 
section. The probable slip characteristics of offshore faults shall also 
be considered as well as the potential for offshore slides in submarine 
material.
    (2) For sites located near lakes and rivers, investigations similar 
to those required in paragraph (c)(1) of this section shall be carried 
out, as appropriate, to determine the potential for the nuclear power 
plant to be exposed to seismically induced floods and water waves as, 
for example, from the failure during an earthquake of an upstream dam or 
from slides of earth or debris into a nearby lake.

                  v. seismic and geologic design bases

    (a) Determination of Design Basis for Vibratory Ground Motion. The 
design of each nuclear power plant shall take into account the potential 
effects of vibratory ground motion caused by earthquakes. The design 
basis for the maximum vibratory ground motion and the expected vibratory 
ground motion should be determined through evaluation of the seismology, 
geology, and the seismic and geologic history of the site and the 
surrounding region. The most severe earthquakes associated with tectonic 
structures or tectonic provinces in the region surrounding the site 
should be identified, considering those historically reported 
earthquakes that can be associated with these structures or provinces 
and other relevant factors. If faults in the region surrounding the site 
are capable faults, the most severe earthquakes associated with these 
faults should be determined by also considering their geologic history. 
The vibratory ground motion at the site should be then determined by 
assuming that the epicenters or locations of highest intensity of the 
earthquakes are situated at the point on the tectonic structures or 
tectonic provinces nearest to the site. The earthquake which could cause 
the maximum vibratory ground motion at the site should be designated the 
Safe Shutdown Earthquake. The specific procedures for determining the 
design basis for vibratory ground motion are given in the following 
paragraphs.
    (1) Determination of Safe Shutdown Earthquake. The Safe Shutdown 
Earthquake shall be identified through evaluation of seismic and 
geologic information developed pursuant to the requirements of paragraph 
IV(a), as follows:
    (i) The historic earthquakes of greatest magnitude or intensity 
which have been correlated with tectonic structures pursuant to the 
requirements of paragraph (a)(6) of section IV shall be determined. In 
addition, for capable faults, the information required by paragraph 
(a)(8) of section IV shall also be taken into account in determining the 
earthquakes of greatest magnitude related to the faults. The magnitude 
or intensity of earthquakes based on geologic evidence may be larger 
than that of the maximum earthquakes historically recorded. The 
accelerations at the site shall be determined assuming that the 
epicenters of the earthquakes of greatest magnitude or the locations of 
highest intensity related to the tectonic structures are situated at the 
point on the structures closest to the site;
    (ii) Where epicenters or locations of highest intensity of 
historically reported earthquakes cannot be reasonably related to 
tectonic structures but are identified pursuant to the requirements of 
paragraph (a)(6) of section IV with tectonic provinces in which the site 
is located, the accelerations at the site shall be determined assuming 
that these earthquakes occur at the site;
    (iii) Where epicenters or locations of the highest intensity of 
historically reported earthquakes cannot be reasonably related to 
tectonic structures but are identified pursuant to the requirements of 
paragraph (a)(6) of section IV with tectonic provinces in which the site 
is not located, the accelerations at the site shall be determined 
assuming that the epicenters or locations of highest intensity of these 
earthquakes are at the closest point to the site on the boundary of the 
tectonic province;
    (iv) The earthquake producing the maximum vibratory acceleration at 
the site, as determined from paragraph (a)(1)(i) through (iii) of this 
section shall be designated the Safe Shutdown Earthquake for vibratory 
ground motion, except as noted in paragraph (a)(1)(v) of this section. 
The characteristics of the Safe Shutdown Earthquake shall be derived 
from more than one earthquake determined from paragraph (a)(1)(i) 
through (iii) of this section, where necessary to assure that the 
maximum vibratory acceleration at the site throughout the frequency 
range of interest is included. In the case where a causative fault is 
near the site, the effect of proximity of an earthquake on the spectral 
characteristics of the Safe Shutdown Earthquake shall be taken into 
account. The procedures in paragraphs (a)(1)(i) through (a)(1)(iii) of 
this section shall be applied in a conservative manner. The 
determinations carried out in accordance with

[[Page 691]]

paragraphs (a)(1)(ii) and (a)(1)(iii) shall assure that the safe 
shutdown earthquake intensity is, as a minimum, equal to the maximum 
historic earthquake intensity experienced within the tectonic province 
in which the site is located. In the event that geological and 
seismological data warrant, the Safe Shutdown Earthquake shall be larger 
than that derived by use of the procedures set forth in section IV and V 
of the appendix. The maximum vibratory accelerations of the Safe 
Shutdown Earthquake at each of the various foundation locations of the 
nuclear power plant structures at a given site shall be determined 
taking into account the characteristics of the underlying soil material 
in transmitting the earthquake-induced motions, obtained pursuant to 
paragraphs (a)(1), (3), and (4) of section IV. The Safe Shutdown 
Earthquake shall be defined by response spectra corresponding to the 
maximum vibratory accelerations as outlined in paragraph (a) of section 
VI; and
    (v) Where the maximum vibratory accelerations of the Safe Shutdown 
Earthquake at the foundations of the nuclear power plant structures are 
determined to be less than one-tenth the acceleration of gravity (0.1 g) 
as a result of the steps required in paragraphs (a)(1)(i) through (iv) 
of this section, it shall be assumed that the maximum vibratory 
accelerations of the Safe Shutdown Earthquake at these foundations are 
at least 0.1 g.
    (2) Determination of Operating Basis Earthquake. The Operating Basis 
Earthquake shall be specified by the applicant after considering the 
seismology and geology of the region surrounding the site. If vibratory 
ground motion exceeding that of the Operating Basis Earthquake occurs, 
shutdown of the nuclear power plant will be required. Prior to resuming 
operations, the licensee will be required to demonstrate to the 
Commission that no functional damage has occurred to those features 
necessary for continued operation without undue risk to the health and 
safety of the public.
    The maximum vibratory ground acceleration of the Operating Basis 
Earthquake shall be at least one-half the maximum vibratory ground 
acceleration of the Safe Shutdown Earthquake.
    (b) Determination of Need to Design for Surface Faulting. In order 
to determine whether a nuclear power plant is required to be designed to 
withstand the effects of surface faulting, the location of the nuclear 
power plant with respect to capable faults shall be considered. The area 
over which each of these faults has caused surface faulting in the past 
is identified by mapping its fault traces in the vicinity of the site. 
The fault traces are mapped along the trend of the fault for 10 miles in 
both directions from the point of its nearest approach to the nuclear 
power plant because, for example, traces may be obscured along portions 
of the fault. The maximum width of the mapped fault traces, called the 
control width, is then determined from this map. Because surface 
faulting has sometimes occurred beyond the limit of mapped fault traces 
or where fault traces have not been previously recognized, the control 
width of the fault is increased by a factor which is dependent upon the 
largest potential earthquake related to the fault. This larger width 
delineates a zone, called the zone requiring detailed faulting 
investigation, in which the possibility of surface faulting is to be 
determined. The following paragraphs outline the specific procedures for 
determining the zone requiring detailed faulting investigation for a 
capable fault.
    (1) Determination of Zone Requiring Detailed Faulting Investigation. 
The zone requiring detailed faulting investigation for a capable fault 
which was investigated pursuant to the requirement of paragraph (b)(7) 
of section IV shall be determined through use of the following table:

Table 2--Determination of Zone Requiring Detailed Faulting Investigation
------------------------------------------------------------------------
                                               Width of zone requiring
          Magnitude of earthquake                 detailed faulting
                                             investigation (See fig. 1)
------------------------------------------------------------------------
Less than 5.5.............................  1 x control width.
5.5-6.4...................................  2 x control width.
6.5-7.5...................................  3 x control width.
Greater than 7.5..........................  4 x control width.
------------------------------------------------------------------------

    The largest magnitude earthquake related to the fault shall be used 
in table 2. This earthquake shall be determined from the information 
developed pursuant to the requirements of paragraph (b) of Section IV 
for the fault, taking into account the information required by paragraph 
(b)(7) of section IV. The control width used in table 2 is determined by 
mapping the outer limits of the fault traces from information developed 
pursuant to paragraph (b)(7)(iv) of section IV. The control width shall 
be used in table 2 unless the characteristics of the fault are obscured 
for a significant portion of the 10 miles on either side of the point of 
nearest approach to the nuclear power plant. In this event, the use in 
table 2 of the width of mapped fault traces more than 10 miles from the 
point of nearest approach to the nuclear power plant may be appropriate.
    The zone requiring detailed faulting investigation, as determined 
from table 2, shall be used for the fault except where:
    (i) The zone requiring detailed faulting investigation from table 2 
is less than one-half mile in width. In this case the zone shall be at 
least one-half mile in width; or
    (ii) Definitive evidence concerning the regional and local 
characteristics of the fault

[[Page 692]]

justifies use of a different value. For example, thrust or bedding-plane 
faults may require an increase in width of the zone to account for the 
projected dip of the fault plane; or
    (iii) More detailed three-dimensional information, such as that 
obtained from precise investigative techniques, may justify the use of a 
narrower zone. Possible examples of such techniques are the use of 
accurate records from closely spaced drill holes or from closely spaced, 
high-resolution offshore geophysical surveys.
    In delineating the zone requiring detailed faulting investigation 
for a fault, the center of the zone shall coincide with the center of 
the fault at the point of nearest approach of the fault to the nuclear 
power plant as illustrated in figure 1.
    (c) Determination of Design Bases for Seismically Induced Floods and 
Water Waves. The size of seismically induced floods and water waves 
which could affect a site from either locally or distantly generated 
seismic activity shall be determined, taking into consideration the 
results of the investigation required by paragraph (c) of section IV. 
Local topographic characteristics which might tend to modify the 
possible runup and drawdown at the site shall be considered. Adverse 
tide conditions shall also be taken into account in determining the 
effect of the floods and waves on the site. The characteristics of the 
earthquake to be used in evaluating the offshore effects of local 
earthquakes shall be determined by a procedure similar to that used to 
determine the characteristics of the Safe Shutdown Earthquake in 
paragraph V(a).
    (d) Determination of Other Design Conditions--(1) Soil Stability. 
Vibratory ground motion associated with the Safe Shutdown Earthquake can 
cause soil instability due to ground disruption such as fissuring, 
differential consolidation, liquefaction, and cratering which is not 
directly related to surface faulting. The following geologic features 
which could affect the foundations of the proposed nuclear power plant 
structures shall be evaluated, taking into account the information 
concerning the physical properties of materials underlying the site 
developed pursuant to paragraphs (a)(1), (3), and (4) of section IV and 
the effects of the Safe Shutdown Earthquake:
    (i) Areas of actual or potential surface or subsurface subsidence, 
uplift, or collapse resulting from:
    (a) Natural features such as tectonic depressions and cavernous or 
karst terrains, particularly those underlain by calcareous or other 
soluble deposits;
    (b) Man's activities such as withdrawal of fluid from or addition of 
fluid to the subsurface, extraction of minerals, or the loading effects 
of dams or reservoirs; and
    (c) Regional deformation.
    (ii) Deformational zones such as shears, joints, fractures, folds, 
or combinations of these features.
    (iii) Zones of alteration or irregular weathering profiles and zones 
of structural weakness composed of crushed or disturbed materials.
    (iv) Unrelieved residual stresses in bedrock.
    (v) Rocks or soils that might be unstable because of their 
mineralogy, lack of consolidation, water content, or potentially 
undesirable response to seismic or other events. Seismic response 
characteristics to be considered shall include liquefaction, thixotropy, 
differential consolidation, cratering, and fissuring.
    (2) Slope stability. Stability of all slopes, both natural and 
artificial, the failure of which could adversely affect the nuclear 
power plant, shall be considered. An assessment shall be made of the 
potential effects of erosion or deposition and of combinations of 
erosion or deposition with seismic activity, taking into account 
information concerning the physical property of the materials underlying 
the site developed pursuant to paragraph (a)(1), (3), and (4) of section 
IV and the effects of the Safe Shutdown Earthquake.
    (3) Cooling water supply. Assurance of adequate cooling water supply 
for emergency and long-term shutdown decay heat removal shall be 
considered in the design of the nuclear power plant, taking in to 
account information concerning the physical properties of the materials 
underlying the site developed pursuant to paragraphs (a)(1), (3), and 
(4) of section IV and the effects of the Safe Shutdown Earthquake and 
the design basis for surface faulting. Consideration of river blockage 
or diversion or other failures which may block the flow of cooling 
water, coastal uplift or subsidence, or tsunami runup and drawdown, and 
failure of dams and intake structures shall be included in the 
evaluation, where appropriate.
    (4) Distant structures. Those structures which are not located in 
the immediate vicinity of the site but which are safety related shall be 
designed to withstand the effect of the Safe Shutdown Earthquake and the 
design basis for surface faulting determined on a comparable basis to 
that of the nuclear power plant, taking into account the material 
underlying the structures and the different location with respect to 
that of the site.

                  vi. application to engineering design

    (a) Vibratory ground motion--(1) Safe Shutdown Earthquake. The 
vibratory ground motion produced by the Safe Shutdown Earthquake shall 
be defined by response spectra corresponding to the maximum vibratory 
accelerations at the elevations of the foundations of the nuclear power 
plant structures

[[Page 693]]

determine pursuant to paragraph (a)(1) of section V. The response 
spectra shall relate the response of the foundations of the nuclear 
power plant structures to the vibratory ground motion, considering such 
foundations to be single-degree-of-freedom damped oscillators and 
neglecting soil-structure interaction effects. In view of the limited 
data available on vibratory ground motions of strong earthquakes, it 
usually will be appropriate that the response spectra be smoothed design 
spectra developed from a series of response spectra related to the 
vibratory motions caused by more than one earthquake.
    The nuclear power plant shall be designed so that, if the Safe 
Shutdown Earthquake occurs, certain structures, systems, and components 
will remain functional. These structures, systems, and components are 
those necessary to assure (i) the integrity of the reactor coolant 
pressure boundary, (ii) the capability to shut down the reactor and 
maintain it in a safe condition, or (iii) the capability to prevent or 
mitigate the consequences of accidents which could result in potential 
offsite exposures comparable to the guideline exposures of this part. In 
addition to seismic loads, including aftershocks, applicable concurrent 
functional and accident-induced loads shall be taken into account in the 
design of these safety-related structures, systems, and components. The 
design of the nuclear power plant shall also take into account the 
possible effects of the Safe Shutdown Earthquake on the facility 
foundations by ground disruption, such as fissuring, differential 
consolidation, cratering, liquefaction, and landsliding, as required in 
paragraph (d) of section V.
    The engineering method used to insure that the required safety 
functions are maintained during and after the vibratory ground motion 
associated with the Safe Shutdown Earthquake shall involve the use of 
either a suitable dynamic analysis or a suitable qualification test to 
demonstrate that structures, systems and components can withstand the 
seismic and other concurrent loads, except where it can be demonstrated 
that the use of an equivalent static load method provides adequate 
conservatism.
    The analysis or test shall take into account soil-structure 
interaction effects and the expected duration of vibratory motion. It is 
permissible to design for strain limits in excess of yield strain in 
some of these safety-related structures, systems, and components during 
the Safe Shutdown Earthquake and under the postulated concurrent 
conditions, provided that the necessary safety functions are maintained.
    (2) Operating Basis Earthquake. The Operating Basis Earthquake shall 
be defined by response spectra. All structures, systems, and components 
of the nuclear power plant necessary for continued operation without 
undue risk to the health and safety of the public shall be designed to 
remain functional and within applicable stress and deformation limits 
when subjected to the effects of the vibratory motion of the Operating 
Basis Earthquake in combination with normal operating loads. The 
engineering method used to insure that these structures, systems, and 
components are capable of withstanding the effects of the Operating 
Basis Earthquake shall involve the use of either a suitable dynamic 
analysis or a suitable qualification test to demonstrate that the 
structures, systems and components can withstand the seismic and other 
concurrent loads, except where it can be demonstrated that the use of an 
equivalent static load method provides adequate conservatism. The 
analysis or test shall take into account soil-structure interaction 
effects and the expected duration of vibratory motion.
    (3) Required Seismic instrumentation. Suitable instrumentation shall 
be provided so that the seismic response of nuclear power plant features 
important to safety can be determined promptly to permit comparison of 
such response with that used as the design basis. Such a comparison is 
needed to decide whether the plant can continue to be operated safely 
and to permit such timely action as may be appropriate.
    These criteria do not address the need for instrumentation that 
would automatically shut down a nuclear power plant when an earthquake 
occurs which exceeds a predetermined intensity. The need for such 
instrumentation is under consideration.
    (b) Surface Faulting. (1) If the nuclear power plant is to be 
located within the zone requiring detailed faulting investigation, a 
detailed investigation of the regional and local geologic and seismic 
characteristics of the site shall be carried out to determine the need 
to take into account surface faulting in the design of the nuclear power 
plant. Where it is determined that surface faulting need not be taken 
into account, sufficient data to clearly justify the determination shall 
be presented in the license application.
    (2) Where it is determined that surface faulting must be taken into 
account, the applicant shall, in establishing the design basis for 
surface faulting on a site take into account evidence concerning the 
regional and local geologic and seismic characteristics of the site and 
from any other relevant data.
    (3) The design basis for surface faulting shall be taken into 
account in the design of the nuclear power plant by providing reasonable 
assurance that in the event of such displacement during faulting certain 
structures, systems, and components will remain functional. These 
structures, systems, and components are those necessary to assure (i) 
the integrity of the reactor coolant pressure boundary, (ii) the 
capability to shut down

[[Page 694]]

the reactor and maintain it in a safe shutdown condition, or (iii) the 
capability to prevent or mitigate the consequences of accidents which 
could result in potential offsite exposures comparable to the guideline 
exposures of this part. In addition to seismic loads, including 
aftershocks, applicable concurrent functional and accident-induced loads 
shall be taken into account in the design of such safety features. The 
design provisions shall be based on an assumption that the design basis 
for surface faulting can occur in any direction and azimuth and under 
any part of the nuclear power plant unless evidence indicates this 
assumption is not appropriate, and shall take into account the estimated 
rate at which the surface faulting may occur.
    (c) Seismically Induced Floods and Water Waves and Other Design 
Conditions. The design basis for seismically induced floods and water 
waves from either locally or distantly generated seismic activity and 
other design conditions determined pursuant to paragraphs (c) and (d) of 
section V, shall be taken into account in the design of the nuclear 
power plant so as to prevent undue risk to the health and safety of the 
public.
[GRAPHIC] [TIFF OMITTED] TC22SE91.002

  Figure 1--Diagrammatic Illustration of Delineation of Width of Zone 
 Requiring Detailed Faulting Investigations For Specific Nuclear Power 
                             Plant Location.

(Sec. 201, Pub. L. 93-438, 88 Stat. 1243 (42 U.S.C. 5841))

[38 FR 31281, Nov. 13, 1973, as amended at 38 FR 32575, Nov. 27, 1973; 
42 FR 2052, Jan. 10, 1977; 78 FR 34250, June 7, 2013]



PART 110_EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL--
Table of Contents



                      Subpart A_General Provisions

Sec.
110.1 Purpose and scope.
110.2 Definitions.
110.3 Interpretations.
110.4 Communications.
110.5 Licensing requirements.
110.6 Retransfers.
110.7 Information collection requirements: OMB approval.
110.7a Completeness and accuracy of information.
110.7b Deliberate misconduct.
110.8 List of nuclear facilities and equipment under NRC export 
          licensing authority.
110.9 List of Nuclear Material under NRC export licensing authority.
110.9a List of nuclear equipment and material under NRC import licensing 
          authority.

                          Subpart B_Exemptions

110.10 General.
110.11 Export of IAEA safeguards samples.

                           Subpart C_Licenses

110.19 Types of licenses.
110.20 General license information.
110.21 General license for the export of special nuclear material.
110.22 General license for the export of source material.
110.23 General license for the export of byproduct material.
110.24 General license for the export of deuterium.
110.25 [Reserved]
110.26 General license for the export of nuclear reactor components.
110.27 General license for imports.
110.28 Embargoed destinations.
110.29 Restricted destinations.
110.30 Members of the Nuclear Suppliers Group.
110.31 Application for a specific license.
110.32 Information required in an application for a specific license/NRC 
          Form 7.

                Subpart D_Review of License Applications

110.40 Commission review.
110.41 Executive Branch review.
110.42 Export licensing criteria.
110.43 Import licensing criteria.
110.44 Physical security standards.
110.45 Issuance or denial of licenses.
110.46 Conduct resulting in termination of nuclear exports.

[[Page 695]]

             Subpart E_License Terms and Related Provisions

110.50 Terms.
110.51 Amendment and renewal of licenses.
110.52 Revocation, suspension, and modification.
110.53 United States address, records, and inspections.
110.54 Reporting requirements.

                  Subpart F_Violations and Enforcement

110.60 Violations.
110.61 Notice of violation.
110.62 Order to show cause.
110.63 Order for revocation, suspension, or modification.
110.64 Civil penalty.
110.65 Settlement and compromise.
110.66 Enforcement hearing.
110.67 Criminal penalties.

 Subpart G_Public Notification and Availability of Documents and Records

110.70 Public notice of receipt of an application.
110.71 Notice of withdrawal of an application.
110.72 Public availability of documents.
110.73 Availability of NRC records.

      Subpart H_Public Participation Procedures Concerning License 
                              Applications

110.80 Basis for hearings.
110.81 Written comments.
110.82 Hearing request or intervention petition.
110.83 Answers and replies.
110.84 Commission action on a hearing request or intervention petition.
110.85 Notice of hearing consisting of written comments.
110.86 Notice of oral hearing.
110.87 Conditions in a notice or order.
110.88 Authority of the Secretary.
110.89 Filing and service.
110.90 Computation of time.
110.91 Commission consultations.

                           Subpart I_Hearings

110.100 Public hearings.
110.101 Filing and service.
110.102 Hearing docket.
110.103 Acceptance of hearing documents.
110.104 Presiding officer.
110.105 Responsibility and power of the presiding officer in an oral 
          hearing.
110.106 Participation in a hearing.
110.107 Presentation of testimony in an oral hearing.
110.108 Appearance in an oral hearing.
110.109 Motions and requests.
110.110 Default.
110.111 Waiver of a rule or regulation.
110.112 Reporter and transcript for an oral hearing.
110.113 Commission action.

   Subpart J_Special Procedures for Classified Information in Hearings

110.120 Purpose and scope.
110.121 Security clearances and access to classified information.
110.122 Classification assistance.
110.123 Notice of intent to introduce classified information.
110.124 Rearrangement or suspension of a hearing.
110.125 Unclassified statements required.
110.126 Protection of classified information.

                          Subpart K_Rulemaking

110.130 Initiation of rulemaking.
110.131 Petition for rulemaking.
110.132 Commission action on a petition.
110.133 Notice of proposed rulemaking.
110.134 Public participation.
110.135 Notice of rulemaking.

Appendix A to Part 110--Illustrative List of Nuclear Reactor Equipment 
          Under NRC Export Licensing Authority
Appendix B to Part 110--Illustrative List of Gas Centrifuge Enrichment 
          Plant Components Under NRC's Export Licensing Authority
Appendix C to Part 110--Illustrative List of Gaseous Diffusion 
          Enrichment Plant Assemblies and Components Under NRC Export 
          Licensing Authority
Appendix D to Part 110--Illustrative List of Aerodynamic Enrichment 
          Plant Equipment and Components Under NRC Export Licensing 
          Authority
Appendix E to Part 110--Illustrative List of Chemical Exchange or Ion 
          Exchange Enrichment Plant Equipment and Components Under NRC 
          Export Licensing Authority
Appendix F to Part 110--Illustrative List of Laser-Based Enrichment 
          Plant Equipment and Components Under NRC Export Licensing 
          Authority
Appendix G to Part 110--Illustrative List of Plasma Separation 
          Enrichment Plant Equipment and Components Under NRC Export 
          Licensing Authority
Appendix H to Part 110--Illustrative List of Electromagnetic Enrichment 
          Plant Equipment and Components Under NRC Export Licensing 
          Authority
Appendix I to Part 110--Illustrative List of Reprocessing Plant 
          Components Under NRC Export Licensing Authority
Appendix J to Part 110--Illustrative List of Uranium Conversion Plant 
          Equipment and Plutonium Conversion Plant

[[Page 696]]

          Equipment Under NRC Export Licensing Authority
Appendix K to Part 110--Illustrative List of Equipment and Components 
          Under NRC Export Licensing Authority for Use in a Plant for 
          the Production of Heavy Water, Deuterium and Deuterium 
          Compounds
Appendix L to Part 110--Illustrative List of Byproduct Materials Under 
          NRC Export/Import Licensing Authority
Appendix M to Part 110--Categorization of Nuclear Material
Appendix N to Part 110--Illustrative List of Lithium Isotope Separation 
          Facilities, Plants and Equipment Under NRC's Export Licensing 
          Authority
Appendix O to Part 110--Illustrative List of Fuel Element Fabrication 
          Plant Equipment and Components Under NRC's Export Licensing 
          Authority
Appendix P to Part 110--Category 1 and 2 Radioactive Material

    Authority: Atomic Energy Act of 1954, secs. 11, 51, 53, 54, 57, 62, 
63, 64, 65, 81, 82, 103, 104, 109, 111, 121, 122, 123, 124, 126, 127, 
128, 129, 133, 134, 161, 170H, 181, 182, 183, 184, 186, 187, 189, 223, 
234 (42 U.S.C. 2014, 2071, 2073, 2074, 2077, 2092, 2093, 2094, 2095, 
2111, 2112, 2133, 2134, 2139, 2141, 2151, 2152, 2153, 2154, 2155, 2156, 
2157, 2158, 2160c, 2160d, 2201, 2210h, 2231, 2232, 2233, 2234, 2236, 
2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, sec. 201 (42 
U.S.C. 5841); Administrative Procedure Act (5 U.S.C. 552, 553); 42 
U.S.C. 2139a, 2155a; 44 U.S.C. 3504 note.
    Section 110.1(b) also issued under 22 U.S.C. 2403; 22 U.S.C. 2778a; 
50 App. U.S.C. 2401 et seq.
    Sections 110.1(b)(2) and 110.1(b)(3) also issued under 22 U.S.C. 
2403.
    Section 110.11 also issued under Atomic Energy Act secs. 54(c), 
57(d), 122 (42 U.S.C. 2074, 2152).
    Section 110.50(b)(3) also issued under Atomic Energy Act sec. 123 
(42 U.S.C. 2153).
    Section 110.51 also issued under Atomic Energy Act sec. 184 (42 
U.S.C. 2234).
    Section 110.52 also issued under Atomic Energy Act sec. 186, (42 
U.S.C. 2236).
    Sections 110.80-110.113 also issued under 5 U.S.C. 552, 554.
    Sections 110.130-110.135 also issued under 5 U.S.C. 553.
    Sections 110.2 and 110.42(a)(9) also issued under Intelligence 
Authorization Act sec. 903 (42 U.S.C. 2151 et seq.).

    Source: 43 FR 21641, May 19, 1978, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 110.1  Purpose and scope.

    (a) The regulations in this part prescribe licensing, enforcement, 
and rulemaking procedures and criteria, under the Atomic Energy Act, for 
the export of nuclear equipment and material, as set out in Sec. Sec. 
110.8 and 110.9, and the import of nuclear equipment and material, as 
set out in Sec. 110.9a. This part also gives notice to all persons who 
knowingly provide to any licensee, applicant, contractor, or 
subcontractor, components, equipment, materials, or other goods or 
services, that relate to a licensee's or applicant's activities subject 
to this part, that they may be individually subject to NRC enforcement 
action for violation of Sec. 110.7b.
    (b) The regulations in this part apply to all persons in the United 
States except:
    (1) Persons who import or export U.S. Munitions List nuclear items 
such as uranium depleted in the isotope-235 and incorporated in defense 
articles. These persons are subject to the regulations promulgated 
pursuant to the Arms Export Control Act and administered by the 
Department of State, Directorate of Defense Trade Controls, and the 
Department of Justice, Bureau of Alcohol, Tobacco, Firearms and 
Explosives, as authorized by section 110 of the International Security 
and Development Cooperation Act of 1980.
    (2) Persons who export uranium depleted in the isotope-235 and 
incorporated in commodities solely to take advantage of high density or 
pyrophoric characteristics. These persons are subject to the controls of 
the Department of Commerce under the Export Administration Act, as 
continued in force under Executive Order 13222 (August 22, 2001), as 
extended;
    (3) Persons who export nuclear referral list commodities such as 
bulk zirconium, rotor and bellows equipment, maraging steel, nuclear 
reactor related equipment, including process control systems and 
simulators. These persons are subject to the licensing authority of the 
Department of Commerce pursuant to 15 CFR part 730 et seq.;
    (4) Persons who import deuterium, nuclear grade graphite, or nuclear 
equipment other than production or utilization facilities. A uranium 
enrichment facility is not a production facility for the purposes of 
import; and
    (5) Shipments which are only passing through the U.S. (in bond 
shipments) do not require an NRC import or export

[[Page 697]]

license; however, they must comply with the Department of 
Transportation/IAEA packaging, and State transportation requirements.

[49 FR 47197, Dec. 3, 1984; 49 FR 49841, Dec. 24, 1984, as amended at 55 
FR 34519, Aug. 23, 1990; 56 FR 40692, Aug. 15, 1991; 58 FR 13001, Mar. 
9, 1993; 61 FR 35602, July 8, 1996; 63 FR 1900, Jan. 13, 1998; 65 FR 
70289, Nov. 22, 2000; 75 FR 44085, July 28, 2010]



Sec. 110.2  Definitions.

    As used in this part,
    Accelerator-produced radioactive material means any material made 
radioactive by a particle accelerator.
    Agreement for cooperation means any agreement with another nation or 
group of nations concluded under section 123 of the Atomic Energy Act.
    Atomic Energy Act means the Atomic Energy Act of 1954, as amended 
(42 U.S.C. 2011 et seq.).
    Bulk material means any quantity of any one or more of the 
radionuclides listed in Table 1 of Appendix P to this part in a form 
that is:
    (1) Not a Category 1 radioactive source;
    (2) Not a Category 2 radioactive source;
    (3) Not plutonium-238; and
    (4) Deemed to pose a risk similar to or greater than a Category 2 
radioactive source.
    Byproduct material means
    (1) Any radioactive material (except special nuclear material) 
yielded in, or made radioactive by, exposure to the radiation incident 
to the process of producing or utilizing special nuclear material;
    (2) The tailings or wastes produced by the extraction or 
concentration of uranium or thorium from ore (see 10 CFR 20.1003);
    (3)(i) Any discrete source of radium-226 that is produced, 
extracted, or converted after extraction, before, on, or after August 8, 
2005, for use for a commercial, medical, or research activity; or
    (ii) Any material that has been made radioactive by use of a 
particle accelerator and is produced, extracted, or converted after 
extraction, before, on, or after August 8, 2005 for use for a 
commercial, medical, or research activity; and
    (4) Any discrete source of naturally occurring radioactive material, 
other than source material, that--
    (i) The Commission, in consultation with the Administrator of the 
Environmental Protection Agency, the Secretary of Energy, the Secretary 
of Homeland Security, and the head of any other appropriate Federal 
agency, determines would pose a threat similar to the threat posed by a 
discrete source of radium-226 to the public health and safety or the 
common defense and security; and
    (ii) Before, on, or after August 8, 2005 is extracted or converted 
after extraction for use in a commercial, medical, or research activity.
    Classified Information means Classified National Security 
Information under Executive Order 13526, as amended, or any predecessor 
or successor Executive Order and Restricted Data under the Atomic Energy 
Act.
    Commission means the United States Nuclear Regulatory Commission or 
its duly authorized representatives.
    Common defense and security means the common defense and security of 
the United States.
    Conversion facility means any facility for the transformation from 
one uranium chemical species to another, including conversion of uranium 
ore concentrates to uranium trioxide (UO3), conversion of UO3 to uranium 
dioxide (UO2), conversion of uranium oxides to uranium tetrafluoride 
(UF4) or uranium hexafluoride (UF6), conversion of UF4 to UF6, 
conversion of UF6 to UF4, conversion of UF4 to uranium metal, and 
conversion of uranium fluorides to UO2.
    Depleted uranium means uranium having a percentage of uranium-235 
less than the naturally occurring distribution of uranium-235 found in 
natural uranium (less than 0.711 weight percent uranium-235). It is 
obtained from spent (used) fuel elements or as byproduct tails or 
residues from uranium isotope separation.
    Deuterium means deuterium and any deuterium compound, including 
heavy water, in which the ratio of deuterium atoms to hydrogen atoms 
exceeds 1:5000.

[[Page 698]]

    Discrete source means a radionuclide that has been processed so that 
its concentration within a material has been purposely increased for use 
for commercial, medical, or research activities.
    Disposal means permanent isolation of radioactive material from the 
surrounding environment.
    Dual-use means equipment and materials that may be used in nuclear 
or non-nuclear applications.
    Effective kilograms of special nuclear material means:
    (1) For plutonium and uranium-233, their weight in kilograms;
    (2) For uranium enriched 1 percent or greater in the isotope 
uranium-235, its element weight in kilograms multiplied by the square of 
its enrichment expressed as a decimal weight fraction; and
    (3) For uranium enriched below 1 percent in the isotope uranium-235, 
its element weight in kilograms multiplied by 0.0001.
    Embargoed means that no nuclear material or equipment can be 
exported to certain countries under an NRC general license. Exports to 
embargoed countries must be pursuant to a specific license issued by the 
NRC and require Executive Branch review pursuant to Sec. 110.41.
    Exceptional circumstances means, with respect to exports from the 
United States of radioactive material listed in Table 1 of Appendix P of 
this part:
    (1) Cases of considerable health or medical need as acknowledged by 
the U.S. Government and the government of the importing country;
    (2) Cases where there is an imminent radiological hazard or security 
threat presented by one or more radioactive sources; and
    (3) Cases in which the exporting facility or U.S. Government 
maintains control of the radioactive material throughout the period the 
material is outside of the U.S. and removes the material at the 
conclusion of this period.
    Executive Branch means the Departments of State, Energy, Defense and 
Commerce.
    Export means to physically transfer nuclear equipment or material to 
a person or an international organization in a foreign country, except 
DOE distributions as authorized in Section 111 of the Atomic Energy Act 
or Section 110 of the International Security and Development Cooperation 
Act of 1980.
    General license means an export or import license effective without 
the filing of a specific application with the Commission or the issuance 
of licensing documents to a particular person. A general license is a 
type of license issued through rulemaking by the NRC and is not an 
exemption from the requirements in this part. A general license does not 
relieve a person from complying with other applicable NRC, Federal, and 
State requirements.
    Heels means small quantities of natural, depleted or low-enriched 
uranium (to a maximum of 20 percent), in the form of uranium 
hexafluoride (UF6) left in emptied transport cylinders being returned to 
suppliers after delivery of the product.
    High-enriched uranium means uranium enriched to 20 percent or 
greater in the isotope uranium-235.
    IAEA means the International Atomic Energy Agency.
    Import means import into the United States.
    Individual shipment means a shipment consisting of one lot of 
freight tendered to a carrier by one consignor at one place at one time 
for delivery to one consignee on one bill of lading. This lot may 
consist of:
    (1) Only one item or
    (2) A number of containers all listed on the same set of shipping 
documents. This one lot of freight or ``distinct'' shipment can be 
transported on the same carrier with other distinct shipments containing 
the same items as long as each shipment is covered by separate sets of 
shipping documents.
    The phrase introduced into a hearing means the introduction or 
incorporation of testimony or documentary matter into the record of a 
hearing.
    License means a general or specific export or import license issued 
pursuant to this part.
    Licensee means a person authorized by a specific or a general 
license to export or import nuclear equipment or material pursuant to 
this part.

[[Page 699]]

    Low-enriched uranium means uranium enriched below 20 percent in the 
isotope uranium-235.
    Low-level waste compact, as used in this part, means a compact 
entered into by two or more States pursuant to the Low-Level Radioactive 
Waste Policy Amendments Act of 1985.
    Management means storage, packaging, or treatment of radioactive 
waste.
    Medical isotope, for the purposes of Sec. 110.42(a)(9), includes 
molybdenum-99, iodine-131, xenon-133, and other radioactive materials 
used to produce a radiopharmaceutical for diagnostic, therapeutic 
procedures or for research and development.
    Natural uranium means uranium as found in nature, containing about 
0.711 percent of uranium-235, 99.283 percent of uranium-238, and a trace 
(0.006 percent) of uranium-234.
    NPT means the Treaty on the Non-Proliferation of Nuclear Weapons 
(TIAS 6839).
    Non-nuclear weapon State means any State not a nuclear weapon State 
as defined in the Treaty on the Non-Proliferation of Nuclear Weapons. 
Nuclear weapon state means any State which has manufactured and exploded 
a nuclear weapon or other nuclear explosive device prior to January 1, 
1967 (China, France, Russia, United Kingdom, United States).
    Non-Proliferation Act means the Nuclear Non-Proliferation Act of 
1978 (Pub. L. 95-242).
    NRC Public Document Room means the facility at One White Flint 
North, 11555 Rockville Pike (first floor), Rockville, Maryland, where 
certain public records of the NRC that were made available for public 
inspection in paper or microfiche prior to the implementation of the NRC 
Agencywide Documents Access and Management System, commonly referred to 
as ADAMS, will remain available for public inspection. It is also the 
place where NRC makes computer terminals available to access the 
Publicly Available Records System (PARS) component of ADAMS on the NRC 
Web site, http://www.nrc.gov, and where copies can be viewed or ordered 
for a fee as set forth in Sec. 9.35 of this chapter. The facility is 
staffed with reference librarians to assist the public in identifying 
and locating documents and in using the NRC Website and ADAMS. The NRC 
Public Document Room is open from 7:45 a.m. to 4:15 p.m., Monday through 
Friday, except on Federal holidays. Reference service and access to 
documents may also be requested by telephone (301-415-4737 or 800-397-
4209) between 8:30 a.m. and 4:15 p.m., or by e-mail 
([email protected]), facsimile (301-415-3548), or letter (NRC Public 
Document Room, One White Flint North, 11555 Rockville Pike (first 
floor), Rockville, Maryland 20852-2738).
    NRC records means any documentary material made by, in the 
possession of, or under the control of the Commission under Federal law 
or in connection with the transaction of public business as evidence of 
any of the Commission's activities.
    NRC Web site, http://www.nrc.gov, is the Internet uniform resource 
locator name for the Internet address of the Web site where NRC will 
ordinarily make available its public records for inspection.
    Nuclear grade graphite for nuclear end use means graphite having a 
purity level better than (i.e., less than) 5 parts per million boron 
equivalent, as measured according to ASTM standard C1233-98 and intended 
for use in a nuclear reactor. (Nuclear grade graphite for non-nuclear 
end use is regulated by the Department of Commerce.)
    Nuclear reactor means an apparatus, other than an atomic weapon or 
nuclear explosive device, designed or used to sustain nuclear fission in 
a self-supporting chain reaction.
    Nuclear reactor internals means the major structures within a 
reactor vessel that have one or more functions such as supporting the 
core, maintaining fuel alignment, directing primary coolant flow, 
providing radiation shields for the reactor vessel, and guiding in-core 
instrumentation.
    Nuclear Referral List (NRL) means the nuclear-related, dual-use 
commodities on the Commerce Control List that are subject to the nuclear 
non-proliferation export licensing controls of the Department of 
Commerce. They are

[[Page 700]]

contained in 15 CFR part 774 of the Department of Commerce's Export 
Administration Regulations and are designated by the symbol (NP) as the 
reason for control.
    Nuclear Suppliers Group (NSG) is a group of nuclear supplier 
countries which seeks to contribute to the non-proliferation of nuclear 
weapons through the implementation of Guidelines for nuclear exports and 
nuclear-related exports.
    Obligations means the commitments undertaken by the U.S. Government 
or by foreign governments or groups of nations with respect to imports 
or exports of nuclear material (except byproduct material) and equipment 
listed in Sec. Sec. 110.8 and 110.9. Imports and exports of material or 
equipment subject to these commitments involve conditions placed on the 
transfer of the material or equipment, such as peaceful end-use 
assurances, prior consent for retransfer, and exchanges of information 
on the import or export. The U.S. Government informs the licensee of 
obligations attached to material or equipment being imported into the 
United States and approves changes to those obligations.
    Packaging means one or more receptacles and wrappers and their 
contents, excluding any special nuclear material, source material or 
byproduct material, but including absorbent material, spacing 
structures, thermal insulation, radiation shielding, devices for cooling 
and for absorbing mechanical shock, external fittings, neutron 
moderators, nonfissile neutron absorbers and other supplementary 
equipment.
    Participant means a person, identified in a hearing notice or other 
Commission order, who takes part in a hearing conducted by the 
Commission under this part, including any person to whom the Commission 
grants a hearing or leave to intervene in an export or import licensing 
hearing, either as a matter of right or as a matter of discretion.
    Particle accelerator means any machine capable of accelerating 
electrons, protons, deuterons, or other charged particles in a vacuum 
and of discharging the resultant particulate or other radiation into a 
medium at energies usually in excess of 1 megaelectron volt. For 
purposes of this definition, ``accelerator'' is an equivalent term.
    Person means any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
Government agency, other than the Commission or the Department of 
Energy, except that the Department of Energy shall be considered a 
person within the meaning of the regulations in this part to the extent 
that its activities are subject to the licensing and related regulatory 
authority of the Commission pursuant to section 111 of the Atomic Energy 
Act; any State or political subdivision of, or any political entity 
within a State, any foreign government or nation or any political 
subdivision of any such government or nation, or other entity; and any 
legal successor, representative, agent, or agency of the foregoing.
    Physical security or Physical protection means measures to 
reasonably ensure that source or special nuclear material will only be 
used for authorized purposes and to prevent theft or sabotage.
    Production facility means any nuclear reactor or plant specially 
designed or used to produce special nuclear material through the 
irradiation of source material or special nuclear material, the chemical 
reprocessing of irradiated source or special nuclear material, or the 
separation of isotopes, other than a uranium enrichment facility for 
purposes of import.
    Public health and safety means the public health and safety of the 
United States.
    Radioactive material means source, byproduct, or special nuclear 
material.
    Radioactive waste, for the purposes of this part, means any material 
that contains or is contaminated with source, byproduct, or special 
nuclear material that by its possession would require a specific 
radioactive material license in accordance with this Chapter and is 
imported or exported for the purposes of disposal in a land disposal 
facility as defined in 10 CFR part 61, a disposal area as defined in 
Appendix A to 10 CFR part 40, or an equivalent facility; or recycling, 
waste treatment or other waste management process that

[[Page 701]]

generates radioactive material for disposal in a land disposal facility 
as defined in 10 CFR part 61, a disposal area as defined in Appendix A 
to 10 CFR part 40, or an equivalent facility. Radioactive waste does not 
include radioactive material that is--
    (1) Of U.S. origin and contained in a sealed source, or device 
containing a sealed source, that is being returned to a manufacturer, 
distributor or other entity which is authorized to receive and possess 
the sealed source or the device containing a sealed source;
    (2) A contaminant on any non-radioactive material (including service 
tools and protective clothing) used in a nuclear facility (an NRC- or 
Agreement State-licensed facility (or equivalent facility) or activity 
authorized to possess or use radioactive material), if the material is 
being shipped solely for recovery and beneficial reuse of the non-
radioactive material in a nuclear facility and not for waste management 
purposes or disposal;
    (3) Exempted from regulation by the Nuclear Regulatory Commission or 
equivalent Agreement State regulations;
    (4) Generated or used in a U.S. Government waste research and 
development testing program under international arrangements;
    (5) Being returned by or for the U.S. Government or military to a 
facility that is authorized to possess the material; or
    (6) Imported solely for the purposes of recycling and not for waste 
management or disposal where there is a market for the recycled material 
and evidence of a contract or business agreement can be produced upon 
request by the NRC.

    Note: The definition of radioactive waste in this part does not 
include spent or irradiated fuel.

    Radiopharmaceutical, for the purposes of Sec. 110.42(a)(9), means a 
radioactive isotope that contains byproduct material combined with 
chemical or biological material and is designed to accumulate 
temporarily in a part of the body for therapeutic purposes or for 
enabling the production of a useful image for use in a diagnosis of a 
medical condition.
    Recipient country, for the purposes of Sec. 110.42(a)(9), means 
Canada, Belgium, France, Germany, and the Netherlands.
    Restricted destinations means countries that are listed in Sec. 
110.29 based on recommendations from the Executive Branch. These 
countries may receive exports of certain materials and quantities under 
a general license, but some exports to restricted destinations will 
require issuance of a specific license by the NRC including Executive 
Branch review pursuant to Sec. 110.41.
    Retransfer means the transport from one foreign country to another 
of nuclear equipment or nuclear material previously exported from the 
United States, or of special nuclear material produced through the use 
of source material or special nuclear material previously exported from 
the United States.
    Sealed source means any special nuclear material or byproduct 
material encased in a capsule designed to prevent leakage or escape of 
that nuclear material.
    Secretary means the Secretary of the Commission.
    Source material means:
    (1) Natural or depleted uranium, or thorium, other than special 
nuclear material; or
    (2) Ores that contain by weight 0.05 percent or more of uranium, 
thorium or depleted uranium.
    Special nuclear material means plutonium, uranium-233 or uranium 
enriched above 0.711 percent by weight in the isotope uranium-235.
    Specific activity means the radioactivity of a radionuclide per unit 
mass of that nuclide, expressed in the SI unit of terabecquerels per 
gram (TBq/g). Values of specific activity are found in Appendix A to 
part 71 of this chapter.
    Specific license means an export or import license document issued 
to a named person and authorizing the export or import of specified 
nuclear equipment or materials based upon the review and approval of an 
NRC Form 7 application filed pursuant to this part and other related 
submittals in support of the application.
    Storage means the temporary holding of radioactive material.

[[Page 702]]

    Target means material subjected to irradiation in an accelerator or 
nuclear reactor to induce a reaction or produce nuclear material.
    Transfer means the transfer of possession from one person to another 
person.
    Transport means the physical movement of material from one location 
to another.
    Treatment means any method, technique, or process, including storage 
for radioactive decay, designed to change the physical, chemical or 
biological characteristics or composition of any radioactive material.
    Tritium means not only tritium but also includes compounds and 
mixtures containing tritium in which the ratio of tritium to hydrogen by 
atoms exceeds one part in 1,000.
    United States, when used in a geographical sense, includes Puerto 
Rico and all territories and possessions of the United States.
    Uranium enrichment facility means:
    (1) Any facility used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or
    (2) Any equipment or device, or important component part especially 
designed for such equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.
    Utilization facility means:
    (1) Any nuclear reactor, other than one that is a production 
facility and
    (2) Any of the following major components of a nuclear reactor:
    (i) Reactor pressure vessel (designed to contain the core of a 
nuclear reactor);
    (ii) Reactor primary coolant pump or circulator;
    (iii) ``On-line'' reactor fuel charging and discharging machine; and
    (iv) Complete reactor control rod system.
    (3) A utilization facility does not include the steam turbine 
generator portion of a nuclear power plant.

[43 FR 21691, May 19, 1978]

    Editorial Note: For Federal Register citations affecting Sec. 
110.2, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 110.3  Interpretations.

    Except as authorized by the Commission in writing, no interpretation 
of the meaning of the regulations in this part other than a written 
interpretation by the Commission's General Counsel is binding upon the 
Commission.



Sec. 110.4  Communications.

    Except where otherwise specified in this part, all communications 
and reports concerning the regulations in this part should be addressed 
to the Deputy Director of the NRC's Office of International Programs, 
either by telephone to (301) 415-2344; by mail to the U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; by hand delivery to 
the NRC's offices at 11555 Rockville Pike, Rockville, Maryland; or, 
where practicable, by electronic submission, for example, via Electronic 
Information Exchange, or CD-ROM. Electronic submissions must be made in 
a manner that enables the NRC to receive, read, authenticate, 
distribute, and archive the submission, and process and retrieve it a 
single page at a time. Detailed guidance on making electronic 
submissions can be obtained by visiting the NRC's Web site at http://
www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[68 FR 58824, Oct. 10, 2003, as amended at 74 FR 62686, Dec. 1, 2009; 80 
FR 74982, Dec. 1, 2015]



Sec. 110.5  Licensing requirements.

    Except as provided under subpart B of this part, no person may 
export any nuclear equipment or material listed in Sec. 110.8 and Sec. 
110.9, or import any nuclear equipment or material listed in Sec. 
110.9a, unless authorized by a general or specific license issued under 
this part.

[56 FR 24684, May 31, 1991, as amended at 58 FR 13002, Mar. 9, 1993]

[[Page 703]]



Sec. 110.6  Retransfers.

    (a) Retransfer of any nuclear equipment or material listed in 
Sec. Sec. 110.8 and 110.9 (except byproduct material), including 
special nuclear material produced through the use of equipment, source 
material, or special nuclear material bearing obligations to the United 
States pursuant to an agreement for cooperation, requires authorization 
by the Department of Energy, unless the export to the new destination is 
authorized by the NRC under a specific or general license or an 
exemption from licensing requirements. See definition of ``obligations'' 
in Sec. 110.2.
    (b) Requests for authority to retransfer are processed by the 
Department of Energy, National Nuclear Security Administration, Office 
of International Regimes and Agreements, Washington, DC 20585.

[75 FR 44087, July 28, 2010]



Sec. 110.7  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control numbers 3150-0036.
    (b) The approved information requirements contained in this part 
appear in Sec. Sec. 110.7a, 110.27, 110.32, 110.50, 110.52, 110.53, and 
110.54.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. The information collection requirements 
contained in Sec. Sec. 110.19, 110.20, 110.21, 110.22, 110.23, 110.31, 
110.32, and 110.51, and NRC Form 7 are approved under control number 
3150-0027.

[62 FR 52190, Oct. 6, 1997, as amended at 65 FR 70290, Nov. 22, 2000; 67 
FR 67101, Nov. 4, 2002; 71 FR 19104, Apr. 13, 2006; 75 FR 44087, July 
28, 2010; 76 FR 72087, Nov. 22, 2011]



Sec. 110.7a  Completeness and accuracy of information.

    (a) Information provided to the Commission by an applicant for a 
license or by a licensee or information required by statute or by the 
Commission's regulations, orders, or license conditions to be maintained 
by the applicant or the licensee shall be complete and accurate in all 
material respects.
    (b) Each licensee or applicant for a license shall notify the 
Commission of information identified by the applicant or licensee as 
having, for the regulated activity, a significant implication for public 
health and safety or common defense and security. An applicant or 
licensee violates this paragraph if the applicant or licensee fails to 
notify the Commission of information that the applicant or licensee has 
identified as having a significant implication for public health and 
safety or common defense and security. Notification shall be provided to 
the Administrator of the appropriate Regional Office within two working 
days of identifying the information. This requirement is not applicable 
to information which is already required to be provided to the 
Commission by other reporting or updating requirements.

[52 FR 49374, Dec. 31, 1987, as amended at 75 FR 44087, July 28, 2010]



Sec. 110.7b  Deliberate misconduct.

    (a) Any licensee, applicant for a license, employee of a licensee or 
applicant; or any contractor (including a supplier or consultant), 
subcontractor, employee of a contractor or subcontractor of any licensee 
or applicant for a license, who knowingly provides to any licensee, 
applicant, contractor, or subcontractor, any components, equipment, 
materials, or other goods or services that relate to a licensee's or 
applicant's activities in this part, may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee or applicant to be in violation of 
any rule, regulation, or order; or any term, condition, or limitation of 
any license issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, an applicant, or a 
licensee's

[[Page 704]]

or applicant's contractor or subcontractor, information that the person 
submitting the information knows to be incomplete or inaccurate in some 
respect material to the NRC.
    (b) A person who violates paragraph (a)(1) or (a)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (c) For the purposes of paragraph (a)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee or applicant to be in violation of any 
rule, regulation, or order; or any term, condition, or limitation, of 
any license issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
applicant, contractor, or subcontractor.

[63 FR 1900, Jan. 13, 1998]



Sec. 110.8  List of nuclear facilities and equipment under NRC export
licensing authority.

    (a) Nuclear reactors and especially designed or prepared equipment 
and components for nuclear reactors. (See Appendix A to this part.)
    (b) Plants for the separation of isotopes of uranium (source 
material or special nuclear material) including gas centrifuge plants, 
gaseous diffusion plants, aerodynamic enrichment plants, chemical 
exchange or ion exchange enrichment plants, laser based enrichment 
plants, plasma separation enrichment plants, electromagnetic enrichment 
plants, and especially designed or prepared equipment, other than 
analytical instruments, for the separation of isotopes of uranium. (See 
appendices to this part for lists of: gas centrifuge equipment--Appendix 
B; gaseous diffusion equipment--Appendix C; aerodynamic enrichment 
equipment--Appendix D; chemical exchange or ion exchange enrichment 
equipment--Appendix E; laser based enrichment equipment--Appendix F; 
plasma separation enrichment equipment--Appendix G; and electromagnetic 
enrichment equipment--Appendix H.)
    (c) Plants for the separation of the isotopes of lithium and 
especially designed or prepared assemblies and components for these 
plants. (See Appendix N to this part.)
    (d) Plants for the reprocessing of irradiated nuclear reactor fuel 
elements and especially designed or prepared assemblies and components 
for these plants. (See Appendix I to this part.)
    (e) Plants for the fabrication of nuclear reactor fuel elements and 
especially designed or prepared assemblies and components for these 
plants. (See Appendix O to this part.)
    (f) Plants for the conversion of uranium and plutonium and 
especially designed or prepared assemblies and components for these 
plants. (See Appendix J to this part.)
    (g) Plants for the production, separation, or purification of heavy 
water, deuterium, and deuterium compounds and especially designed or 
prepared assemblies and components for these plants. (See Appendix K to 
this part.)
    (h) Plants for the production of special nuclear material using 
accelerator-driven subcritical assembly systems capable of continuous 
operation above 5 MWe thermal.
    (i) Other nuclear-related commodities are under the export licensing 
authority of the Department of Commerce.

[61 FR 35602, July 8, 1996, as amended at 65 FR 70290, Nov. 22, 2000]



Sec. 110.9  List of Nuclear Material under NRC export licensing authority.

    (a) Special Nuclear Material.
    (b) Source Material.
    (c) Byproduct Material.
    (d) Deuterium.
    (e) Nuclear grade graphite for nuclear end use.

[55 FR 30450, July 26, 1990, as amended at 70 FR 41939, July 21, 2005]



Sec. 110.9a  List of nuclear equipment and material under NRC import 
licensing authority.

    (a) Production and utilization facilities.
    (b) Special nuclear material.
    (c) Source material.

[[Page 705]]

    (d) Byproduct material.

[49 FR 47198, Dec. 3, 1984. Redesignated at 55 FR 30450, July 26, 1990, 
and amended at 57 FR 18393, Apr. 30, 1992; 58 FR 13003, Mar. 9, 1993]



                          Subpart B_Exemptions



Sec. 110.10  General.

    (a) In response to a request or on its own initiative, the 
Commission may grant an exemption from the regulations in this part, if 
it determines that the exemption:
    (1) Is authorized by law;
    (2) Is not inimical to the common defense and security; and
    (3) Does not constitute an unreasonable risk to the public health 
and safety.
    (b) An exemption from statutory licensing requirements, as 
authorized by sections 57d, 62, and 81 of the Atomic Energy Act, will be 
granted only after coordination with the Executive Branch.
    (c) The granting of an exemption does not relieve any person from 
complying with the regulations of other U.S. Federal and/or State 
government agencies applicable to exports or imports under their 
authority.

[49 FR 47198, Dec. 3, 1984, as amended at 58 FR 13003, Mar. 9, 1993; 65 
FR 70290, Nov. 22, 2000; 75 FR 44087, July 28, 2010]



Sec. 110.11  Export of IAEA safeguards samples.

    (a) A person is exempt from the requirements for a license to export 
special nuclear, source, and byproduct material set forth in sections 
53, 54d, 64, 81 and 82 of the Atomic Energy Act and from the regulations 
in this part to the extent that the person exports special nuclear, 
source, or byproduct material in IAEA safeguards samples. The samples 
must be exported in accordance with Sec. 75.8 of this chapter, or a 
comparable U.S. Department of Energy order, and:
    (1) For special nuclear material, be in quantities not exceeding a 
combined total of 100 grams of contained plutonium, uranium-233, and 
uranium-235 per facility per year;
    (2) For source material, be in quantities not exceeding 5 kilograms 
per facility per year; and
    (3) For byproduct material, be in quantities not exceeding the 
values in Sec. 30.71 of this chapter per shipment.
    (b) This exemption does not relieve any person from complying with 
parts 71 or 73 of this chapter or any Commission order under section 
201(a) of the Energy Reorganization Act of 1974 (42 U.S.C. 5841(a)).

[77 FR 27114, May 9, 2012]



                           Subpart C_Licenses

    Source: 49 FR 47198, Dec. 3, 1984, unless otherwise noted.



Sec. 110.19  Types of licenses.

    Licenses for the export and import of nuclear equipment and material 
in this part consist of general licenses and specific licenses. A 
general license is effective without the filing of an application with 
the Commission or the issuance of licensing documents to a particular 
person. A specific license is issued to a named person and is effective 
upon approval by the Commission of an application filed pursuant to the 
regulations in this part and issuance of licensing documents to the 
applicant.

[75 FR 44087, July 28, 2010]



Sec. 110.20  General license information.

    (a) A person may use an NRC general license as authority to export 
or import nuclear equipment or material, if the nuclear equipment or 
material to be exported or imported is covered by the NRC general 
licenses described in Sec. Sec. 110.21 through 110.27. If an export or 
import is not covered by the NRC general licenses described in 
Sec. Sec. 110.21 through 110.27, a person must file an application with 
the Commission for a specific license in accordance with Sec. Sec. 
110.31 through 110.32.
    (b) In response to a petition or on its own initiative, the 
Commission may issue a general license for export or import if it 
determines that any exports or imports made under the general license 
will not be inimical to the common defense and security or constitute an 
unreasonable risk to the public health and safety and otherwise meet 
applicable statutory requirements. A general license is issued as a 
regulation after a rulemaking proceeding under

[[Page 706]]

subpart K of this part. Issuance of a general license is coordinated 
with the Executive Branch.
    (c) A general license does not relieve a person from complying with 
the regulations of other Government agencies applicable to exports or 
imports under their authority.
    (d) A general license for export may not be used if the exporter 
knows, or has reason to believe, that the material will be used in any 
illegal activity or any activity related to isotope separation, chemical 
reprocessing, heavy water production or the fabrication of nuclear fuel 
containing plutonium, unless these activities are generically authorized 
under an appropriate agreement for cooperation.
    (e) A person who uses an NRC general license as the authority to 
export or import may cite on the shipping documents the section of this 
part which authorizes the described export or import under general 
license, as a means of expediting U.S. Customs Service's processing of 
the shipment.
    (f) As specified in Sec. Sec. 110.21 through 110.26, 110.28, 
110.29, and 110.30 only certain countries are eligible recipients of 
equipment or material under NRC general licenses to export. The 
Commission will closely monitor these countries and may at any time 
remove a country from a general license in response to significant 
adverse developments in the country involved. A key factor in this 
regard is the nonproliferation credentials of the importing country.

[49 FR 47198, Dec. 3, 1984, as amended at 58 FR 13003, Mar. 9, 1993; 59 
FR 48997, Sept. 26, 1994; 60 FR 37563, July 21, 1995; 75 FR 44087, July 
28, 2010]



Sec. 110.21  General license for the export of special nuclear material.

    (a) Except as provided in paragraph (d) of this section, a general 
license is issued to any person to export the following to any country 
not listed in Sec. 110.28:
    (1) Low-enriched uranium as residual contamination (17.5 parts per 
million or less) in any item or substance.
    (2) Plutonium containing 80 percent or more by weight of plutonium-
238 in cardiac pacemakers.
    (3) Special nuclear material, other than plutonium-236 and 
plutonium-238, in sensing components in instruments, if no more than 3 
grams of enriched uranium or 0.1 gram of plutonium or uranium-233 are 
contained in each sensing component.
    (4) Plutonium-236 and plutonium-238 when contained in a device, or a 
source for use in a device, in quantities of less than 3.7 x 
10-3 TBq (100 millicuries) of alpha activity (189 micrograms 
plutonium-236, 5.88 milligrams plutonium-238) per device or source.
    (b) Except as provided in paragraph (d) of this section, a general 
license is issued to any person to export the following to any country 
not listed in Sec. 110.28 or Sec. 110.29:
    (1) Special nuclear material, other than plutonium-236 and 
plutonium-238, in individual shipments of 0.001 effective kilogram or 
less (e.g., 1.0 gram of plutonium, uranium-233 or uranium-235, or 10 
kilograms of 1 percent enriched uranium), not to exceed 0.1 effective 
kilogram per calendar year to any one country.
    (2) Special nuclear material in fuel elements as replacements for 
damaged or defective unirradiated fuel elements previously exported 
under a specific license, subject to the same terms as the original 
export license and the condition that the replaced fuel elements must be 
returned to the United States within a reasonable time period.
    (3) Uranium, enriched to less than 20 percent in uranium-235, in the 
form of uranium hexafluoride (UF6) heels in cylinders being returned to 
suppliers in EURATOM.
    (c) Except as provided in paragraph (d) of this section, a general 
license is issued to any person to export plutonium-236 or plutonium-238 
to any country listed in Sec. 110.30 in individual shipments of 1 gram 
or less, not to exceed 100 grams per calendar year to any one country.
    (d) The general licenses in paragraphs (a), (b), and (c) of this 
section do not authorize the export of special nuclear material in 
radioactive waste.

[49 FR 47198, Dec. 3, 1984, as amended at 58 FR 13003, Mar. 9, 1993; 59 
FR 48997, Sept. 26, 1994; 60 FR 37563, July 21, 1995; 65 FR 70290, Nov. 
22, 2000; 70 FR 46066, Aug. 9, 2005; 75 FR 44087, July 28, 2010]

[[Page 707]]



Sec. 110.22  General license for the export of source material.

    (a) Except as provided in paragraph (e) of this section, a general 
license is issued to any person to export the following to any country 
not listed in Sec. 110.28:
    (1) Uranium or thorium, other than uranium-230, uranium-232, 
thorium-227, and thorium-228, in any substance in concentrations of less 
than 0.05 percent by weight.
    (2) Thorium, other than thorium-227 and thorium-228, in incandescent 
gas mantles or in alloys in concentrations of 5 percent or less.
    (3) Thorium-227, thorium-228, uranium-230, and uranium-232 when 
contained in a device, or a source for use in a device, in quantities of 
less than 3.7 x 10-3 TBq (100 millicuries) of alpha activity 
(3.12 micrograms thorium-227, 122 micrograms thorium-228, 3.7 micrograms 
uranium-230, 4.7 milligrams uranium-232) per device or source.
    (b) Except as provided in paragraph (e) of this section, a general 
license is issued to any person to export uranium or thorium, other than 
uranium-230, uranium-232, thorium-227, or thorium-228, in individual 
shipments of 10 kilograms or less to any country not listed in Sec. 
110.28 or Sec. 110.29, not to exceed 1,000 kilograms per calendar year 
to any one country or 500 kilograms per calendar year to any one country 
when the uranium or thorium is Canadian-obligated.
    (c) Except as provided in paragraph (e) of this section, a general 
license is issued to any person to export uranium or thorium, other than 
uranium-230, uranium-232, thorium-227, or thorium-228, in individual 
shipments of 1 kilogram or less to any country listed in Sec. 110.29, 
not to exceed 100 kilograms per calendar year to any one country.
    (d) Except as provided in paragraph (e) of this section, a general 
license is issued to any person to export uranium-230, uranium-232, 
thorium-227, or thorium-228 in individual shipments of 10 kilograms or 
less to any country listed in Sec. 110.30, not to exceed 1,000 
kilograms per calendar year to any one country or 500 kilograms per 
calendar year to any one country when the uranium or thorium is 
Canadian-obligated.
    (e) Paragraphs (a), (b), (c), and (d) of this section do not 
authorize the export under general license of source material in 
radioactive waste.

[75 FR 44088, July 28, 2010, as amended at 77 FR 27114, May 9, 2012]



Sec. 110.23  General license for the export of byproduct material.

    (a) A general license is issued to any person to export byproduct 
material (see Appendix L to this part) to any country not listed in 
Sec. 110.28 and subject to the following limitations:
    (1) The general license in this section does not authorize the 
export of byproduct material in the form of radioactive waste.
    (2) The general license in this section does not authorize the 
export of the following radionuclides:

Americium-242m
Californium-249
Californium-251
Curium-245
Curium-247

    (3) For byproduct materials listed in Table 1 of Appendix P to this 
part, individual shipments under a general license for export must be 
less than the terabecquerel (TBq) values specified in Category 2 of 
Table 1 unless a more restrictive requirement applies.
    (4) The general license authorizes exports of the following 
radionuclides when contained in a device, or a source for use in a 
device, in quantities less than 3.7 x 10-3 TBq (100 
millicuries) of alpha activity per device or source, unless the export 
is to a country listed in Sec. 110.30:

Actinium-225
Actinium-227
Californium-248
Californium-250
Californium-252
Californium-253
Californium-254
Curium-240
Curium-241
Curium-242
Curium-243
Curium-244
Einsteinium-252
Einsteinium-253
Einsteinium-254
Einsteinium-255
Fermium-257

[[Page 708]]

Gadolinium-148
Mendelevium-258
Neptunium-235
Polonium-208
Polonium-209
Polonium-210
Radium-223

    (5)(i) For americium-241, exports under the general license to a 
country listed in Sec. 110.29 must not exceed 3.7 x 10-2 TBq 
(one curie) per shipment.
    (ii) For americium-241, exports under the general license to a 
country listed in Sec. 110.29 that exceed 3.7 x 10-2 TBq 
(one curie) per shipment, must be contained in industrial process 
control equipment or petroleum exploration equipment in quantities not 
exceeding 0.60 TBq (16 curies) per device and not exceeding 7.4 TBq/
calendar year (200 curies/calendar year) to any one country.
    (iii) All exports of americium are subject to the reporting 
requirements listed in Sec. 110.54(b).
    (6) For neptunium-235 and -237, exports under the general license 
must not exceed one gram for individual shipment and must not exceed a 
cumulative total of 10 grams per calendar year to any one country. All 
exports of neptunium are subject to the reporting requirements listed in 
Sec. 110.54(b).
    (7) For polonium-210, exports under the general license, when 
contained in static eliminators, must not exceed 3.7 TBq (100 curies) 
per individual shipment.
    (8)(i) For tritium in any dispersed form (e.g., luminescent light 
sources and paint, accelerator targets, calibration standards, labeled 
compounds), exports under the general license must not exceed 0.37 TBq 
(10 curies (1.03 milligrams)) per item, not to exceed 37 TBq (1,000 
curies (103 milligrams)) per shipment, or 370 TBq (10,000 curies (1.03 
grams)) per calendar year to any one country.
    (ii) For tritium in any dispersed form (e.g., luminescent light 
sources and paint, accelerator targets, calibration standards, labeled 
compounds), exports under the general license to the countries listed in 
Sec. 110.30 must not exceed the quantity of 1.48 TBq (40 curies (4.12 
milligrams)) per item, not to exceed 37 TBq (1,000 curies (103 
milligrams)) per shipment or 370 TBq (10,000 curies (1.03 grams)) per 
calendar year to any one country.
    (iii) For tritium in luminescent safety devices installed in an 
aircraft, exports under the general license must not exceed 1.48 TBq (40 
curies (4.12 milligrams)) per light source.
    (iv) The general license in this section does not authorize the 
export of tritium for recovery or recycle purposes.
    (b) [Reserved]

[75 FR 44088, July 28, 2010, as amended at 82 FR 52826, Nov. 15, 2017]



Sec. 110.24  General license for the export of deuterium.

    (a) A general license is issued to any person to export to any 
country not listed in Sec. 110.28 or Sec. 110.29 deuterium in 
individual shipments of 10 kilograms or less (50 kilograms of heavy 
water). No person may export more than 200 kilograms (1,000 kilograms of 
heavy water) per calendar year to any one country.
    (b) A general license is issued to any person to export to any 
country listed in Sec. 110.29 deuterium in individual shipments of 1 
kilogram or less (5 kilograms of heavy water). No person may export more 
than 5 kilograms (25 kilograms of heavy water) per calendar year to any 
one country listed in Sec. 110.29.

[75 FR 44088, July 28, 2010]



Sec. 110.25  [Reserved]



Sec. 110.26  General license for the export of nuclear reactor
components.

    (a) A general license is issued to any person to export to a 
destination listed in paragraph (b) of this section any nuclear reactor 
component of U.S. origin described in paragraphs (5) through (11) of 
appendix A to this part if--
    (1) The component will be used in a light or heavy water-moderated 
power or research reactor; or
    (2) The component is in semifabricated form and will be undergoing 
final fabrication or repair in those countries for either subsequent 
return to the United States for use in a nuclear power or research 
reactor in the United States or in one of the destinations listed in 
paragraph (b) of this section.
    (b) The export of nuclear reactor components under the general 
license

[[Page 709]]

established in paragraph (a) of this section is approved to the 
following destinations:

Austria
Belgium
Bulgaria
Canada
Cyprus
Czech Republic
Denmark
Estonia
Finland
France
Germany
Greece
Hungary
Indonesia
Ireland
Italy
Japan
Latvia
Lithuania
Luxembourg
Malta
Netherlands
New Zealand
Philippines
Poland
Portugal
Republic of Korea
Romania
Slovak Republic
Slovenia
Spain
Sweden
Switzerland
Taiwan
United Kingdom

    (c) This general license does not authorize the export of 
components, in final or semi-fabricated form, for research reactors 
capable of continuous operation above 5 MW thermal.
    (d) This general license does not authorize the export of 
essentially complete reactors through piecemeal exports of facility 
components. When individual exports of components would amount in the 
aggregate to export of an essentially complete nuclear reactor, a 
facility export license is required.
    (e) All exports under paragraph (a) of this section are subject to 
the reporting requirements in Sec. 110.54(c).

    Note to Sec. 110.26: U.S. Origin includes components produced or 
finished in the United States, even with non-U.S. content unless the 
foreign content is obligated by supplier government conditions, such as 
a prior consent for retransfer condition.

[75 FR 44089, July 28, 2010, as amended at 79 FR 39291, July 10, 2014]



Sec. 110.27  General license for imports.

    (a) Except as provided in paragraphs (b) and (c) of this section, a 
general license is issued to any person to import byproduct, source, or 
special nuclear material if the U.S. consignee is authorized to receive 
and possess the material under the relevant NRC or Agreement State 
regulations.
    (b) The general license in paragraph (a) of this section does not 
authorize the import of more than 100 kilograms per shipment of source 
and/or special nuclear material in the form of irradiated fuel.
    (c) Paragraph (a) of this section does not authorize the import 
under a general license of radioactive waste.
    (d) A person importing formula quantities of strategic special 
nuclear material (as defined in Sec. 73.2 of this chapter) under this 
general license shall provide the notifications required by Sec. 73.27 
and Sec. 73.72 of this chapter.
    (e) A general license is issued to any person to import the major 
components of a utilization facility as defined in Sec. 110.2 for end-
use at a utilization facility licensed by the Commission.
    (f) Importers of radioactive material listed in appendix P to this 
part must provide the notifications required by Sec. 110.50.

[51 FR 47208, Dec. 31, 1986, as amended at 56 FR 38336, Aug. 13, 1991; 
58 FR 13003, Mar. 9, 1993; 60 FR 37564, July 21, 1995; 61 FR 35602, July 
8, 1996; 65 FR 70291, Nov. 22, 2000; 68 FR 31589, May 28, 2003; 70 FR 
37991, July 1, 2005; 75 FR 44089, July 28, 2010; 77 FR 27114, May 9, 
2012]



Sec. 110.28  Embargoed destinations.

Cuba
Iran
Iraq
North Korea
Syria
Sudan

[58 FR 13003, Mar. 9, 1993, as amended at 61 FR 35602, July 8, 1996; 65 
FR 70291, Nov. 22, 2000; 70 FR 29936, May 25, 2005; 72 FR 1427, Jan. 12, 
2007]



Sec. 110.29  Restricted destinations.

Afghanistan
Andorra
Angola
Burma (Myanmar)
Djibouti
India
Israel
Libya
Pakistan
South Sudan

[58 FR 13003, Mar. 9, 1993, as amended at 59 FR 48998, Sept. 26, 1994; 
61 FR 35602, July 8, 1996; 70 FR 29936, May 25, 2005; 72 FR 1427, Jan. 
12, 2007; 77 FR 11385, Feb. 27, 2012; 78 FR 8361, Feb. 6, 2013]



Sec. 110.30  Members of the Nuclear Suppliers Group.

Argentina
Australia
Austria
Belarus
Belgium
Brazil
Bulgaria
Canada
China
Croatia
Cyprus
Czech Republic
Denmark
Estonia
Finland
France

[[Page 710]]


Germany
Greece
Hungary
Iceland
Ireland
Italy
Japan
Kazakhstan
Latvia
Lithuania
Luxembourg
Malta
Mexico
Netherlands
New Zealand
Norway
Poland
Portugal
Republic of Korea
Romania
Russia
Serbia
Slovak Republic
Slovenia
South Africa
Spain
Sweden
Switzerland
Turkey
Ukraine
United Kingdom

[59 FR 48998, Sept. 26, 1994, as amended at 61 FR 35602, July 8, 1996; 
65 FR 70291, Nov. 22, 2000; 75 FR 44089, July 28, 2010; 79 FR 39291, 
July 10, 2014]



Sec. 110.31  Application for a specific license.

    (a) A person shall file an application for a specific license to 
export or import with the Deputy Director of the NRC's Office of 
International Programs, using an appropriate method listed in Sec. 
110.4.
    (b) Applications for an export, import, amendment or renewal 
licenses or a request for an exemption from a licensing requirement 
under this part shall be filed on NRC Form 7.
    (c) An application for a specific license to export or import or a 
request for an exemption from a licensing requirement must be 
accompanied by the appropriate fee in accordance with the fee schedules 
in Sec. 170.21 and Sec. 170.31 of this chapter. A license application 
will not be processed unless the specified fee is received.
    (d) Each application on NRC Form 7 shall be signed by the applicant 
or licensee or a person duly authorized to act for and on behalf of the 
applicant or licensee.
    (e) Each person shall provide in the license application, as 
appropriate, the information specified in Sec. 110.32. The Commission 
also may require the submission of additional information if necessary 
to complete its review.
    (f) An application may cover multiple shipments and destinations.
    (g) The applicant shall withdraw an application when it is no longer 
needed. The Commission's official files retain all documents related to 
a withdrawn application.

[75 FR 44089, July 28, 2010]



Sec. 110.32  Information required in an application for a specific
license/NRC Form 7.

    (a) Name and address of applicant.
    (b) Name and address of any other party, including the supplier of 
equipment or material, if different from the applicant.
    (c) Country of origin of equipment or material, and any other 
countries that have processed the material prior to its import into the 
U.S.

    Note: This is meant to include all obligations attached to the 
material, according to the definition of obligations in Sec. 110.2. 
Licensees must keep records of obligations attached to material which 
they own or is in their possession.

    (d) Names and addresses of all intermediate and ultimate consignees, 
other than intermediate consignees performing shipping services only.
    (e) Dates of proposed first and last shipments.
    (f) Description of the equipment or material including, as 
appropriate, the following:
    (1) Maximum quantity of material in grams or kilograms 
(terabecquerels or TBq for byproduct material) and its chemical and 
physical form.
    (2) For enriched uranium, the maximum weight percentage of 
enrichment and maximum weight of contained uranium-235.
    (3) For nuclear equipment, the name of the facility and its total 
dollar value.
    (4) For nuclear reactors, the name of the facility, its design power 
level and its total dollar value.
    (5) For proposed exports or imports of radioactive waste, the 
volume, physical and chemical characteristics, route of transit of 
shipment, classification (as defined in Sec. 61.55 of this chapter) if 
imported or exported for direct disposal at part 61 or equivalent 
Agreement State licensed facility, and ultimate disposition (including 
forms of management or treatment) of the waste.
    (6) For proposed imports of radioactive waste, the industrial or 
other process responsible for generation of

[[Page 711]]

the waste, and the status of the arrangements for disposition, including 
pertinent documentation of these arrangements.
    (7) Description of end use by all consignees in sufficient detail to 
permit accurate evaluation of the justification for the proposed export 
or import, including the need for shipment by the dates specified.
    (g)(1) For proposed exports of Category 1 quantities of material 
listed in Table 1 of appendix P to this part, pertinent documentation 
that the recipient of the material has the necessary authorization under 
the laws and regulations of the importing country to receive and possess 
the material.
    (2) For proposed exports of Category 2 quantities of material listed 
in Table 1 of appendix P to this part, pertinent documentation that the 
recipient of the material has the necessary authorization under the laws 
and regulations of the importing country to receive and possess the 
material. This documentation must be provided to the NRC at least 24 
hours prior to the shipment.
    (3) Pertinent documentation shall consist of a copy of the 
recipient's authorization to receive and possess the material to be 
exported or a confirmation from the government of the importing country 
that the recipient is so authorized. The recipient authorization shall 
include the following information:
    (i) Name of the recipient;
    (ii) Recipient location and legal address or principal place of 
business;
    (iii) Relevant radionuclides and radioactivity being imported or 
that the recipient is authorized to receive and possess;
    (iv) Uses, if appropriate; and
    (v) The expiration date of the recipient's authorization (if any).

[75 FR 44089, July 28, 2010, as amended at 82 FR 52826, Nov. 15, 2017]



                Subpart D_Review of License Applications



Sec. 110.40  Commission review.

    (a) Immediately after receipt of a license application for an export 
or import requiring a specific license under this part, the Commission 
will initiate its licensing review and, to the maximum extent feasible, 
will expeditiously process the application concurrently with any 
applicable review by the Executive Branch.
    (b) The Commissioners shall review a license application for export 
of the following:
    (1) A production or utilization facility.
    (2) More than 5 effective kilograms of high-enriched uranium, 
plutonium or uranium-233.
    (3) An export involving assistance to end uses related to isotope 
separation, chemical reprocessing, heavy water production, advanced 
reactors, or the fabrication of nuclear fuel containing plutonium, 
except for exports of source material or low-enriched uranium to EURATOM 
or Japan for enrichment up to 5 percent in the isotope uranium-235, and 
those categories of exports which the Commission has approved in advance 
as constituting permitted incidental assistance.
    (4) The initial export to a country since March 10, 1978 of source 
or special nuclear material for nuclear end use.
    (5) An initial export to any country listed in Sec. 110.28 or Sec. 
110.29 involving over:
    (i) 10 grams of plutonium, uranium-233 or high-enriched uranium;
    (ii) 1 effective kilogram of low-enriched uranium;
    (iii) 250 kilograms of source material or heavy water; or
    (iv) 37 TBq (1,000 curies) of tritium.
    (6) The export of radioactive material listed in Table 1 of Appendix 
P of this part involving:
    (i) Exceptional circumstances in Sec. 110.42(e); or
    (ii) Category 1 quantities of material to any country listed in 
Sec. 110.28.
    (c) The Commission will review export and import license 
applications raising significant policy issues.
    (d) If the Commission has not completed action on a license 
application within 60 days after receipt of the Executive Branch 
judgment, as provided for in Sec. 110.41, or the license application 
when an Executive Branch judgment is not required, it will inform the 
applicant in writing of the reason for delay

[[Page 712]]

and, as appropriate, provide follow-up reports.

[75 FR 44090, July 28, 2010]



Sec. 110.41  Executive Branch review.

    (a) An application for a license to export the following will be 
promptly forwarded to the Executive Branch for review:
    (1) A production or utilization facility.
    (2) More than one effective kilogram of high-enriched uranium or 10 
grams of plutonium or uranium-233.
    (3) Nuclear grade graphite for nuclear end use.
    (4) More than 3.7 TBq (100 curies) of tritium, and deuterium oxide 
(heavy water), other than exports of heavy water to Canada.
    (5) One kilogram or more of source or special nuclear material to be 
exported under the US-IAEA Agreement for Cooperation.
    (6) An export involving assistance to end uses related to isotope 
separation, chemical reprocessing, heavy water production, advanced 
reactors, or the fabrication of nuclear fuel containing plutonium, 
except for exports of source material or low-enriched uranium to EURATOM 
and Japan for enrichment up to 5 percent in the isotope uranium-235, and 
those categories of exports approved in advance by the Executive Branch 
as constituting permitted incidental assistance.
    (7) The initial export of nuclear material or equipment to a foreign 
reactor.
    (8) An export involving radioactive waste.
    (9) An export to any country listed in Sec. 110.28 or Sec. 110.29.
    (10) An export raising significant policy issues or subject to 
special limitations as determined by the Commission or the Executive 
Branch, including exports of radioactive material listed in Table 1 of 
appendix P to this part involving exceptional circumstances in Sec. 
110.42(e).
    (b) The Executive Branch will be requested to:
    (1) Provide its judgment as to whether the proposed export would be 
inimical to the common defense and security, along with supporting 
rationale and information.
    (2) Where applicable, confirm that the proposed export would be 
under the terms of an agreement for cooperation; and
    (3) Address the extent to which the export criteria in Sec. 110.42 
are met, if applicable, and the extent to which the recipient country or 
group of countries has adhered to the provisions of any applicable 
agreement for cooperation.
    (c) The Commission may request the Executive Branch to address 
specific concerns and provide additional data and recommendations as 
necessary.

[43 FR 21641, May 19, 1978, as amended at 49 FR 47200, Dec. 3, 1984; 58 
FR 13004, Mar. 9, 1993; 60 FR 37564, July 21, 1995; 61 FR 35602, July 8, 
1996; 70 FR 41939, July 21, 2005; 70 FR 37992, July 1, 2005; 70 FR 
46066, Aug. 9, 2005; 75 FR 44090, July 28, 2010]



Sec. 110.42  Export licensing criteria.

    (a) The review of license applications for export for peaceful 
nuclear uses of production or utilization facilities \1\ or for export 
for peaceful nuclear uses of special nuclear or source material 
requiring a specific license under this part is governed by the 
following criteria:
---------------------------------------------------------------------------

    \1\ Export of nuclear reactors, reactor pressure vessels, reactor 
primary coolant pumps and circulators, ``on-line'' reactor fuel charging 
and discharging machines, and complete reactor control rod systems, as 
specified in paragraphs (1) through (4) of appendix A to this part, are 
subject to the export licensing criteria in Sec. 110.42(a). Exports of 
nuclear reactor components, as specified in paragraphs (5) through (11) 
of appendix A to this part, when exported separately from the items 
described in paragraphs (1) through (4) of appendix A to this part, are 
subject to the export licensing criteria in Sec. 110.42(b).
---------------------------------------------------------------------------

    (1) IAEA safeguards as required by Article III (2) of the NPT will 
be applied with respect to any such facilities or material proposed to 
be exported, to any such material or facilities previously exported and 
subject to the applicable agreement for cooperation, and to any special 
nuclear material used in or produced through the use thereof.
    (2) No such material or facilities proposed to be exported or 
previously exported and subject to the applicable agreement for 
cooperation, and no special nuclear material produced through the use of 
such material or facilities,

[[Page 713]]

will be used for any nuclear explosive device or for research on or 
development of any nuclear explosive device.
    (3) Adequate physical security measures will be maintained with 
respect to such material or facilities proposed to be exported and to 
any special nuclear material used in or produced through the use 
thereof. Physical security measures will be deemed adequate if such 
measures provide a level of protection equivalent to that set forth in 
Sec. 110.44.
    (4) No such material or facilities proposed to be exported, and no 
special nuclear material produced through the use of such material, will 
be retransferred to the jurisdiction of any other country or group of 
countries unless the prior approval of the United States is obtained for 
such retransfer.
    (5) No such material proposed to be exported and no special nuclear 
material produced through the use of such material will be reprocessed, 
and no irradiated fuel elements containing such material removed from a 
reactor will be altered in form or content, unless the prior approval of 
the United States is obtained for such reprocessing or alteration.
    (6) With respect to exports of such material or facilities to 
nonnuclear weapon states, IAEA safeguards will be maintained with 
respect to all peaceful activities in, under the jurisdiction of, or 
carried out under the control of such state at the time of export. This 
criterion will not be applied if the Commission has been notified by the 
President in writing that failure to approve an export because this 
criterion has not been met would be seriously prejudicial to the 
achievement of United States nonproliferation objectives or otherwise 
jeopardize the common defense and security, in which case the provisions 
of section 128 of the Atomic Energy Act regarding Congressional review 
will apply.
    (7) The proposed export of a facility or of more than 0.003 
effective kilograms of special nuclear material, other than plutonium 
containing 80 percent or more by weight of plutonium-238, would be under 
the terms of an agreement for cooperation.
    (8) The proposed export is not inimical to the common defense and 
security and, in the case of facility exports, does not constitute an 
unreasonable risk to the public health and safety in the United States.
    (9)(i) Except as provided in paragraph (a)(9)(ii) of this section, 
with respect to exports of high-enriched uranium to be used as a fuel or 
target in a nuclear research or test reactor, the Commission determines 
that:
    (A) There is no alternative nuclear reactor fuel or target enriched 
to less than 20 percent in the isotope U-235 that can be used in that 
reactor;
    (B) The proposed recipient of the uranium has provided assurances 
that, whenever an alternative nuclear reactor fuel or target can be used 
in that reactor, it will use that alternative fuel or target in lieu of 
highly-enriched uranium; and
    (C) The United States Government is actively developing an 
alternative nuclear reactor fuel or target that can be used in that 
reactor.
    (ii) With regard to a Recipient Country, the Commission may issue a 
license authorizing the export of high-enriched uranium for medical 
isotope production, including shipment to and use at intermediate and 
ultimate consignees, if the Commission determines that:
    (A) The Recipient Country that supplies an assurance letter to the 
United States Government in connection with the consideration by the 
Commission of the export license application has informed the United 
States Government that any intermediate consignees and the ultimate 
consignee specified in the export license application are required to 
use the high-enriched uranium solely for the production of medical 
isotopes; and
    (B) The high-enriched uranium will be irradiated only in a reactor 
in the Recipient Country that--
    (1) Uses an alternative nuclear fuel; or
    (2) Is the subject of an agreement with the United States Government 
to convert to an alternative nuclear reactor fuel when alternative 
nuclear reactor fuel can be used in the reactor.
    (iii) A fuel or target ``can be used'' in a nuclear research or test 
reactor if--

[[Page 714]]

    (A) The fuel or target has been qualified by the Reduced Enrichment 
Research and Test Reactor Program of the Department of Energy; and
    (B) Use of the fuel or target will permit the large majority of 
ongoing and planned experiments and isotope production to be conducted 
in the reactor without a large percentage increase in the total cost of 
operating the reactor.
    (b) The review of license applications for the export of nuclear 
equipment, other than a production or utilization facility, and for 
deuterium and nuclear grade graphite for nuclear end use, is governed by 
the following criteria:
    (1) IAEA safeguards as required by Article III (2) of the NPT will 
be applied with respect to such equipment or material.
    (2) No such equipment or material will be used for any nuclear 
explosive device or for research on or development of any nuclear 
explosive device.
    (3) No such equipment or material will be retransferred to the 
jurisdiction of any other country or group of countries without the 
prior consent of the United States.
    (4) The proposed export is not inimical to the common defense and 
security.
    (c) Except where paragraph (d) is applicable, the review of license 
applications for export of byproduct material or for export of source 
material for non-nuclear end uses requiring a specific license under 
this part is governed by the criterion that the proposed export is not 
inimical to the common defense and security.
    (d) The review of license applications for the export of radioactive 
waste requiring a specific license under this part is governed by the 
following criteria:
    (1) The proposed export is not inimical to the common defense and 
security.
    (2) The receiving country, after being advised of the information 
required by Sec. 110.32(f)(5), finds that it has the administrative and 
technical capacity and regulatory structure to manage and dispose of the 
waste and consents to the receipt of the radioactive waste. In the case 
of radioactive waste containing a nuclear material to which paragraph 
(a) or (b) of this section is applicable, the criteria in this paragraph 
(d) shall be in addition to the criteria provided in paragraph (a) or 
(b) of this section.
    (e) In making its findings under paragraphs (a)(8) and (c) of this 
section for proposed exports of radioactive material listed in Appendix 
P to this part, the NRC shall consider:
    (1) Whether the foreign recipient is authorized based on the 
authorization or confirmation required by Sec. 110.32(h) to receive and 
possess the material under the laws and regulations of the importing 
country;
    (2) Whether the importing country has the appropriate technical and 
administrative capability, resources and regulatory structure to manage 
the material in a safe and secure manner;
    (3) For proposed exports of Category 1 amounts of radioactive 
material listed in Table 1 of Appendix P to this part, whether the 
government of the importing country provides consent to the United 
States Government for the import of the material;
    (4) In cases where the importing country does not have the technical 
and administrative capability described in paragraph (e)(2) of this 
section, and in cases where there is insufficient evidence of the 
recipient's authorization to receive and possess the material to be 
exported, described in paragraph (e)(1) of this section, whether 
exceptional circumstances exist, and if so, whether the export should be 
licensed in light of those exceptional circumstances and the risks, if 
any, to the common defense and security of the proposed export;
    (5) For proposed exports under exceptional circumstances of Category 
1 or Category 2 amounts of radioactive material listed in Table 1 of 
Appendix P to this part, whether the government of the importing country 
provides consent to the United States Government for the import of the 
material;
    (6) For proposed exports of radioactive material listed in Table 1 
of Appendix P to this part under the exceptional circumstance in which 
there is a considerable health or medical need as acknowledged by the 
U.S. Government and the importing country, whether the United States and 
the importing

[[Page 715]]

country have, to the extent practicable, made arrangements for the safe 
and secure management of the radioactive sources during and at the end 
of their useful life;
    (7) Based upon the available information, whether the foreign 
recipient has engaged in clandestine or illegal procurement of 
radioactive material listed in Table 1 of Appendix P to the part;
    (8) Based upon available information, whether an import or export 
authorization for radioactive material listed in Table 1 of Appendix P 
to this part has been denied to the recipient or importing country, or 
whether the recipient or importing country has diverted any import or 
export of radioactive material previously authorized; and
    (9) Based upon available information, whether there is a risk of 
diversion or malicious acts involving radioactive material in Table 1 of 
Appendix P to this part.

[49 FR 47200, Dec. 3, 1984, as amended at 55 FR 34519, Aug. 23, 1990; 58 
FR 13004, Mar. 9, 1993; 58 FR 57964, Oct. 28, 1993; 60 FR 37564, July 
21, 1995; 70 FR 37992, July 1, 2005; 70 FR 41939, July 21, 2005; 70 FR 
46066, Aug. 9, 2005; 71 FR 20339, Apr. 20, 2006; 71 FR 40003, July 14, 
2006; 79 FR 39291, July 10, 2014]



Sec. 110.43  Import licensing criteria.

    The review of license applications for imports requiring a specific 
license under this part is governed by the following criteria:
    (a) The proposed import is not inimical to the common defense and 
security.
    (b) The proposed import does not constitute an unreasonable risk to 
the public health and safety.
    (c) Any applicable requirements of subpart A of part 51 of this 
chapter are satisfied.
    (d) With respect to the import of radioactive waste, an appropriate 
facility has agreed to accept and is authorized to possess the waste for 
management or disposal as confirmed by NRC consultations with, as 
applicable, the Agreement State in which the facility is located and 
low-level waste compact commission(s).

[60 FR 37565, July 21, 1995, as amended at 70 FR 37992, July 1, 2005; 75 
FR 44090, July 28, 2010]



Sec. 110.44  Physical security standards.

    (a) Physical security measures in recipient countries must provide 
protection at least comparable to the recommendations in the current 
version of IAEA publication, ``Nuclear Security Recommendations on 
Physical Protection of Nuclear Material and Nuclear Facilities'' 
(INFCIRC/225/Revision 5), January 2011, which is incorporated by 
reference in this part. This incorporation by reference was approved by 
the Director of the Office of the Federal Register in accordance with 5 
U.S.C. 552(a) and 1 CFR part 51. Notice of any changes made to the 
material incorporated by reference will be published in the Federal 
Register. Copies of INFCIRC/225/Revision 5 may be obtained from the 
Marketing and Sales Unit, Publishing Section, IAEA, Vienna International 
Centre, P.O. Box 100, 1400 Vienna Austria; Fax: 43 1 2600 29302; 
telephone: 43 1 2600 22417; email: [email protected]; Web 
site: http://www.iaea.org/books. You may inspect a copy at the NRC 
Library, 11545 Rockville Pike, Rockville, Maryland 20852-2738, 
telephone: 301-415-4737 or 1-800-397-4209, between 8:30 a.m. and 4:15 
p.m.; or at the National Archives and Records Administration (NARA). For 
information on the availability of this material at NARA, call 202-741-
6030, or go to: http://www.archives.gov/federal-register/cfr/ibr-
locations.html.
    (b) Commission determinations on the adequacy of physical security 
measures are based on:
    (1) Receipt by the appropriate U.S. Executive Branch Agency of 
written assurances from the relevant recipient country government that 
physical security measures providing protection at least comparable to 
the recommendations set forth in INFCIRC/225/Revision 5.
    (2) Information obtained through country visits, information 
exchanges, or other sources. Determinations are made on a country-wide 
basis and are subject to continuing review. Appendix M to this part 
describes the different categories of nuclear material to which physical 
security measures are applied.

[75 FR 44090, July 28, 2010, as amended at 79 FR 39291, July 10, 2014]

[[Page 716]]



Sec. 110.45  Issuance or denial of licenses.

    (a) The Commission will issue an export license if it has been 
notified by the State Department that it is the judgment of the 
Executive Branch that the proposed export will not be inimical to the 
common defense and security, and:
    (1) Finds, based upon a reasonable judgment of the assurances 
provided and other information available to the Federal government, that 
the applicable criteria in Sec. 110.42, or their equivalent, are met.
    (2) Finds that there are no material changed circumstances 
associated with an export license application (except for byproduct 
material applications) from those existing at the time of issuance of a 
prior license to export to the same country, if the prior license was 
issued under the provisions of paragraph (a)(1) of this section.
    (b) The Commission will issue an import license if it finds that:
    (1) The proposed import will not be inimical to the common defense 
and security;
    (2) The proposed import will not constitute an unreasonable risk to 
the public health and safety;
    (3) The requirements of subpart A of part 51 of this chapter (to the 
extent applicable to the proposed import) have been satisfied; and
    (4) With respect to a proposed import of radioactive waste, an 
appropriate facility has agreed to accept and is authorized to posses 
the waste for management or disposal as confirmed by NRC consultations 
with, as applicable, the Agreement State(s) in which the facility is 
located and the low-level waste compact commission(s).
    (c) With respect to a proposed import of radioactive material listed 
in Table 1 of Appendix P to this part:
    (1) If the Commission authorizes a proposed import of Category 1 or 
Category 2 amounts of radioactive material, it will take appropriate 
steps to ensure that a copy of the recipient authorization, or 
confirmation by the U.S. Government that the recipient is authorized to 
receive and possess the source or sources to be exported, is provided to 
the Government of the exporting country or to the exporting facility.
    (2) If the Commission authorizes a proposed import of Category 1 
amounts of radioactive material, it will take appropriate steps to 
ensure that a copy of the consent of the United States Government to the 
import is provided to the government of the exporting country in cases 
where it is requested by such government.
    (d) If, after receiving the Executive Branch judgment that the 
issuance of a proposed export license will not be inimical to the common 
defense and security, the Commission does not issue the proposed license 
on a timely basis because it is unable to make the statutory 
determinations required under the Atomic Energy Act, the Commission will 
publicly issue a decision to that effect and will submit the license 
application to the President. The Commission's decision will include an 
explanation of the basis for the decision and any dissenting or separate 
views. The provisions in this paragraph do not apply to Commission 
decisions regarding applications for specific licenses to export 
byproduct material, including radioactive material listed in Table 1 of 
appendix P to this part, or radioactive waste.
    (e) The Commission will deny: (1) Any export license application for 
which the Executive Branch judgment does not recommend approval; (2) any 
byproduct material export license application for which the Commission 
is unable to make the finding in paragraph (a)(1) of this section; or 
(3) any import license application for which the Commission is unable to 
make the finding in paragraph (b) of this section. The applicant will be 
notified in writing of the reason for denial.

[49 FR 47201, Dec. 3, 1984. Redesignated and amended at 60 FR 37565, 
July 21, 1995; 70 FR 37992, July 1, 2005; 75 FR 44091, July 28, 2010]



Sec. 110.46  Conduct resulting in termination of nuclear exports.

    (a) Except as provided in paragraph (c) of this section, no license 
will be issued to export nuclear equipment or material, other than 
byproduct material, to any non-nuclear weapon state that is found by the 
President to have, after March 10, 1978:
    (1) Detonated a nuclear explosive device;

[[Page 717]]

    (2) Terminated or abrogated IAEA safeguards;
    (3) Materially violated an IAEA safeguards agreement; or
    (4) Engaged in activities involving source or special nuclear 
material and having direct significance for the manufacture or 
acquisition of nuclear explosive devices, and failed to take steps which 
represent sufficient progress toward terminating such activities.
    (b) Except as provided in paragraph (c) of this section, no license 
will be issued to export nuclear equipment or material, other than 
byproduct material, to any country or group of countries that is found 
by the President to have, after March 10, 1978:
    (1) Materially violated an agreement for cooperation with the United 
States or the terms of any other agreement under which nuclear equipment 
or material has been exported;
    (2) Assisted, encouraged or induced any non-nuclear weapon state to 
engage in activities involving source or special nuclear material and 
having direct significance for the manufacture or acquistion of nuclear 
explosive devices, and failed to take steps which represent sufficient 
progress toward terminating such assistance, encouragement or 
inducement; or
    (3) Entered into an agreement for the transfer of reprocessing 
equipment, materials or technology to the sovereign control of a non-
nuclear weapon state, except in connection with an international fuel 
cycle evaluation in which the United States is a participant or pursuant 
to an international agreement or understanding to which the United 
States subscribes.
    (c) Under section 129 of the Atomic Energy Act, the President may 
waive the requirement for the termination of exports to a country 
described in paragraph (a) or (b) of this section after determining in 
writing that the cessation of exports would seriously prejudice the 
achievement of United States nonproliferation objectives or otherwise 
jeopardize the common defense and security. If the President makes this 
determination, the Commission will issue licenses to export to that 
country, if other applicable statutory provisions are met.

[43 FR 21641, May 19, 1978, as amended at 49 FR 47202, Dec. 3, 1984. 
Redesignated at 60 FR 37565, July 21, 1995]



             Subpart E_License Terms and Related Provisions



Sec. 110.50  Terms.

    (a) General and specific licenses. (1) Each license is subject to 
all applicable provisions of the Atomic Energy Act and other applicable 
law and to all applicable rules, regulations, decisions and orders of 
the Commission.
    (2) Each license is subject to amendment, suspension, revocation or 
incorporation of separate conditions when required by amendments of the 
Atomic Energy Act or other applicable law, or by other rules, 
regulations, decisions or orders issued in accordance with the terms of 
the Atomic Energy Act or other applicable law.
    (3) A licensee authorized to export or import nuclear material is 
responsible for compliance with applicable requirements of this chapter, 
unless a domestic licensee of the Commission has assumed that 
responsibility and the Commission has been so notified.
    (4) Each license authorizes export or import only and does not 
authorize any person to receive title to, acquire, receive, possess, 
deliver, use, transport or transfer any nuclear equipment or material 
subject to this part.
    (5) Each license issued by the NRC for the export or import of 
nuclear material authorizes only the export or import of that nuclear 
material and accompanying packaging, fuel element, hardware, or other 
associated devices or products.
    (6) No nuclear equipment license confers authority to export or 
import nuclear material.
    (7) Each nuclear equipment export license authorizes the export of 
only those items required for use in the foreign nuclear installation 
for which the items are intended.
    (8) A licensee shall not proceed to export or import and shall 
notify the Commission promptly if he knows or has reason to believe that 
the packaging requirements of part 71 of this chapter have not been met.

[[Page 718]]

    (b) Specific licenses. (1) Each specific license will have an 
expiration date.
    (2) A licensee may export or import only for the purpose(s) and/or 
end-use(s) stated in the specific export or import license issued by 
NRC.
    (3) Unless a license specifically authorizes the export of certain 
foreign-obligated nuclear material or equipment, a licensee may not ship 
such material or equipment until:
    (i) The licensee has requested and the Commission has issued an 
amendment to the license authorizing such shipment; or
    (ii) The licensee has given at least 40 days advance notice of the 
intended shipment in writing to the Deputy Director, Office of 
International Programs (OIP); and
    (iii) The Deputy Director, OIP has:
    (A) Obtained confirmation, through either the Department of Energy 
or State, that the foreign government in question has given its consent 
to the intended shipment pursuant to its agreement for cooperation with 
the United States; and
    (B) Communicated this in writing to the licensee.
    (c) Advanced notification. (1) A licensee authorized to export or 
import the radioactive material listed in Appendix P to this part is 
responsible for notifying NRC and, in cases of exports, the government 
of the importing country in advance of each shipment. A list of points 
of contact in importing countries is available at NRC's Office of 
International Programs Web site, accessible on the NRC Public Web site 
at http://www.nrc.gov.
    (2) The NRC's office responsible for receiving advance notifications 
for all export and import shipments is the NRC Operations Center. 
Notifications are to be e-mailed to [email protected] (preferred method) 
or faxed to (301) 816-5151. In the subject line of the e-mail or on the 
fax cover page include ``10 CFR 110.50(c) Notification.'' To contact the 
NRC Operations Center, use the same e-mail address or call (301) 816-
5100. Difficulties notifying the NRC Operations Center must be promptly 
reported to the Office of International Programs at (301) 415-2336.
    (3) Notifications may be electronic or in writing on business 
stationary, and must contain or be accompanied by the information which 
follows.
    (i) For export notifications:
    (A) 10 CFR part 110 export license number and expiration date;
    (B) Name of the individual and licensee making the notification, 
address, and telephone number;
    (C) Foreign recipient name, address, and end use location(s) (if 
different than recipient's address);
    (D) Radionuclides and activity level in TBq, both for single and 
aggregate shipments;
    (E) Make, model and serial number, for any Category 1 and 2 sealed 
sources, if available;
    (F) End use in the importing country, if known;
    (G) Shipment date; and
    (H) A copy of the foreign recipient's authorization or confirmation 
of that authorization from the government of the importing country as 
required by Sec. 110.32(g) unless the authorization has already been 
provided to the NRC.
    (ii) For import notifications:
    (A) Name of individual and licensee making the notification, 
address, and telephone number;
    (B) Recipient name, location, and address (if different than above);
    (C) Name, location, address, contact name and telephone number for 
exporting facility;
    (D) Radionuclides and activity level in TBq, both for single and 
aggregate shipments;
    (E) Make, model and serial number, radionuclide, and activity level 
for any Category 1 and 2 sealed sources, if available;
    (F) End use in the U.S.;
    (G) Shipment date from exporting facility and estimated arrival date 
at the end use location; and
    (H) NRC or Agreement State license number to possess the import in 
the U.S. and expiration date.
    (4) Export notifications must be received by the NRC at least 7 days 
in advance of each shipment, to the extent practical, but in no case 
less than 24 hours in advance of each shipment. Import notifications 
must be received by the NRC at least 7 days in advance of each shipment.

[[Page 719]]

    (5) Advance notifications containing the above information must be 
controlled, handled, and transmitted in accordance with Sec. 2.390 of 
this chapter and other applicable NRC requirements governing protection 
of sensitive information.
    (d) A specific license may be transferred, disposed of or assigned 
to another person only with the approval of the Commission by license 
amendment.

[75 FR 44091, July 28, 2010]



Sec. 110.51  Amendment and renewal of licenses.

    (a) Amendments. (1) Applications for amendment of a specific license 
shall be filed on NRC Form 7 in accordance with Sec. Sec. 110.31 and 
110.32 and shall specify the respects in which the licensee desires the 
license to be amended and the grounds for such amendment.
    (2) An amendment is not required for:
    (i) Changes in monetary value (but not amount or quantity);
    (ii) Changes in the names and/or mailing addresses within the same 
countries of the intermediate or ultimate consignees listed on the 
license; or
    (iii) The addition of intermediate consignees in any of the 
importing countries specified in the license (for a nuclear equipment 
license only).
    (b) Renewals. (1) Applications for renewal of a specific license 
shall be filed on NRC Form 7 in accordance with Sec. Sec. 110.31 and 
110.32.
    (2) If an application to renew a license is submitted 30 days or 
more before the license expires, the license remains valid until the 
Commission acts on the renewal application. An expired license is not 
renewable.
    (c) General. In considering an application by a licensee to renew or 
amend a license, the Commission will apply, as appropriate, the same 
procedures and criteria it uses for initial license applications.

[75 FR 44092, July 28, 2010]



Sec. 110.52  Revocation, suspension, and modification.

    (a) A license may be revoked, suspended, or modified for a condition 
which would warrant denial of the original license application.
    (b) The Commission may require further information from a licensee 
to determine whether a license should be revoked, suspended, or 
modified.
    (c) Except when the common defense and security or public health and 
safety requires otherwise, no license will be revoked, suspended, or 
modified before the licensee is informed in writing of the grounds for 
such action and afforded the opportunity to reply and be heard under 
procedures patterned on those in subpart I.

[43 FR 21641, May 19, 1978, as amended at 62 FR 59277, Nov. 3, 1997]



Sec. 110.53  United States address, records, and inspections.

    (a) Each licensee (general or specific) shall have an office in the 
United States where papers may be served and where records required by 
the Commission will be maintained.
    (b)(1) Each license applicant or licensee (general or specific) 
shall maintain records concerning his exports or imports. The licensee 
shall retain these records for five years after each export or import 
except that byproduct material records must be retained for three years 
after the date of each export or import shipment.
    (2) Records which must be maintained pursuant to this part may be 
the original or a reproduced copy or microform if such reproduced copy 
or microform is duly authenticated by authorized personnel and the 
microform is capable of producing a clear and legible copy after storage 
for the period specified by Commission regulations. The record may also 
be stored in electronic media with the capability for producing legible, 
accurate, and complete records during the required retention period. 
Records such as letters, drawings, specifications, must include all 
pertinent information such as stamps, initials, and signatures. The 
licensee shall maintain adequate safeguards against tampering with and 
loss of records.
    (c) Each licensee shall permit the Commission to inspect his 
records, premises, and activities pertaining to

[[Page 720]]

his exports and imports when necessary to fulfill the requirements of 
the Atomic Energy Act.

[43 FR 21641, May 19, 1978, as amended at 53 FR 19263, May 27, 1988; 75 
FR 44092, July 28, 2010]



Sec. 110.54  Reporting requirements.

    (a)(1) Reports of exports of nuclear facilities and equipment, 
nuclear grade graphite for nuclear end use, and deuterium shipped during 
the previous quarter must be submitted by licensees making exports under 
the general license or specific license of this part by January 15, 
April 15, July 15, and October 15 of each year on DOC/NRC Forms AP-M or 
AP-13, and associated forms. The reports must contain information on all 
nuclear facilities, equipment, and non-nuclear materials (nuclear grade 
graphite for nuclear end use and deuterium) listed in Annex II of the 
Additional Protocol.
    (2) These required reports must be sent via facsimile to (202) 482-
1731, emailed to [email protected], or hand-delivered or submitted by 
courier to the Bureau of Industry and Security, in hard copy, to the 
following address: Treaty Compliance Division, Bureau of Industry and 
Security, U.S. Department of Commerce, Attn: AP Reports, 14th Street and 
Pennsylvania Avenue, NW., Room 4515, Washington, DC 20230. Telephone: 
(202) 482-1001.
    (b) Persons making exports under the general license established by 
Sec. 110.23(a) or under a specific license shall submit by February 1 
of each year one copy of a report of all americium and neptunium 
shipments during the previous calendar year. This report shall be 
submitted to the Deputy Director, Office of International Programs at 
the address provided in Sec. 110.4. The report must include:
    (1) A description of the material, including quantity in TBq and 
gram;
    (2) Approximate shipment dates; and
    (3) A list of recipient countries, end users, and intended use keyed 
to the items shipped.
    (c) Persons making exports under the general license established by 
Sec. 110.26(a) shall submit by February 1 of each year one copy of a 
report of all components shipped during the previous calendar year. This 
report shall be submitted to the Deputy Director, Office of 
International Programs at the address provided in Sec. 110.4. This 
report must include:
    (1) A description of the components keyed to the categories listed 
in appendix A to this part.
    (2) Approximate shipment dates.
    (3) A list of recipient countries and end users keyed to the items 
shipped.

[75 FR 44092, July 28, 2010, as amended at 77 FR 27114, May 9, 2012]



                  Subpart F_Violations and Enforcement



Sec. 110.60  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act;
    (2) Title II of the Energy Reorganization Act of 1974; or
    (3) A regulation or order pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of:
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act.

[75 FR 44092, July 28, 2010]



Sec. 110.61  Notice of violation.

    (a) Before instituting any enforcement action the Commission will 
serve on the licensee written notice of violation, except as provided in 
paragraph (d).
    (b) The notice will state the alleged violation; require the 
licensee to respond in writing, within 20 days or

[[Page 721]]

other specified time; and may also require the licensee to state the 
corrective steps taken or to be taken and the date when full compliance 
will be achieved.
    (c) The notice may provide that, if an adequate and timely reply is 
not received, an order to show cause may be issued pursuant to Sec. 
110.62 or a proceeding instituted to impose a civil penalty pursuant to 
Sec. 110.64.
    (d) The notice may be omitted and an order to show cause issued when 
the Commission determines that the violation is willful or that the 
public health, safety, or interest so requires.



Sec. 110.62  Order to show cause.

    (a) In response to an alleged violation, described in Sec. 110.60, 
the Commission may institute a proceeding to revoke, suspend, or modify 
a license by issuing an order to show cause:
    (1) Stating the alleged violation and proposed enforcement action; 
and
    (2) Informing the licensee of his right, within 20 days or other 
specified time, to file a written answer and demand a hearing.
    (b) An answer consenting to the proposed enforcement action shall 
constitute a waiver by the licensee of a hearing and of all rights to 
seek further Commission or judicial review.
    (c) The order to show cause may be omitted and an order issued to 
revoke, suspend, or modify the license in cases where the Commission 
determines that the violation is willful or that the public health, 
safety, or interest so requires.



Sec. 110.63  Order for revocation, suspension, or modification.

    (a) In response to an alleged violation described in Sec. 110.60, 
the Commission may revoke, suspend, or modify a license by issuing an 
order:
    (1) Stating the violation and the effective date of the proposed 
enforcement action; and
    (2) Informing the licensee of his right, within 20 days or other 
specified time, to file a written answer and demand a hearing.
    (b) If an answer is not filed within the time specified, the 
enforcement action will become effective and permanent as proposed.
    (c) If a timely answer is filed, the Commission, after considering 
the answer, will issue an order dismissing the proceeding, staying the 
effectiveness of the order or taking other appropriate action.
    (d) The order may be made effective immediately, with reasons 
stated, pending further hearing and order, when the Commission 
determines that the violation is willful or that the public health, 
safety, or interest so requires.



Sec. 110.64  Civil penalty.

    (a) In response to a violation, the Commission may institute a 
proceeding to impose a civil penalty under section 234 of the Atomic 
Energy Act by issuing a notice to the licensee:
    (1) Stating the alleged violation and the amount of the proposed 
penalty;
    (2) Informing the licensee of his right, within 20 days or other 
specified time, to file a written answer; and
    (3) Advising that a delinquent payment for a subsequently imposed 
penalty may be referred to the Attorney General for collection pursuant 
to section 234c. of the Atomic Energy Act.
    (b) If an answer is not filed within the time specified, the 
Commission will issue an order imposing the proposed penalty.
    (c) If a timely answer is filed, the Commission, after considering 
the answer, will issue an order dismissing the proceeding or imposing a 
penalty subject to any required hearing.
    (d) If an order imposing a civil penalty is issued, the licensee may 
request a hearing within 20 days or other specified time.
    (e) Except when the matter has been referred to the Attorney General 
for collection, payment of penalties shall be made by check, draft, or 
money order payable to the Treasurer of the United States, and mailed to 
the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
    (f) An enforcement action to impose a civil penalty will not itself 
revoke, modify, or suspend any license under this part.

[43 FR 21641, May 19, 1978, as amended at 62 FR 27495, May 20, 1997]

[[Page 722]]



Sec. 110.65  Settlement and compromise.

    At any time after issuance of an order for any enforcement action 
under this subpart, an agreement may be entered into for settlement of 
the proceeding or compromise of a penalty. Upon approval by the 
Commission, or presiding officer if a hearing has been requested, the 
terms of the settlement or compromise will be embodied in the order 
disposing of the enforcement action.



Sec. 110.66  Enforcement hearing.

    (a) If the licensee demands a hearing, the Commission will issue an 
order specifying the time and place.
    (b) A hearing pursuant to this subpart will be conducted under the 
procedures in subpart G of part 2 of this chapter.

[43 FR 21641, May 19, 1978, as amended at 75 FR 44093, July 28, 2010]



Sec. 110.67  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act provides for criminal 
sanctions for willful violation of, attempted violation of, or 
conspiracy to violate, any regulation issued under sections 161b., 
161i., or 161o. of the Atomic Energy Act. For purposes of section 223, 
all the regulations in 10 CFR part 110 are issued under one or more of 
sections 161b, 161i, or 161o, except for the sections listed in 
paragraph (b) of this section.
    (b) The regulations in part 110 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 110.1, 110.2, 110.3, 110.4, 110.7, 110.10, 110.11, 110.30, 
110.31, 110.32, 110.40, 110.41, 110.42, 110.43, 110.44, 110.45, 110.46, 
110.51, 110.52, 110.60, 110.61, 110.62, 110.63, 110.64, 110.65, 110.66, 
110.67, 110.70, 110.71, 110.72, 110.73, 110.80, 110.81, 110.82, 110.83, 
110.84, 110.85, 110.86, 110.87, 110.88, 110.89, 110.90, 110.91, 110.100, 
110.101, 110.102, 110.103, 110.104, 110.105, 110.106, 110.107, 110.108, 
110.109, 110.110, 110.111, 110.112, 110.113, 110.120, 110.122, 110.124, 
110.130, 110.131, 110.132, 110.133, 110.134, and 110.135.

[57 FR 55080, Nov. 24, 1992; 57 FR 62605, Dec. 31, 1992, as amended at 
60 FR 37565, July 21, 1995; 75 FR 44093, July 28, 2010]



 Subpart G_Public Notification and Availability of Documents and Records



Sec. 110.70  Public notice of receipt of an application.

    (a) The Commission will notice the receipt of each license 
application, including applications for amendment or renewal, for an 
export or import for which a specific license is required by making a 
copy available at the NRC Web site, http://www.nrc.gov.
    (b) The Commission will also publish in the Federal Register a 
notice of receipt of each license application, including applications 
for amendment or renewal, to export the following:
    (1) A production or utilization facility.
    (2) Five effective kilograms or more of plutonium, high-enriched 
uranium or uranium-233.
    (3) 10,000 kilograms or more of heavy water. (Note: Does not apply 
to exports of heavy water to Canada.)
    (4) Nuclear grade graphite for nuclear end use.
    (5) Radioactive waste.
    (c) The Commission will also publish in the Federal Register a 
notice of receipt of a license application, including applications for 
amendment or renewal, for an import of radioactive waste for which a 
specific license is required.

[75 FR 44093, July 28, 2010]



Sec. 110.71  Notice of withdrawal of an application.

    The Commission will notice the withdrawal of an application by 
making a copy available at the NRC Web site, http://www.nrc.gov.

[64 FR 48955, Sept. 9, 1999]



Sec. 110.72  Public availability of documents.

    Unless exempt from disclosure under part 9 of this chapter, the 
following documents pertaining to each license and license application 
for an import or export requiring a specific license under this part 
will be made available at the NRC Web site, http://www.nrc.gov, and/or 
at the NRC Public Document Room:

[[Page 723]]

    (a) The license application and any requests for amendments;
    (b) Commission correspondence with the applicant or licensee;
    (c) Federal Register notices;
    (d) The Commission letter requesting Executive Branch views;
    (e) Correspondence from the State Department with Executive Branch 
views;
    (f) Correspondence from foreign governments and international 
organizations;
    (g) Filings pursuant to subpart I and Commission and Executive 
Branch responses, if any;
    (h) If a hearing is held, the hearing record and decision;
    (i) A statement of staff conclusions; and
    (j) The license, requests for license amendments and amendments.

[43 FR 21641, May 19, 1978, as amended at 60 FR 37565, July 21, 1995; 64 
FR 48955, Sept. 9, 1999]



Sec. 110.73  Availability of NRC records.

    (a) Commission records under this part will be made available to the 
public only in accordance with part 9 of this chapter.
    (b) Proprietary information provided under this part may be 
protected under Part 9 and Sec. 2.390(b), (c), and (d) of this chapter.

[43 FR 21641, May 19, 1978, as amended at 69 FR 2281, Jan. 14, 2004]



      Subpart H_Public Participation Procedures Concerning License 
                              Applications



Sec. 110.80  Basis for hearings.

    The procedures in this part will constitute the exclusive basis for 
hearings on export and import license applications.

[75 FR 44093, July 28, 2010]



Sec. 110.81  Written comments.

    (a) The Commission encourages written comments from the public 
regarding export and import license applications. The Commission will 
consider and, if appropriate, respond to these comments.
    (b) These comments should be submitted within 30 days after public 
notice of receipt of the application on the NRC Web site or in the 
Federal Register and addressed to the Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attention: Rulemakings and 
Adjudications Staff.
    (c) The Commission will provide the applicant with a copy of the 
comments and, if appropriate, a reasonable opportunity for response.

[43 FR 21641, May 19, 1978, as amended at 62 FR 27495, May 20, 1997; 75 
FR 44093, July 28, 2010]



Sec. 110.82  Hearing request or intervention petition.

    (a) A person may request a hearing or petition for leave to 
intervene on a license application for an import or export requiring a 
specific license.
    (b) Hearing requests and intervention petitions must:
    (1) State the name, address and telephone number of the requestor or 
petitioner;
    (2) Set forth the issues sought to be raised;
    (3) Explain why a hearing or an intervention would be in the public 
interest and how a hearing or intervention would assist the Commission 
in making the determinations required by Sec. 110.45.
    (4) Specify, when a person asserts that his interest may be 
affected, both the facts pertaining to his interest and how it may be 
affected, with particular reference to the factors in Sec. 110.84.
    (c) Hearing requests and intervention petitions will be considered 
timely only if filed not later than:
    (1) 30 days after notice of receipt in the Federal Register, for 
those applications published in the Federal Register;
    (2) 30 days after publication of notice on the NRC Web site at 
http://www.nrc.gov;
    (3) 30 days after notice of receipt in the Public Document Room; or
    (4) Such other time as may be provided by the Commission.

[43 FR 21641, May 19, 1978, as amended at 49 FR 47202, Dec. 3, 1984; 60 
FR 37565, July 21, 1995; 60 FR 55183, Oct. 30, 1995; 65 FR 70291, Nov. 
22, 2000; 75 FR 44093, July 28, 2010]

[[Page 724]]



Sec. 110.83  Answers and replies.

    (a) Unless otherwise specified by the Commission, an answer to a 
hearing request or intervention petition may be filed within 30 days 
after the request or petition has been served.
    (b) Unless otherwise specified by the Commission, a reply to an 
answer may be filed within 10 days after all timely answers have been 
filed.
    (c) Answers and replies should address the factors in Sec. 110.84.

[43 FR 21641, May 19, 1978, as amended at 49 FR 47203, Dec. 3, 1984]



Sec. 110.84  Commission action on a hearing request or intervention
petition.

    (a) In an export licensing proceeding, or in an import licensing 
proceeding in which a hearing request or intervention petition does not 
assert or establish an interest which may be affected, the Commission 
will consider:
    (1) Whether a hearing would be in the public interest; and
    (2) Whether a hearing would assist the Commission in making the 
statutory determinations required by the Atomic Energy Act.
    (b) If a hearing request or intervention petition asserts an 
interest which may be affected, the Commission will consider:
    (1) The nature of the alleged interest;
    (2) How that interest relates to issuance or denial; and
    (3) The possible effect of any order on that interest, including 
whether the relief requested is within the Commission's authority, and, 
if so, whether granting relief would redress the alleged injury.
    (c) Untimely hearing requests or intervention petitions may be 
denied unless good cause for failure to file on time is established. In 
reviewing untimely requests or petitions, the Commission will also 
consider:
    (1) The availability of other means by which the requestor's or 
petitioner's interest, if any, will be protected or represented by other 
participants in a hearing; and
    (2) The extent to which the issues will be broadened or action on 
the application delayed.
    (d) Before granting or denying a hearing request or intervention 
petition, the Commission will review the Executive Branch's views on the 
license application and may request further information from the 
petitioner, requester, the Commission staff, the Executive Branch or 
others.
    (e) The Commission will deny a request or petition that pertains 
solely to matters outside its jurisdiction.
    (f) If an issue has been adequately explored in a previous licensing 
hearing conducted pursuant to this part, a request for a new hearing in 
connection with that issue will be denied unless:
    (1) A hearing request or intervention petition establishes that an 
interest may be affected; or
    (2) The Commission determines that changed circumstances or new 
information warrant a new hearing.
    (g) After consideration of the factors covered by paragraphs (a) 
through (f), the Commission will issue a notice or order granting or 
denying a hearing request or intervention petition. Upon the affirmative 
vote of two Commissioners a hearing will be ordered. A notice granting a 
hearing will be published in the Federal Register and will specify 
whether the hearing will be oral or consist of written comments. A 
denial notice will set forth the reasons for denial.

[43 FR 21641, May 19, 1978, as amended at 49 FR 47203, Dec. 3, 1984]



Sec. 110.85  Notice of hearing consisting of written comments.

    (a) A notice of hearing consisting of written comments will:
    (1) State the issues to be considered;
    (2) Provide the names and addresses of participants;
    (3) Specify the time limits for participants and others to submit 
written views and respond to any written comments; and
    (4) State any other instructions the Commission deems appropriate.
    (b) The Secretary will give notice of any hearing under this section 
and Sec. 110.86 to any person who so requests.



Sec. 110.86  Notice of oral hearing.

    (a) A notice of oral hearing will:
    (1) State the time, place and issues to be considered;
    (2) Provide names and addresses of participants;
    (3) Designate the presiding officer;

[[Page 725]]

    (4) Specify the time limit for participants and others to indicate 
whether they wish to present views; and
    (5) State any other instructions the Commission deems appropriate.
    (b) If the Commission is not the presiding officer, the notice of 
oral hearing will also state:
    (1) When the jurisdiction of the presiding officer commences and 
terminates;
    (2) The powers of the presiding officer; and
    (3) Instructions to the presiding officer to certify promptly the 
completed hearing record to the Commission without preliminary decision 
or findings, unless the Commission directs otherwise.



Sec. 110.87  Conditions in a notice or order.

    (a) A notice or order granting a hearing or permitting intervention 
may restrict irrelevant or duplicative testimony, or require common 
interests to be represented by a single spokesman.
    (b) If a participant's interests do not extend to all the issues in 
the hearing, the notice or order may limit his participation 
accordingly.
    (c) Unless authorized by the Commission, the granting of 
participation will not broaden the hearing issues.



Sec. 110.88  Authority of the Secretary.

    The Secretary is authorized to prescribe time schedules and other 
procedural arrangements, when not covered by this part, and rule on 
related procedural requests.



Sec. 110.89  Filing and service.

    (a) Hearing requests, intervention petitions, answers, replies and 
accompanying documents must be filed with the Commission by delivery or 
by mail to the Secretary, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, Attention: Rulemakings and Adjudications 
Staff or via the E-Filing system, following the procedure set forth in 
10 CFR 2.302. Filing by mail is complete upon deposit in the mail. 
Filing via the E-Filing system is completed by following the 
requirements described in 10 CFR 2.302(d).
    (b) All filing and Commission notices and orders must be served upon 
the applicant; the General Counsel, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555; the Executive Secretary, Department of State, 
Washington, DC 20520; and participants if any. Hearing requests, 
intervention petitions, and answers and replies must be served by the 
person filing those pleadings.
    (c) Service is completed by:
    (1) Delivering the paper to the person; or leaving it in his office 
with someone in charge; or, if there is no one in charge, leaving it in 
a conspicuous place in the office; or, if he has no office or it is 
closed, leaving it at his usual place of residence with some occupant of 
suitable age and discretion;
    (2) Following the requirements for E-Filing in 10 CFR 2.305;
    (3) Depositing it in the United States mail, express mail, or 
expedited delivery service, properly stamped and addressed; or
    (4) Any other manner authorized by law, when service cannot be made 
as provided in paragraphs (c)(1) through (3) of this section.
    (d) Proof of service, stating the name and address of the person 
served and the manner and date of service, shall be shown, and may be 
made by:
    (1) Written acknowledgment of the person served or an authorized 
representative;
    (2) The certificate or affidavit of the person making the service; 
or
    (3) Following the requirements for E-Filing in 10 CFR 2.305.
    (e) The Commission may make special provisions for service when 
circumstances warrant.

[72 FR 49154, Aug. 28, 2007]



Sec. 110.90  Computation of time.

    (a) In computing any period of time, the day of the act, event, or 
default after which the designated period of time begins to run is not 
included. The last day of the period so computed is included unless it 
is a Saturday or Sunday, a Federal legal holiday at the place where the 
action or event is to occur, or a day upon which, because of an 
emergency closure of the Federal government in Washington, DC, NRC 
Headquarters does not open for business, in which event the period runs

[[Page 726]]

until the end of the next day that is not a Saturday, Sunday, holiday, 
or emergency closure.
    (b) In time periods of less than seven (7) days, intermediate 
Saturdays, Sundays, Federal legal holidays, and emergency closures are 
not counted.
    (c) Whenever an action is required within a prescribed period by a 
document served under Sec. 110.89 of this part, no additional time is 
added to the prescribed period except as set forth in 10 CFR 2.306(b).
    (d) To be considered timely, a document must be served:
    (1) By 5 p.m. Eastern Time for a document served in person or by 
expedited service; and
    (2) By 11:59 p.m. Eastern Time for a document served by the E-Filing 
system.

[72 FR 49154, Aug. 28, 2007]



Sec. 110.91  Commission consultations.

    The Commission may consult at any time on a license application with 
the staff, the Executive Branch or other persons.

[49 FR 47203, Dec. 3, 1984]



                           Subpart I_Hearings



Sec. 110.100  Public hearings.

    Hearings under this part will be public unless the Commission 
directs otherwise.



Sec. 110.101  Filing and service.

    Filing and service of hearing documents shall be pursuant to Sec. 
110.89.



Sec. 110.102  Hearing docket.

    For each hearing, the Secretary will maintain a docket which will 
include the hearing transcript, exhibits and all papers filed or issued 
pursuant to the hearing.



Sec. 110.103  Acceptance of hearing documents.

    (a) Each document filed or issued must be clearly legible and bear 
the docket number, license application number, and hearing title.
    (b) Each document shall be filed in one original and signed by the 
participant or their authorized representative, with their address and 
date of signature indicated. The signature is a representation that the 
document is submitted with full authority, the signer knows its 
contents, and that, to the best of his knowledge, the statements made in 
it are true.
    (c) Filings submitted using the E-filing system must follow the 
requirements outlined in 10 CFR 2.304.
    (d) A document not meeting the requirements of this section may be 
returned with an explanation for nonacceptance and, if so, will not be 
docketed.

[72 FR 49154, Aug. 28, 2007]



Sec. 110.104  Presiding officer.

    (a) The full Commission will ordinarily be the presiding officer at 
a hearing under this part. However, the Commission may provide in a 
hearing notice that one or more Commissioners, or any other person as 
provided by law, will preside.
    (b) A participant may submit a written motion for the 
disqualification of any person presiding. The motion shall be supported 
by affidavit setting forth the alleged grounds for disqualification. If 
the presiding officer does not grant the motion or the person does not 
disqualify himself, the Commission will decide the matter.
    (c) If any presiding officer designated by the Commission deems 
himself disqualified, he shall withdraw by notice on the record after 
notifying the Commission.
    (d) If a presiding officer becomes unavailable, the Commission will 
designate a replacement.
    (e) Any motion concerning the designation of a replacement presiding 
officer shall be made within 5 days after the designation.
    (f) Unless otherwise ordered by the Commission, the jurisdiction of 
a presiding officer other than the Commission commences as designated in 
the hearing notice and terminates upon certification of the hearing 
record to the Commission, or when the presiding officer is disqualified.



Sec. 110.105  Responsibility and power of the presiding officer in an 
oral hearing.

    (a) The presiding officer in any oral hearing shall conduct a fair 
hearing,

[[Page 727]]

develop a record that will contribute to informed decisionmaking, and, 
within the framework of the Commission's orders, have the power 
necessary to achieve these ends, including the power to:
    (1) Take action to avoid unnecessary delay and maintain order;
    (2) Dispose of procedural requests;
    (3) Question participants and witnesses, and entertain suggestions 
as to questions which may be asked of participants and witnessess;
    (4) Order consolidation of participants;
    (5) Establish the order of presentation;
    (6) Hold conferences before or during the hearing;
    (7) Establish reasonable time limits;
    (8) Limit the number of witnesses; and
    (9) Strike or reject duplicative or irrelevant presentations.
    (b) Where the Commission itself does not preside:
    (1) The presiding officer may certify questions or refer rulings to 
the Commission for decision;
    (2) Any hearing order may be modified by the Commission; and
    (3) The presiding officer will certify the completed hearing record 
to the Commission, which may then issue its opinion on the hearing or 
provide that additional testimony be presented.



Sec. 110.106  Participation in a hearing.

    (a) Unless otherwise limited by this part or by the Commission, 
participants in a hearing may submit:
    (1) Initial and concluding written statements of position on the 
issues;
    (2) Written questions to the presiding officer; and
    (3) Written responses and rebuttal testimony to the statements of 
other participants.
    (b) Participants in an oral hearing may also submit oral statements, 
questions, responses and rebuttal testimony.
    (c) A participant in an import licensing hearing establishing that 
his interest may be affected, may be accorded additional procedural 
rights under subpart G of part 2 with respect to resolution of domestic 
factual issues regarding the public health, safety and environment of 
the United States, and the protection of the United States public 
against domestic theft, diversion or sabotage, to the extent that such 
issues are separable from the nondomestic issues associated with the 
license application.



Sec. 110.107  Presentation of testimony in an oral hearing.

    (a) All direct testimony in an oral hearing shall be filed no later 
than 7 days before the hearing or as otherwise ordered or allowed.
    (b) Written testimony will be received into evidence in exhibit 
form.
    (c) Unless proscribed under Sec. 110.87, members of groups which 
are designated as participants may testify in their individual 
capacities.
    (d) Participants may present their own witnesses.
    (e) Testimony by the Commission and the Executive Branch will be 
presented only by persons officially designated for that purpose.
    (f) Participants and witnesses will be questioned orally or in 
writing and only by the presiding officer. Questions may be addressed to 
individuals or to panels of participants or witnesses.
    (g) The presiding officer may accept written testimony from a person 
unable to appear at the hearing, and may request him to respond to 
questions.
    (h) No subpoenas will be granted at the request of participants for 
attendance and testimony of participants or witnesses or the production 
of evidence.



Sec. 110.108  Appearance in an oral hearing.

    (a) A participant may appear in a hearing on his own behalf or be 
represented by an authorized representative.
    (b) A person appearing shall file a written notice stating his name, 
address and telephone number, and if an authorized representative, the 
basis of his eligibility and the name and address of the participant on 
whose behalf he appears.
    (c) A person may be excluded from a hearing for disorderly, dilatory 
or contemptuous conduct, provided he is informed of the grounds and 
given an opportunity to respond.

[[Page 728]]



Sec. 110.109  Motions and requests.

    (a) Motions and requests shall be addressed to the presiding 
officer, and, if written, also filed with the Secretary and served on 
other participants.
    (b) Other participants may respond to the motion or request. 
Responses to written motions or requests shall be filed within 5 days 
after service.
    (c) When the Commission does not preside, in response to a motion or 
request, the presiding officer may refer a ruling or certify a question 
to the Commission for decision and notify the participants.
    (d) Unless otherwise ordered by the Commission, a motion or request, 
or the certification of a question or referral of a ruling, shall not 
stay or extend any aspect of the hearing.



Sec. 110.110  Default.

    When a participant fails to act within a specified time, the 
presiding officer may consider him in default, issue an appropriate 
ruling and proceed without further notice to the defaulting participant.



Sec. 110.111  Waiver of a rule or regulation.

    (a) A participant may petition that a Commission rule or regulation 
be waived with respect to the license application under consideration.
    (b) The sole ground for a waiver shall be that, because of special 
circumstances concerning the subject of the hearing, application of a 
rule or regulation would not serve the purposes for which it was 
adopted.
    (c) Waiver petition shall specify why application of the rule or 
regulation would not serve the purposes for which it was adopted.
    (d) Other participants may, within 10 days, file a response to a 
waiver petition.
    (e) When the Commission does not preside, the presiding officer will 
certify the waiver petition to the Commission, which, in response, will 
grant or deny the waiver or direct any further proceedings.
    (f) Regardless of whether a waiver is granted or denied, a separate 
petition for rulemaking may be filed pursuant to subpart K of this part.

[43 FR 21641, May 19, 1978, as amended at 62 FR 59277, Nov. 3, 1997]



Sec. 110.112  Reporter and transcript for an oral hearing.

    (a) A reporter designated by the Commission will record an oral 
hearing and prepare the official hearing transcript.
    (b) Except for any portions containing classified information, 
Restricted Data, Safeguards Information, proprietary information, or 
other sensitive unclassified information, transcripts will be made 
available at the NRC Web site, http://www.nrc.gov, and/or at the NRC 
Public Document Room.
    (c) Corrections of the official transcript may be made only as 
specified by the Secretary.

[43 FR 21641, May 19, 1978, as amended at 64 FR 48955, Sept. 9, 1999; 75 
FR 44093, July 28, 2010]



Sec. 110.113  Commission action.

    (a) Upon completion of a hearing, the Commission will issue a 
written opinion including its decision on the license application, the 
reasons for the decision and any dissenting views.
    (b) While the Commission will consider fully the hearing record, the 
licensing decision will be based on all relevant information, including 
information which might go beyond that in the hearing record.
    (c) If the Commission considers information not in the hearing 
record in reaching its licensing decision, the hearing participants will 
be informed and, if not classified or otherwise privileged, the 
information will be made available at the NRC Web site, http://
www.nrc.gov, and furnished to the participants.
    (d) The Commission may issue a license before completion of a 
hearing if it finds that:
    (1) Prompt issuance is required in the public interest, particularly 
the common defense and security; and
    (2) A participant establishing that his interest may be affected has 
been provided a fair opportunity to present his views.
    (e) The Commission may:
    (1) Defer any hearing;

[[Page 729]]

    (2) Consolidate applications for hearing;
    (3) Narrow or broaden the hearing issues; and
    (4) Take other action, as appropriate.

[43 FR 21641, May 19, 1978, as amended at 64 FR 48955, Sept. 9, 1999]



   Subpart J_Special Procedures for Classified Information in Hearings



Sec. 110.120  Purpose and scope.

    (a) This subpart contains special procedures concerning access to, 
and introduction of, classified information into hearings under this 
part.
    (b) These procedures do not in any way apply to classified 
information exchanged between the Executive Branch and the Commission 
not introduced into a hearing. Such information will be declassified to 
the maximum extent feasible. The public statements of the Commission 
staff and Executive Branch will, to the extent consistent with 
classification requirements, reflect consideration of any such 
classified information.



Sec. 110.121  Security clearances and access to classified information.

    (a) No person without a security clearance will have access to 
classified information.
    (b) Only the Commission will act upon an application for access to 
classified information.
    (c) To the extent practicable, applications for access to classified 
information shall describe the information to which access is desired 
and its level of classification (confidential, secret or other); the 
reasons for requesting access; the names of individuals for whom access 
is requested; and the reasons why access is requested for those 
individuals.
    (d) The Commission will consider requests for appropriate security 
clearances in reasonable numbers; conduct its review and grant or deny 
these in accordance with part 10 of this chapter; and make a reasonable 
charge to cover costs.
    (e) The Commission will not grant security clearances for access to 
classified information, unless it determines that the available 
unclassified information is inadequate on the subject matter involved.
    (f) When an application demonstrates that access to classified 
information not introduced into a hearing may be needed to prepare a 
participant's position on the hearing issues, the Commission may issue 
an order granting access to this information to the participant, his 
authorized representative or other persons. Access will be subject to 
the conditions in paragraphs (e) and (j) and will not be granted unless 
required security clearances have been obtained.
    (g) Once classified information has been introduced into a hearing, 
the Commission will grant access to a participant, his authorized 
representative or such other persons as the Commission determines may be 
needed by the participant to prepare his position on the hearing issues. 
Access will be subject to the conditions in paragraphs (e) and (j) of 
this section and will not be granted unless required security clearances 
have been obtained.
    (h) For good cause, the Commission may postpone action upon an 
application for access to classified information.
    (i) The Commission will grant access to classified information only 
up to the level for which the persons described in paragraphs (f) and 
(g) of this section are cleared and only upon an adequate commitment by 
them not to disclose such information subject to penalties as provided 
by law.
    (j) The Commission will not in any circumstances grant access to 
classified information:
    (1) Unless it determines that the grant is not inimical to the 
common defense and security; and
    (2) Which it has received from another Government agency, without 
the prior consent of the originating agency.
    (k) Upon completion of a hearing, the Commission will terminate all 
security clearances granted pursuant to the hearing and may require the 
disposal of classified information to which access has been granted or 
the observance of other procedures to safeguard this information.

[[Page 730]]



Sec. 110.122  Classification assistance.

    On the request of any hearing participant or the presiding officer 
(if other than the Commission), the Commission will designate a 
representative to advise and assist the presiding officer or the 
participants with respect to security classification of information and 
the protective requirements to be observed.



Sec. 110.123  Notice of intent to introduce classified information.

    (a) A participant shall seek the required security clearances, where 
necessary, and file with the Secretary a notice of intent to introduce 
classified information into a hearing at the earliest possible time 
after the notice of hearing.
    (b) If a participant has not filed a notice of intent in accordance 
with this section, he may introduce classified information only if he 
gives to the other participants and the Commission prompt written notice 
of intent and only as permitted by the Commission when it determines 
that the public interest will not be prejudiced.
    (c) The notice of intent shall be unclassified and, to the extent 
consistent with classification requirements, state:
    (1) The subject matter of the classified information, which it is 
anticipated will be involved;
    (2) The highest level of classification of the information 
(confidential, secret or other);
    (3) When it is anticipated that the information would be introduced; 
and
    (4) The relevance and materiality of the information to the hearing 
issues.



Sec. 110.124  Rearrangement or suspension of a hearing.

    When a participant gives notice of intent to introduce classified 
information and other participants do not have the required security 
clearances, subject to Sec. 110.121, the Commission may:
    (a) Suspend or rearrange the normal order of the hearing to give 
other participants an opportunity to obtain the required security 
clearances with minimum delay in the conduct of the hearing; or
    (b) Take such other action as it determines to be in the public 
interest.



Sec. 110.125  Unclassified statements required.

    (a) It is the obligation of hearing participants to introduce 
information in unclassified form wherever possible, and to declassify, 
to the maximum extent feasible, any classified information introduced 
into the hearing. This obligation rests on each participant whether or 
not any other participant has the required security clearances.
    (b) When classified information is offered for introduction into a 
hearing:
    (1) The participant offering it shall, to the extent consistent with 
classification requirements, submit to the presiding officer and other 
participants an unclassified statement describing the substance of the 
classified information as accurately and completely as possible;
    (2) In accordance with procedures agreed upon by the participants or 
prescribed by the presiding officer, and after notice to all 
participants and opportunity to be heard on the notice, the presiding 
officer will determine whether an unclassified statement may be 
substituted for the classified information in the hearing record without 
prejudice to the interest of any participant or the public;
    (3) If the Commission determines that the unclassified statement 
(together with such unclassified modifications as it finds are necessary 
or appropriate to protect the interest of other participants and the 
public) adequately sets forth information in the classified matter which 
is relevant and material to the issues in the hearing, it will direct 
that the classified matter be excluded from the record of the hearing; 
and
    (4) The Commission may postpone any of the procedures in this 
section until all other evidence has been received. However, a 
participant shall not postpone service of any unclassified statement 
required in this section.



Sec. 110.126  Protection of classified information.

    Nothing in this subpart shall relieve any person from safeguarding 
classified information as required by law and rules, regulations or 
orders of any Government agency.

[[Page 731]]



                          Subpart K_Rulemaking



Sec. 110.130  Initiation of rulemaking.

    The Commission may initiate action to amend the regulations in this 
part on its own initiative or in response to a petition.



Sec. 110.131  Petition for rulemaking.

    (a) A petition for rulemaking should be addressed to the Secretary 
of the Commission, for the attention of the Secretary's Rulemakings and 
Adjudications Staff. The petition should be sent using an appropriate 
method listed in Sec. 110.4.
    (b) The petition shall state the basis for the requested amendment.
    (c) The petition may request the Commission to suspend all or part 
of any licensing proceeding under this part pending disposition of the 
petition.
    (d) The Secretary will assign a docket number to the petition, place 
a copy in the Public Document Room and notice its receipt in the Federal 
Register.
    (e) Publication may be limited by order of the Commission to the 
extent required by section 181 of the Atomic Energy Act.

[43 FR 21641, May 19, 1978, as amended at 63 FR 15744, Apr. 1, 1998; 68 
FR 58824, Oct. 10, 2003]



Sec. 110.132  Commission action on a petition.

    (a) The Commission may grant or deny the petition in whole or in 
part.
    (b) If the petition is granted, a notice of proposed rulemaking or a 
notice of rulemaking will be published in the Federal Register.
    (c) If the petition is denied, the petitioner will be informed of 
the grounds.
    (d) Commission action on a petition will normally follow, whenever 
appropriate, receipt and evaluation of Executive Branch views.
    (e) The Commission, in exercising the discretion authorized by 
section 4(a)(1) of the Administrative Procedure Act (5 U.S.C. 
553(a)(1)), will decide what, if any, public rulemaking procedures will 
be followed.



Sec. 110.133  Notice of proposed rulemaking.

    (a) When the Commission proposes to amend the regulations in this 
part, it will normally publish a notice of proposed rulemaking in the 
Federal Register.
    (b) A notice of proposed rulemaking will include:
    (1) The authority for the proposed rule;
    (2) The substance and purpose of the proposed rule;
    (3) Directions for public participation;
    (4) The time and place of any public hearing; and
    (5) If a hearing is to be held by other than the Commission, 
designating of a presiding officer and instructions for the conduct of 
the hearing.
    (c) A notice of proposed rulemaking will be published not less than 
15 days before any hearing, unless the Commission for good cause 
provides otherwise in the notice.



Sec. 110.134  Public participation.

    (a) The Commission may hold an oral hearing on a proposed rule or 
permit any person to participate in a rulemaking proceeding through the 
submission of written comments.
    (b) When it is in the public interest and is authorized by law, 
public rule-making procedures may be omitted and a notice of rulemaking 
published pursuant to Sec. 110.135.



Sec. 110.135  Notice of rulemaking.

    (a) Upon approval of an amendment, the Commission will publish in 
the Federal Register a notice of rule-making which includes a statement 
of its basis and purpose, effective date and, where appropriate, any 
significant variations from the amendment as proposed in any notice of 
proposed rulemaking.
    (b) The effective date of an amendment will normally be no earlier 
than 30 days after publication of the notice of rulemaking, unless the 
Commission for good cause provides otherwise in the notice.

[[Page 732]]



   Sec. Appendix A to Part 110--Illustrative List of Nuclear Reactor 
             Equipment Under NRC Export Licensing Authority

    Note: A nuclear reactor basically includes the items within or 
attached directly to the reactor vessel, the equipment which controls 
the level of power in the core, and the components which normally 
contain or come in direct contact with or control the primary coolant of 
the reactor core.

    (1) Reactor pressure vessels, i.e., metal vessels, as complete units 
or major shop-fabricated parts, especially designed or prepared to 
contain the core of a nuclear reactor and capable of withstanding the 
operating pressure of the primary coolant.
    (2) On-line (e.g., CANDU) reactor fuel charging and discharging 
machines, i.e., manipulative equipment especially designed for inserting 
or removing fuel in an operating nuclear reactor.
    (3) Complete reactor control rod system, i.e., rods especially 
designed or prepared for the control of the reaction rate in a nuclear 
reactor, including the neutron absorbing part and the support or 
suspension structures therefor.
    (4) Reactor primary coolant pumps or circulators, i.e., pumps or 
circulators especially designed or prepared for circulating the primary 
coolant in a nuclear reactor.
    (5) Reactor pressure tubes, i.e., tubes especially designed or 
prepared to contain both fuel elements and the primary coolant in a 
nuclear reactor.
    (6) Zirconium tubes, i.e., zirconium metal and alloys in the form of 
tubes or assemblies of tubes especially designed or prepared for use as 
fuel cladding in a nuclear reactor.
    (7) Reactor internals, e.g., core support structures, control and 
rod guide tubes, fuel channels, calandria tubes, thermal shields, 
baffles, core grid plates, and diffuser plates especially designed or 
prepared for use in a nuclear reactor.
    (8) Reactor control rod drive mechanisms, including detection and 
measuring equipment to determine neutron flux levels within the core of 
a nuclear reactor.
    (9) Heat exchangers, e.g., steam generators especially designed or 
prepared for the primary, or intermediate, coolant circuit of a nuclear 
reactor or heat exchangers especially designed or prepared for use in 
the primary coolant circuit of a nuclear reactor.
    (10) External thermal shields especially designed or prepared for 
use in a nuclear reactor for reduction of heat loss and also for 
containment vessel protection.
    (11) Any other components especially designed or prepared for use in 
a nuclear reactor or in any of the components described in this 
appendix.

[79 FR 39291, July 10, 2014]



    Sec. Appendix B to Part 110--Illustrative List of Gas Centrifuge 
   Enrichment Plant Components Under NRC's Export Licensing Authority

    1. Assemblies and components especially designed or prepared for use 
in gas centrifuges.
    Note: The gas centrifuge normally consists of a thin-walled 
cylinder(s) of between 75 mm and 650 mm diameter contained in a vacuum 
environment and spun at high peripheral speed (of the order of 300 m/per 
second and more) with the central axis vertical. In order to achieve 
high speed, the materials of construction for the rotating rotor 
assembly, and hence its individual components, have to be manufactured 
to very close tolerances in order to minimize the unbalance. In contrast 
to other centrifuges, the gas centrifuge for uranium enrichment is 
characterized by having within the rotor chamber a rotating disc-shaped 
baffle(s) and a stationary tube arrangement for feeding and extracting 
uranium hexafluoride (UF6) gas and featuring at least three 
separate channels of which two are connected to scoops extending from 
the rotor axis towards the periphery of the rotor chamber. Also 
contained within the vacuum environment are a number of critical items 
which do not rotate and which, although they are especially designed, 
are not difficult to fabricate nor are they fabricated out of unique 
materials. A centrifuge facility, however, requires a large number of 
these components so that quantities can provide an important indication 
of end use.

                         1.1 Rotating Components

    (a) Complete Rotor Assemblies: Thin-walled cylinders, or a number of 
interconnected thin-walled cylinders, manufactured from one of the high 
strength-to-density ratio materials described in the footnote to this 
section.
    If interconnected, the cylinders are joined together by flexible 
bellows or rings as described in Sec. 1.1(c) of this appendix. The 
rotor is fitted with an internal baffle(s) and end caps, as described in 
Sec. 1.1(d) and (e) of this appendix, if in final form. However, the 
complete assembly may be delivered only partly assembled.
    (b) Rotor Tubes: Especially designed or prepared thin-walled 
cylinders with thickness of 12 mm or less, a diameter of between 75 mm 
and 650 mm, and manufactured from one of the high strength-to-density 
ratio materials described in the footnote to this section.
    (c) Rings or Bellows: Components especially designed or prepared to 
give localized support to the rotor tube or to join together a number of 
rotor tubes. The bellows in a short cylinder of wall thickness 3 mm or 
less, a diameter of between 75 mm and 650

[[Page 733]]

mm, having a convolute, and manufactured from one of the high strength-
to-density ratio materials described in the footnote to this section.
    (d) Baffles: Disc shaped components of between 75 mm and 650 mm 
diameter especially designed or prepared to be mounted inside the 
centrifuge rotor tube, in order to isolate the take-off chamber from the 
main separation chamber and, in some cases, to assist the UF6 
gas circulation within the main separation chamber of the rotor tube, 
and manufactured from one of the high strength-to-density ratio 
materials described in the footnote to this section.
    (e) Top Caps/Bottom Caps: Disc shaped components of between 75 mm 
and 650 mm diameter especially designed or prepared to fit to the ends 
of the rotor tube, and so contain the UF6 within the rotor 
tube, and in some cases to support, retain or contain as an integrated 
part, an element of the upper bearing (top cap) or to carry the rotating 
elements of the motor and lower bearing (bottom cap), and manufactured 
from one of the high strength-to-density ratio materials described in 
the footnote to this section.

                                Footnote

    The materials used for centrifuge rotating components include the 
following:
    (a) Maraging steel capable of an ultimate tensile strength of 1.95 
GPa or more.
    (b) Aluminum alloys capable of an ultimate tensile strength of 0.46 
GPa or more.
    (c) Filamentary materials suitable for use in composite structures 
and having a specific modulus of 3.18 x 10\6\ m or greater and a 
specific ultimate tensile strength of 7.62 x 10\4\ m or greater.

(``Specific Modulus'' is the Young's modulus in N/m\2\ divided by the 
specific weight inN/m\3\ when measured at a temperature of 23 20 [deg]C and a relative humidity of 50 5 percent. ``Specific tensile strength'' is the ultimate 
tensile strength in N/m\2\ divided by the specific weight in N/m\3\ when 
measured at a temperature of 23 20 [deg]C and a 
relative humidity of 50 5 percent.)

                          1.2 Static Components

    (a) Magnetic Suspension Bearings: 1. Especially designed or prepared 
bearing assemblies consisting of an annular magnet suspended within a 
housing containing a damping medium. The housing will be manufactured 
from a UF6 resistant material (see footnote to Sec. 2 of 
this appendix). The magnet couples with a pole piece or a second magnet 
fitted to the top cap described in Sec. 1.1(e) of this appendix. The 
magnet may be ring-shaped with a relation between outer and inner 
diameter smaller or equal to 1.6:1. The magnet may be in a form having 
an initial permeability of 0.15 Henry/meter or more, or a remanence of 
98.5 percent or more, or an energy product of greater than 80,000 
joules/m\3\. In addition to the usual material properties, it is a 
prerequisite that the deviation of the magnetic axes from the 
geometrical axes is limited to very small tolerances (lower than 0.1 mm) 
or that homogeneity of the material of the magnet is specially called 
for.
    2. Active magnetic bearings especially designed or prepared for use 
with gas centrifuges. These bearings usually have the following 
characteristics:
    (i) Designed to keep centred a rotor spinning at 600 Hz or more; and
    (ii) Associated to a reliable electrical power supply and/or to an 
uninterruptible power supply (UPS) unit in order to function for more 
than 1 hour.
    (b) Bearings/Dampers: Especially designed or prepared bearings 
comprising a pivot/cup assembly mounted on a damper. The pivot is 
normally a hardened steel shaft polished into a hemisphere at one end 
with a means of attachment to the bottom cap described in Sec. 1.1(e) 
of this appendix at the other. The shaft may, however, have a 
hydrodynamic bearing attached. The cup is pellet-shaped with 
hemispherical indentation in one surface. These components are often 
supplied separately to the damper.
    (c) Molecular Pumps: Especially designed or prepared cylinders 
having internally machined or extruded helical grooves and internally 
machined bores. Typical dimensions are as follows: 75 mm to 650 mm 
internal diameter, 10 mm or more wall thickness, with a length equal to 
or greater than the diameter. The grooves are typically rectangular in 
cross-section and 2 mm or more in depth.
    (d) Motor Stators: Especially designed or prepared ring shaped 
stators for high speed multi-phase alternating current (AC) hysteresis 
(or reluctance) motors for synchronous operation within a vacuum at a 
frequency of 600 Hz or greater and a power of 40 volts amps or greater. 
The stators may consist of multi-phase windings on a laminated low loss 
iron core comprised of thin layers typically 2.0 mm thick or less.
    (e) Centrifuge housing/recipients: Components especially designed or 
prepared to contain the rotor tube assembly of a gas centrifuge. The 
housing consists of a rigid cylinder of wall thickness up to 30 mm with 
precision machined ends to locate the bearings and with one or more 
flanges for mounting. The machined ends are parallel to each other and 
perpendicular to the cylinder's longitudinal axis to within 0.05 degrees 
or less. The housing may also be a honeycomb type structure to 
accommodate several rotor tubes.
    (f) Scoops: Especially designed or prepared tubes for the extraction 
of UF6 gas from within the rotor tube by a Pitot tube action 
(that is, with an aperture facing into the circumferential gas flow 
within the rotor tube,

[[Page 734]]

for example by bending the end of a radially disposed tube) and capable 
of being fixed to the central gas extraction system.
    2. Especially designed or prepared auxiliary systems, equipment, and 
components for gas centrifuge enrichment plants.
    Note: The auxiliary systems, equipment, and components for a gas 
centrifuge enrichment plant are the systems of the plant needed to feed 
UF6 to the centrifuges to link the individual centrifuges to 
each other to form cascades (or stages) to allow for progressively 
higher enrichments and to extract the product and tails of 
UF6 from the centrifuges, together with the equipment 
required to drive the centrifuges or to control the plant.
    Normally UF6 is evaporated from the solid using heated 
autoclaves and is distributed in gaseous form to the centrifuges by way 
of cascade header pipework. The ``product'' and ``tails'' of 
UF6 gaseous streams flowing from the centrifuges are also 
passed by way of cascade header pipework to cold traps (operating at 
about 203 K (-70 [deg]C)) where they are condensed prior to onward 
transfer into suitable containers for transportation or storage. Because 
an enrichment plant consists of many thousands of centrifuges arranged 
in cascades, there are many kilometers of cascade header pipework 
incorporating thousands of welds with a substantial amount of repetition 
of layout. The equipment, component and piping systems are fabricated to 
very high vacuum and cleanliness standards.
    Some of the items listed below either come into direct contact with 
the UF6 process gas or directly control the centrifuges and 
the passage of the gas from centrifuge to centrifuge and cascade to 
cascade. Materials resistant to corrosion by UF6 include 
copper, copper alloys, stainless steel, aluminum, aluminum oxide, 
aluminum alloys, nickel or alloys containing 60 percent or more nickel, 
and fluorinated hydrocarbon polymers.
    (a) Feed Systems/Product and Tails Withdrawal Systems: Especially 
designed or prepared process systems or equipment for enrichment plants 
made of or protected by materials resistant to corrosion by 
UF6 including:
    1. Feed autoclaves, ovens, or systems used for passing 
UF6 to the enrichment process.
    2. Desublimers, cold traps, or pumps used to remove UF6 
from the enrichment process for subsequent transfer upon heating.
    3. Solidification or liquefaction stations used to remove 
UF6 from the enrichment process by compressing and converting 
UF6 to a liquid or solid form.
    4. ``Product'' and ``tails'' stations used for transferring 
UF6 into containers.
    (b) Machine Header Piping Systems: Especially designed or prepared 
piping systems and header systems for handling UF6 within the 
centrifuge cascades.
    This piping network is normally of the ``triple'' header system with 
each centrifuge connected to each of the headers. There is therefore a 
substantial amount of repetition in its form. It is wholly made of or 
protected by UF6 resistant materials (see Note to this 
section) and is fabricated to very high vacuum and cleanliness 
standards.
    (c) Special shut-off and control valves:
    1. Shut-off valves especially designed or prepared to act on the 
feed, ``product'' or ``tails'' UF6 gaseous streams of an 
individual gas centrifuge.
    2. Bellows-sealed valves, manual or automated, shut-off or control, 
made of or protected by materials resistant to corrosion by 
UF6, with an inside diameter of 10 to 160 mm, especially 
designed or prepared for use in main or auxiliary systems of gas 
centrifuge enrichment plants.
    Typical especially designed or prepared valves include bellow-sealed 
valves, fast acting closure-types, fast acting valves, and others.
    (d) UF6 Mass Spectrometers/Ion Sources: Especially 
designed or prepared mass spectrometers capable of taking on-line 
samples from UF6 gas streams and having all of the following:
    1. Capable of measuring ions of 320 atomic mass units or greater and 
having a resolution of better than 1 part in 320.
    2. Ion sources constructed of or protected by nickel, nickel-copper 
alloys with a nickel content of 60 percent or more by weight, or nickel-
chrome alloys.
    3. Electron bombardment ionization sources.
    4. Having a collector system suitable for isotope analysis.
    (e) Frequency Changers: Frequency changers (also known as converters 
or inverters) especially designed or prepared to supply motor stators as 
defined under Sec. 1.2(d) of this appendix, or parts, components, and 
subassemblies of such frequency changers having all of the following 
characteristics:
    1. A multiphase output of 600 Hz or greater; and
    2. High stability (with frequency control better than 0.2 percent).
    (f) Any other components especially designed or prepared for use in 
a gas centrifuge enrichment plant or in any of the components described 
in this appendix.

[79 FR 39291, July 10, 2014]



  Sec. Appendix C to Part 110--Illustrative List of Gaseous Diffusion 
 Enrichment Plant Assemblies and Components Under NRC Export Licensing 
                                Authority

     In the gaseous diffusion method of uranium isotope separation, the 
main technological assembly is a special porous gaseous

[[Page 735]]

diffusion barrier, heat exchanger for cooling the gas (which is heated 
by the process of compression), seal valves and control valves, and 
pipelines. Inasmuch as gaseous diffusion technology uses uranium 
hexafluoride (UF6), all equipment, pipeline and 
instrumentation surfaces (that come in contact with the gas) must be 
made of materials that remain stable in contact with UF6. A 
gaseous diffusion facility requires a number of these assemblies, so 
that quantities can provide an important indication of end use.

    The auxiliary systems, equipment, and components for gaseous 
diffusion enrichment plants are the systems of plant needed to feed 
UF6 to the gaseous diffusion assembly to link the individual 
assemblies to each other to form cascades (or stages) to allow for 
progressively higher enrichments and to extract the ``product'' and 
``tails'' UF6 from the diffusion cascades. Because of the 
high inertial properties of diffusion cascades, any interruption in 
their operation, and especially their shut-down, leads to serious 
consequences. Therefore, a strict and constant maintenance of vacuum in 
all technological systems, automatic protection for accidents, and 
precise automated regulation of the gas flow is of importance in a 
gaseous diffusion plant. All this leads to a need to equip the plant 
with a large number of special measuring, regulating, and controlling 
systems.
    Normally UF6 is evaporated from cylinders placed within 
autoclaves and is distributed in gaseous form to the entry point by way 
of cascade header pipework. The ``product'' and ``tails'' UF6 
gaseous streams flowing from exit points are passed by way of cascade 
header pipework to either cold traps or to compression stations where 
the UF6 gas is liquified prior to onward transfer into 
suitable containers for transportation or storage. Because a gaseous 
diffusion enrichment plant consists of a large number of gaseous 
diffusion assemblies arranged in cascades, there are many kilometers of 
cascade header pipework, incorporating thousands of welds with 
substantial amounts of repetition of layout. The equipment, components, 
and piping systems are fabricated to very high vacuum and cleanliness 
standards.
    The items listed below either come into direct contact with the 
UF6 process gas or directly control the flow within the 
cascade. All surfaces which come into contact with the process gas are 
wholly made of, or lined with, UF6-resistant materials. For 
the purposes of this appendix, the materials resistant to corrosion by 
UF6 include copper, copper alloys, stainless steel, aluminum, 
aluminum oxide, aluminum alloys, nickel or alloys containing 60 percent 
or more nickel and fluorinated hydrocarbon polymers.
    1. Assemblies and components especially designed or prepared for use 
in gaseous diffusion enrichment.

          1.1 Gaseous Diffusion Barriers and Barrier Materials

    (a) Especially designed or prepared thin, porous filters, with a 
pore size of 10-100 nm, a thickness of 5 mm or less, and for tubular 
forms, a diameter of 25 mm or less, made of metallic, polymer or ceramic 
materials resistant to corrosion by UF6 (See Note in Sec. 2 
of this appendix).
    (b) Especially prepared compounds or powders for the manufacture of 
such filters. Such compounds and powders include nickel or alloys 
containing 60 percent or more nickel, aluminum oxide, or UF6-
resistant fully fluorinated hydrocarbon polymers having a purity of 99.9 
percent by weight or more, a particle size less than 10 [micro]m, and a 
high degree of particle size uniformity, which are especially prepared 
for the manufacture of gaseous diffusion barriers.

                          1.2 Diffuser Housings

    Especially designed or prepared hermetically sealed vessels for 
containing the gaseous diffusion barrier, made of or protected by 
UF6-resistant materials (See Note in Sec. 2 of this 
appendix).

                     1.3 Compressors and Gas Blowers

    Especially designed or prepared compressors or gas blowers with a 
suction volume capacity of 1 m\3\ per minute or more of UF6, 
and with a discharge pressure of up to 500 kPa, designed for long-term 
operation in the UF6 environment, as well as separate 
assemblies of such compressors and gas blowers. These compressors and 
gas blowers have a pressure ratio of 10:1 or less and are made of, or 
protected by, materials resistant to UF6 (See Note in Sec. 2 
of this appendix).

                         1.4 Rotary Shaft Seals

    Especially designed or prepared vacuum seals, with seal feed and 
seal exhaust connections, for sealing the shaft connecting the 
compressor or the gas blower rotor with the driver motor so as to ensure 
a reliable seal against in-leaking of air into the inner chamber of the 
compressor or gas blower which is filled with UF6. Such seals 
are normally designed for a buffer gas in-leakage rate of less than 1000 
cm\3\ per minute.

             1.5 Heat Exchangers for Cooling UF6

    Especially designed or prepared heat exchangers made of or protected 
by UF6 resistant materials (see Note to Sec. 2 of this 
appendix) and intended for a leakage pressure change rate of less than 
10 Pa per hour under a pressure difference of 100 kPa.
    2. Auxiliary systems, equipment, and components especially designed 
or prepared for use in gaseous diffusion enrichment.
    Note: The items listed below either come into direct contact with 
the UF6 process gas

[[Page 736]]

or directly control the flow within the cascade. Materials resistant to 
corrosion by UF6 include copper, copper alloys, stainless 
steel, aluminum, aluminum oxide, aluminum alloys, nickel or alloys 
containing 60 percent or more nickel, and fluorinated hydrocarbon 
polymers.

          2.1 Feed Systems/Product and Tails Withdrawal Systems

    Especially designed or prepared process systems or equipment for 
enrichment plants made of, or protected by, materials resistant to 
corrosion by UF6, including:
    (1) Feed autoclaves, ovens, or systems used for passing 
UF6 to the enrichment process;
    (2) Desublimers, cold traps, or pumps used to remove UF6 
from the enrichment process for subsequent transfer upon heating;
    (3) Solidification or liquefaction stations used to remove 
UF6 from the enrichment process by compressing and converting 
UF6 to a liquid or solid form;
    (4) ``Product'' or ``tails'' stations used for transferring 
UF6 into containers.

                        2.2 Header Piping Systems

    Especially designed or prepared piping systems and header systems 
for handling UF6 within the gaseous diffusion cascades. This 
piping network is normally of the ``double'' header system with each 
cell connected to each of the headers.

                           2.3 Vacuum Systems

    (a) Especially designed or prepared vacuum manifolds, vacuum headers 
and vacuum pumps having a suction capacity of 5 m\3\ per minute or more.
    (b) Vacuum pumps especially designed for service in UF6-
bearing atmospheres made of, or protected by, materials resistant to 
corrosion by UF6 (See Note to this section). These pumps may 
be either rotary or positive displacement, may have fluorocarbon seals, 
and may have special working fluids present.

                 2.4 Special Shut-Off and Control Valves

    Especially designed or prepared bellows-sealed valves, manual or 
automated, shut-off or control valves, made of, or protected by, 
materials resistant to corrosion by UF6, for installation in 
main and auxiliary systems of gaseous diffusion enrichment plants.

            2.5 UF6 Mass Spectrometers/Ion Sources

    Especially designed or prepared mass spectrometers capable of taking 
on-line samples from UF6 gas streams and having all of the 
following:
    (a) Capable of measuring ions of 320 atomic mass units or greater 
and having a resolution of better than 1 part in 320;
    (b) ion sources constructed of or protected by nickel, nickel-copper 
alloys with a nickel content of 60 percent or more by weight, or nickel-
chrome alloys;
    (c) electron bombardment ionization sources; and
    (d) having a collector system suitable for isotopic analysis.
    3. Any other components especially designed or prepared for use in a 
gaseous diffusion enrichment plant or in any of the components described 
in this appendix.

[79 FR 39293, July 10, 2014]



Sec. Appendix D to Part 110--Illustrative List of Aerodynamic Enrichment 
   Plant Equipment and Components Under NRC Export Licensing Authority

     In aerodynamic enrichment processes, a mixture of gaseous 
UF6 and light gas (hydrogen or helium) is compressed and then 
passed through separating elements wherein isotopic separation is 
accomplished by the generation of high centrifugal forces over a curved-
wall geometry. Two processes of this type have been successfully 
developed: The separation nozzle process and the vortex tube process. 
For both processes, the main components of a separation stage included 
cylindrical vessels housing the special separation elements (nozzles or 
vortex tubes), gas compressors, and heat exchangers to remove the heat 
of compression. An aerodynamic plant requires a number of these stages, 
so that quantities can provide an important indication of end use. 
Because aerodynamic processes use UF6, all equipment, 
pipeline and instrumentation surfaces (that come in contact with the 
gas) must be made of, or protected by, materials that remain stable in 
contact with UF6. All surfaces which come into contact with 
the process gas are made of, or protected by, UF6-resistant 
materials; including copper, copper alloys, stainless steel, aluminum, 
aluminum oxide, aluminum alloys, nickel or alloys containing 60 percent 
or more nickel by weight, and fluorinated hydrocarbon polymers.

    The following items either come into direct contact with the 
UF6 process gas or directly control the flow within the 
cascade:
    (1) Separation nozzles and assemblies.
    Especially designed or prepared separation nozzles and assemblies 
thereof. The separation nozzles consist of slit-shaped, curved channels 
having a radius of curvature less than 1 mm, resistant to corrosion by 
UF6 and having a knife-edge within the nozzle that separates 
the gas flowing through the nozzle into two fractions.
    (2) Vortex tubes and assemblies.
    Especially designed or prepared vortex tubes and assemblies thereof. 
The vortex tubes are cylindrical or tapered, made of, or protected by, 
materials resistant to corrosion by UF6, and with one or more 
tangential

[[Page 737]]

inlets. The tubes may be equipped with nozzle-type appendages at either 
or both ends.
    The feed gas enters the vortex tube tangentially at one end or 
through swirl vanes or at numerous tangential positions along the 
periphery of the tube.
    (3) Compressors and gas blowers.
    Especially designed or prepared compressors or gas blowers made of, 
or protected by, materials resistant to corrosion by the UF6/
carrier gas (hydrogen or helium) mixture.
    (4) Rotary shaft seals.
    Especially designed or prepared rotary shaft seals, with seal feed 
and seal exhaust connections, for sealing the shaft connecting the 
compressor rotor or the gas blower rotor with the driver motor to ensure 
a reliable seal against out-leakage of process gas or in-leakage of air 
or seal gas into the inner chamber of the compressor or gas blower which 
is filled with a UF6/carrier gas mixture.
    (5) Heat exchangers for gas cooling.
    Especially designed or prepared heat exchangers, made of, or 
protected by, materials resistant to corrosion by UF6.
    (6) Separation element housings.
    Especially designed or prepared separation element housings, made 
of, or protected by, materials resistant to corrosion by UF6, 
for containing vortex tubes or separation nozzles.
    (7) Feed systems/product and tails withdrawal systems.
    Especially designed or prepared process systems or equipment for 
enrichment plants made of, or protected by, materials resistant to 
corrosion by UF6, including:
    (i) Feed autoclaves, ovens, or systems used for passing 
UF6 to the enrichment process;
    (ii) Desublimers (or cold traps) used to remove UF6 from 
the enrichment process for subsequent transfer upon heating;
    (iii) Solidification or liquefaction stations used to remove 
UF6 from the enrichment process by compressing and converting 
UF6 to a liquid or solid form; and
    (iv) ``Product'' or ``tails'' stations used for transferring 
UF6 into containers.
    (8) Header piping systems.
    Especially designed or prepared header piping systems, made of or 
protected by materials resistant to corrosion by UF6, for 
handling UF6 within the aerodynamic cascades. The piping 
network is normally of the ``double'' header design with each stage or 
group of stages connected to each of the headers.
    (9) Vacuum systems and pumps.
    (i) Especially designed or prepared vacuum systems consisting of 
vacuum manifolds, vacuum headers and vacuum pumps, and designed for 
service in UF6-bearing atmospheres.
    (ii) Especially designed or prepared vacuum pumps for service in 
UF6-bearing atmospheres and made of, or protected by, 
materials resistant to corrosion by UF6. These pumps may use 
fluorocarbon seals and special working fluids.
    (10) Special shut-off and control valves.
    Especially designed or prepared bellows-sealed valves, manual or 
automated, shut-off or control valves made of, or protected by, 
materials resistant to corrosion by UF6 with a diameter of 40 
mm or greater for installation in main and auxiliary systems of 
aerodynamic enrichment plants.
    (11) UF6 mass spectrometers/ion sources.
    Especially designed or prepared mass spectrometers capable of taking 
on-line samples from UF6 gas streams and having all of the 
following:
    (i) Capable of measuring ions of 320 atomic mass units or greater 
and having a resolution of better than 1 part in 320;
    (ii) Ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel content of 60 percent or more by weight, or 
nickel-chrome alloys;
    (iii) Electron bombardment ionization sources; and
    (iv) Collector system suitable for isotopic analysis.
    (12) UF6/carrier gas separation systems.
    Especially designed or prepared process systems for separating 
UF6 from carrier gas (hydrogen or helium).
    These systems are designed to reduce the UF6 content in 
the carrier gas to 1 ppm or less and may incorporate equipment such as:
    (i) Cryogenic heat exchangers and cryoseparators capable of 
temperatures of 153 K (-120 [deg]C) or less;
    (ii) Cryogenic refrigeration units capable of temperatures of 153 K 
(-120 [deg]C) or less;
    (iii) Separation nozzle or vortex tube units for the separation of 
UF6 from carrier gas; or
    (iv) UF6 cold traps capable of freezing out UF6.
    (13) Any other components especially designed or prepared for use in 
an aerodynamic enrichment plant or in any of the components described in 
this appendix.

[79 FR 39294, July 10, 2014]



 Sec. Appendix E to Part 110--Illustrative List of Chemical Exchange or 
Ion Exchange Enrichment Plant Equipment and Components Under NRC Export 
                           Licensing Authority

    Note: The slight difference in mass between the isotopes of uranium 
causes small changes in chemical reaction equilibria that can be used as 
a basis for separation of the isotopes. Two processes have been 
successfully developed: Liquid-liquid chemical exchange and solid-liquid 
ion exchange.

    A. In the liquid-liquid chemical exchange process, immiscible liquid 
phases (aqueous and organic) are countercurrently contacted to give the 
cascading effect of thousands of

[[Page 738]]

separation stages. The aqueous phase consists of uranium chloride in 
hydrochloric acid solution; the organic phase consists of an extractant 
containing uranium chloride in an organic solvent. The contactors 
employed in the separation cascade can be liquid-liquid exchange columns 
(such as pulsed columns with sieve plates) or liquid centrifugal 
contactors. Chemical conversions (oxidation and reduction) are required 
at both ends of the separation cascade in order to provide for the 
reflux requirements at each end. A major design concern is to avoid 
contamination of the process streams with certain metal ions. Plastic, 
plastic-lined (including use of fluorocarbon polymers) and/or glass-
lined columns and piping are therefore used.
    (1) Liquid-liquid exchange columns.
    Countercurrent liquid-liquid exchange columns having mechanical 
power input especially designed or prepared for uranium enrichment using 
the chemical exchange process. For corrosion resistance to concentrated 
hydrochloric acid solutions, these columns and their internals are 
normally made of, or protected by, suitable plastic materials (such as 
fluorinated hydrocarbon polymers) or glass. The stage residence time of 
the columns is normally designed to be 30 seconds or less.
    (2) Liquid-liquid centrifugal contactors.
    Especially designed or prepared for uranium enrichment using the 
chemical exchange process. These contactors use rotation to achieve 
dispersion of the organic and aqueous streams and then centrifugal force 
to separate the phases. For corrosion resistance to concentrated 
hydrochloric acid solutions, the contactors are normally made of, or 
protected by, suitable plastic materials (such as fluorinated 
hydrocarbon polymers) or glass. The stage residence time of the 
centrifugal contactors is designed to be short (30 seconds or less).
    (3) Uranium reduction systems and equipment.
    (i) Especially designed or prepared electrochemical reduction cells 
to reduce uranium from one valence state to another for uranium 
enrichment using the chemical exchange process. The cell materials in 
contact with process solutions must be corrosion resistant to 
concentrated hydrochloric acid solutions.
    The cell cathodic compartment must be designed to prevent re-
oxidation of uranium to its higher valence state. To keep the uranium in 
the cathodic compartment, the cell may have an impervious diaphragm 
membrane constructed of special cation exchange material. The cathode 
consists of a suitable solid conductor such as graphite.
    These systems consist of solvent extraction equipment for stripping 
the U + 4 from the organic stream into an aqueous solution, 
evaporation and/or other equipment to accomplish solution pH adjustment 
and control, and pumps or other transfer devices for feeding to the 
electrochemical reduction cells. A major design concern is to avoid 
contamination of the aqueous stream with certain metal ions. For those 
parts in contact with the process stream, the system is constructed of 
equipment made of, or protected by, materials such as glass, 
fluorocarbon polymers, polyphenyl sulfate, polyether sulfone, and resin-
impregnated graphite.
    (ii) Especially designed or prepared systems at the product end of 
the cascade for taking the U + 4 out of the organic stream, 
adjusting the acid concentration, and feeding to the electrochemical 
reduction cells.
    These systems consist of solvent extraction equipment for stripping 
the U + 4 from the organic stream into an aqueous solution, 
evaporation and/or other equipment to accomplish solution pH adjustment 
and control, and pumps or other transfer devices for feeding to the 
electrochemical reduction cells. A major design concern is to avoid 
contamination of the aqueous stream with certain metal ions. For those 
parts in contact with the process stream, the system is constructed of 
equipment made of, or protected by, materials such as glass, 
fluorocarbon polymers, polyphenyl sulfate, polyether sulfone, and resin-
impregnated graphite.
    (4) Feed preparation systems.
    Especially designed or prepared systems for producing high-purity 
uranium chloride feed solutions for chemical exchange uranium isotope 
separation plants.
    These systems consist of dissolution, solvent extraction and/or ion 
exchange equipment for purification and electrolytic cells for reducing 
the uranium U + 6 or U + 4 to U + 3. 
These systems produce uranium chloride solutions having only a few parts 
per million of metallic impurities such as chromium, iron, vanadium, 
molybdenum, and other bivalent or higher multi-valent cations. Materials 
of construction for portions of the system processing high-purity 
U + 3 include glass, fluorinated hydrocarbon polymers, 
polyphenyl sulfate or polyether sulfone plastic-lined and resin-
impregnated graphite.
    (5) Uranium oxidation systems.
    Especially designed or prepared systems for oxidation of 
U + 3 to U + 4 for return to the uranium isotope 
separation cascade in the chemical exchange enrichment process.
    These systems may incorporate equipment such as:
    (i) Equipment for contacting chlorine and oxygen with the aqueous 
effluent from the isotope separation equipment and extracting the 
resultant U + 4 into the stripped organic stream returning 
from the product end of the cascade; and
    (ii) Equipment that separates water from hydrochloric acid so that 
the water and the

[[Page 739]]

concentrated hydrochloric acid may be reintroduced to the process at the 
proper locations.
    B. In the solid-liquid ion-exchange process, enrichment is 
accomplished by uranium adsorption/desorption on a special, fast-acting, 
ion-exchange resin or adsorbent. A solution of uranium in hydrochloric 
acid and other chemical agents is passed through cylindrical enrichment 
columns containing packed beds of the adsorbent. For a continuous 
process, a reflux system is necessary to release the uranium from the 
adsorbent back in the liquid flow so that ``product'' and ``tails'' can 
be collected. This is accomplished with the use of suitable reduction/
oxidation chemical agents that are fully regenerated in separate 
external circuits and that may be partially regenerated within the 
isotopic separation columns themselves. The presence of hot concentrated 
hydrochloric acid solutions in the process requires that the equipment 
be made of, or protected by, special corrosion-resistant materials.
    (1) Fast reacting ion exchange resins/adsorbents.
    Especially designed or prepared for uranium enrichment using the ion 
exchange process, including porous macroreticular resins, and/or 
pellicular structures in which the active chemical exchange groups are 
limited to a coating on the surface of an inactive porous support 
structure, and other composite structures in any suitable form including 
particles or fibers. These ion exchange resins/adsorbents have diameters 
of 0.2 mm or less and must be chemically resistant to concentrated 
hydrochloric acid solutions as well as physically strong enough so as 
not to degrade in the exchange columns. The resins/adsorbents are 
especially designed to achieve very fast uranium isotope exchange 
kinetics (exchange rate half-time of less than 10 seconds) and are 
capable of operating at a temperature in the range of 373 K (100 [deg]C) 
to 473 K (200 [deg]C).
    (2) Ion exchange columns.
    Cylindrical columns greater than 1000 mm in diameter for containing 
and supporting packed beds of ion exchange resin/adsorbent, especially 
designed or prepared for uranium enrichment using the ion exchange 
process. These columns are made of, or protected by, materials (such as 
titanium or fluorocarbon plastics) resistant to corrosion by 
concentrated hydrochloric acid solutions and are capable of operating at 
a temperature in the range of 373 K (100 [deg]C) to 473 K (200 [deg]C) 
and pressures above 0.7 MPa.
    (3) Ion exchange reflux systems.
    (i) Especially designed or prepared chemical or electrochemical 
reduction systems for regeneration of the chemical reducing agent(s) 
used in ion exchange uranium enrichment cascades.
    The ion exchange enrichment process may use, for example, trivalent 
titanium (Ti + 3) as a reducing cation in which case the 
reduction system would regenerate Ti + 3 by reducing 
Ti + 4.
    (ii) Especially designed or prepared chemical or electrochemical 
oxidation systems for regeneration of the chemical oxidizing agent(s) 
used in ion exchange uranium enrichment cascades.
    The ion exchange enrichment process may use, for example, trivalent 
iron (Fe + 3) as an oxidant in which case the oxidation 
system would regenerate Fe + 3 by oxidizing 
Fe + 2.
    C. Any other components especially designed or prepared for use in a 
chemical exchange or ion exchange enrichment plant or in any of the 
components described in this appendix.

[79 FR 39295, July 10, 2014]



Sec. Appendix F to Part 110--Illustrative List of Laser-Based Enrichment 
   Plant Equipment and Components Under NRC Export Licensing Authority

    Note: Present systems for enrichment processes using lasers fall 
into two categories: The process medium is atomic uranium vapor and the 
process medium is the vapor of a uranium compound, sometimes mixed with 
another gas or gases. Common nomenclature for these processes include: 
First category-atomic vapor laser isotope separation; and second 
category-molecular laser isotope separation including chemical reaction 
by isotope selective laser activation. The systems, equipment, and 
components for laser enrichment plants include: (a) Devices to feed 
uranium-metal vapor for selective photo-ionization or devices to feed 
the vapor of a uranium compound (for selective photo-dissociation or 
selective excitation/activation); (b) devices to collect enriched and 
depleted uranium metal as ``product'' and ``tails'' in the first 
category, and devices to collect enriched and depleted uranium compounds 
as ``product'' and ``tails'' in the second category; (c) process laser 
systems to selectively excite the uranium-235 species; and (d) feed 
preparation and product conversion equipment. The complexity of the 
spectroscopy of uranium atoms and compounds may require incorporation of 
a number of available laser and laser optics technologies.

    All surfaces that come into direct contact with the uranium or 
UF6 are wholly made of, or protected by, corrosion-resistant 
materials. For laser-based enrichment items, the materials resistant to 
corrosion by the vapor or liquid of uranium metal or uranium alloys 
include yttria-coated graphite and tantalum; and the materials resistant 
to corrosion by UF6 include copper, copper alloys, stainless 
steel, aluminum, aluminum oxide, aluminum alloys, nickel or alloys 
containing 60 percent

[[Page 740]]

or more nickel by weight, and fluorinated hydrocarbon polymers. Many of 
the following items come into direct contact with uranium metal vapor or 
liquid or with process gas consisting of UF6 or a mixture of 
UF6 and other gases:
    (1) Uranium vaporization systems (atomic vapor based methods).
    Especially designed or prepared uranium metal vaporization systems 
for use in laser enrichment.
    These systems may contain electron beam guns and are designed to 
achieve a delivered power (1 kW or greater) on the target sufficient to 
generate uranium metal vapour at a rate required for the laser 
enrichment function.
    (2) Liquid or vapor uranium metal handling systems and components 
(atomic vapor based methods).
    Especially designed or prepared systems for handling molten uranium, 
molten uranium alloys, or uranium metal vapor.
    The liquid uranium metal handling systems may consist of crucibles 
and cooling equipment for the crucibles. The crucibles and other system 
parts that come into contact with molten uranium, molten uranium alloys, 
or uranium metal vapor are made of, or protected by, materials of 
suitable corrosion and heat resistance, such as tantalum, yttria-coated 
graphite, graphite coated with other rare earth oxides, or mixtures 
thereof.
    (3) Uranium metal ``product'' and ``tails'' collector assemblies 
(atomic vapor based methods).
    Especially designed or prepared ``product'' and ``tails'' collector 
assemblies for uranium metal in liquid or solid form.
    Components for these assemblies are made of or protected by 
materials resistant to the heat and corrosion of uranium metal vapor or 
liquid, such as yttria-coated graphite or tantalum, and may include 
pipes, valves, fittings, ``gutters,'' feed-throughs, heat exchangers and 
collector plates for magnetic, electrostatic, or other separation 
methods.
    (4) Separator module housings (atomic vapor based methods).
    Especially designed or prepared cylindrical or rectangular vessels 
for containing the uranium metal vapor source, the electron beam gun, 
and the ``product'' and ``tails'' collectors. These housings have 
multiplicity of ports for electrical and water feed-throughs, laser beam 
windows, vacuum pump connections, and instrumentation diagnostics and 
monitoring with opening and closure provisions to allow refurbishment of 
internal components.
    (5) Supersonic expansion nozzles (molecular based methods).
    Especially designed or prepared supersonic expansion nozzles for 
cooling mixtures of UF6 and carrier gas to 150 K (-123 
[deg]C) or less which are corrosion resistant to UF6.
    (6) ``Product'' or ``tails'' collectors (molecular based methods).
    Especially designed or prepared components or devices for collecting 
uranium product material or uranium tails material following 
illumination with laser light.
    In one example of molecular laser isotope separation, the product 
collectors serve to collect enriched uranium pentafluoride 
(UF5) solid material. The product collectors may consist of 
filter, impact, or cyclone-type collectors, or combinations thereof, and 
must be corrosion resistant to the UF5/UF6 
environment.
    (7) UF6/carrier gas compressors (molecular based 
methods).
    Especially designed or prepared compressors for UF6/
carrier gas mixtures, designed for long term operation in a 
UF6 environment. Components of these compressors that come 
into contact with process gas are made of, or protected by, materials 
resistant to UF6 corrosion.
    (8) Rotary shaft seals (molecular based methods).
    Especially designed or prepared rotary shaft seals, with seal feed 
and seal exhaust connections, for sealing the shaft connecting the 
compressor rotor with the driver motor to ensure a reliable seal against 
out-leakage of process gas or in-leakage of air or seal gas into the 
inner chamber of the compressor which is filled with a UF6/
carrier gas mixture.
    (9) Fluorination systems (molecular based methods).
    Especially designed or prepared systems for fluorinating 
UF5 (solid) to UF6 (gas).
    These systems are designed to fluorinate the collected 
UF5 powder to UF6 for subsequent collection in 
product containers or for transfer as feed for additional enrichment. In 
one approach, the fluorination reaction may be accomplished within the 
isotope separation system to react and recover directly off the 
``product'' collectors. In another approach, the UF5 powder 
may be removed/transferred from the ``product'' collectors into a 
suitable reaction vessel (e.g., fluidized-bed reactor, screw reactor or 
flame tower) for fluorination. In both approaches, equipment is used for 
storage and transfer of fluorine (or other suitable fluorinating agents) 
and for collection and transfer of UF6.
    (10) UF6 mass spectrometers/ion sources (molecular based 
methods).
    Especially designed or prepared mass spectrometers capable of taking 
on-line samples from UF6 gas streams and having all of the 
following characteristics:
    (i) Capable of measuring ions of 320 atomic mass units or greater 
and having a resolution of better than 1 part in 320;
    (ii) Ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel

[[Page 741]]

content of 60 percent or more by weight, or nickel-chrome alloys;
    (iii) Electron bombardment ionization sources; and
    (iv) Collector system suitable for isotopic analysis.
    (11) Feed systems/product and tails withdrawal systems (molecular 
based methods).
    Especially designed or prepared process systems or equipment for 
enrichment plants made of or protected by materials resistant to 
corrosion by UF6, including:
    (i) Feed autoclaves, ovens, or systems used for passing 
UF6 to the enrichment process;
    (ii) Desublimers (or cold traps) used to remove UF6 from 
the enrichment process for subsequent transfer upon heating;
    (iii) Solidification or liquefaction stations used to remove 
UF6 from the enrichment process by compressing and converting 
UF6 to a liquid or solid; and
    (iv) ``Product'' or ``tails'' stations used to transfer 
UF6 into containers.
    (12) UF6/carrier gas separation systems (molecular based 
methods).
    Especially designed or prepared process systems for separating 
UF6 from carrier gas.
    These systems may incorporate equipment such as:
    (i) Cryogenic heat exchangers or cryoseparators capable of 
temperatures of 153 K (-120 [deg]C) or less;
    (ii) Cryogenic refrigeration units capable of temperatures of 153 K 
(-120 [deg]C) or less; or
    (iii) UF6 cold traps capable of freezing out 
UF6.
    (13) Lasers or Laser systems.
    Especially designed or prepared for the separation of uranium 
isotopes.
    The laser system typically contains both optical and electronic 
components for the management of the laser beam (or beams) and the 
transmission to the isotope separation chamber. The laser system for 
atomic vapor based methods usually consists of tunable dye lasers pumped 
by another type of laser (e.g., copper vapor lasers or certain solid-
state lasers). The laser system for molecular based methods may consist 
of CO2 lasers or excimer lasers and a multi-pass optical 
cell. Lasers or laser systems for both methods require spectrum 
frequency stabilization for operation over extended periods of time.
    (14) Any other components especially designed or prepared for use in 
a laser-based enrichment plant or in any of the components described in 
this appendix.

[79 FR 39296, July 10, 2014]



  Sec. Appendix G to Part 110--Illustrative List of Plasma Separation 
  Enrichment Plant Equipment and Components Under NRC Export Licensing 
                                Authority

    Note: In the plasma separation process, a plasma of uranium ions 
passes through an electric field tuned to the \235\U ion resonance 
frequency so that they preferentially absorb energy and increase the 
diameter of their corkscrew-like orbits. Ions with a large-diameter path 
are trapped to produce a product enriched in \235\U. The plasma, made by 
ionizing uranium vapor, is contained in a vacuum chamber with a high-
strength magnetic field produced by a superconducting magnet. The main 
technological systems of the process include the uranium plasma 
generation system, the separator module with superconducting magnet, and 
metal removal systems for the collection of ``product'' and ``tails.''

    (1) Microwave power sources and antennae.
    Especially designed or prepared microwave power sources and antennae 
for producing or accelerating ions having the following characteristics: 
Greater than 30 GHz frequency and greater than 50 kW mean power output 
for ion production.
    (2) Ion excitation coils.
    Especially designed or prepared radio frequency ion excitation coils 
for frequencies of more than 100 kHz and capable of handling more than 
40 kW mean power.
    (3) Uranium plasma generation systems.
    Especially designed or prepared systems for the generation of 
uranium plasma for use in plasma separation plants.
    (4) Uranium metal ``product'' and ``tails'' collector assemblies.
    Especially designed or prepared ``product'' and ``tails'' collector 
assemblies for uranium metal in solid form. These collector assemblies 
are made of, or protected by, materials resistant to the heat and 
corrosion of uranium metal vapor, such as yttria-coated graphite or 
tantalum.
    (5) Separator module housings.
    Especially designed or prepared cylindrical vessels for use in 
plasma separation enrichment plants for containing the uranium plasma 
source, radio-frequency drive coil, and the ``product'' and ``tails'' 
collectors.
    These housings have a multiplicity of ports for electrical feed-
throughs, diffusion pump connections, and instrumentation diagnostics 
and monitoring. They have provisions for opening and closure to allow 
for refurbishment of internal components and are constructed of a 
suitable non-magnetic material such as stainless steel.

[[Page 742]]

    (6) Any other components especially designed or prepared for use in 
a plasma separation enrichment plant or in any of the components 
described in this appendix.

[79 FR 39297, July 10, 2014]



   Sec. Appendix H to Part 110--Illustrative List of Electromagnetic 
  Enrichment Plant Equipment and Components Under NRC Export Licensing 
                                Authority

    Note: In the electromagnetic process, uranium metal ions produced by 
ionization of a salt feed material (typically UCL4) are accelerated and 
passed through a magnetic field that has the effect of causing the ions 
of different isotopes to follow different paths. The major components of 
an electromagnetic isotope separator include: a magnetic field for ion-
beam diversion/separation of the isotopes, an ion source with its 
acceleration system, and a collection system for the separated ions. 
Auxiliary systems for the process include the magnet power supply 
system, the ion source high-voltage power supply system, the vacuum 
system, and extensive chemical handling systems for recovery of product 
and cleaning/recycling of components.

    (1) Electromagnetic isotope separators.
    Especially designed or prepared for the separation of uranium 
isotopes, and equipment and components therefor, including:
    (i) Ion Sources--especially designed or prepared single or multiple 
uranium ion sources consisting of a vapor source, ionizer, and beam 
accelerator, constructed of materials such as graphite, stainless steel, 
or copper, and capable of providing a total ion beam current of 50 mA or 
greater;
    (ii) Ion collectors--collector plates consisting of two or more 
slits and pockets especially designed or prepared for collection of 
enriched and depleted uranium ion beams and constructed of materials 
such as graphite or stainless steel;
    (iii) Vacuum housings--especially designed or prepared vacuum 
housings for uranium electromagnetic separators, constructed of suitable 
non-magnetic materials such as stainless steel and designed for 
operation at pressures of 0.1 Pa or lower.
    The housings are specially designed to contain the ion sources, 
collector plates and water-cooled liners and have provision for 
diffusion pump connections and opening and closure for removal and 
reinstallation of these components; and
    (iv) Magnet pole pieces--especially designed or prepared magnet pole 
pieces having a diameter greater than 2 m used to maintain a constant 
magnetic field within an electromagnetic isotope separator and to 
transfer the magnetic field between adjoining separators.
    (2) High voltage power supplies.
    Especially designed or prepared high-voltage power supplies for ion 
sources, having all of the following characteristics:
    (i) Capable of continuous operation;
    (ii) Output voltage of 20,000 V or greater;
    (iii) Output current of 1 A or greater; and
    (iv) Voltage regulation of better than 0.01% over an 8 hour time 
period.
    (3) Magnet power supplies.
    Especially designed or prepared high-power, direct current magnet 
power supplies having all of the following characteristics:
    (i) Capable of continuously producing a current output of 500 A or 
greater at a voltage of 100 V or greater; and
    (ii) A current or voltage regulation better than 0.01% over an 8 
hour time period.
    (4) Any other components especially designed or prepared for use in 
an electromagnetic enrichment plant or in any of the components 
described in this appendix.

[61 FR 35606, July 8, 1996, as amended at 79 FR 39297, July 10, 2014]



  Sec. Appendix I to Part 110--Illustrative List of Reprocessing Plant 
             Components Under NRC Export Licensing Authority

    Note: Reprocessing irradiated nuclear fuel separates plutonium and 
uranium from intensely radioactive fission products and other 
transuranic elements. Different technical processes can accomplish this 
separation. However, over the years Purex has become the most commonly 
used and accepted process. Purex involves the dissolution of irradiated 
nuclear fuel in nitric acid, followed by separation of the uranium, 
plutonium, and fission products by solvent extraction using a mixture of 
tributyl phosphate in an organic diluent.

    Purex facilities have process functions similar to each other, 
including: Irradiated fuel element chopping, fuel dissolution, solvent 
extraction, and process liquor storage. There may also be equipment for 
thermal denitration of uranium nitrate, conversion of plutonium nitrate 
to oxide metal, and treatment of fission product waste liquor to a form 
suitable for long term storage or disposal. However, the specific type 
and configuration of the equipment performing these functions may differ 
between Purex facilities for several reasons, including the type and 
quantity of irradiated nuclear fuel to be reprocessed and the intended 
disposition of the recovered materials, and the safety and maintenance 
philosophy incorporated into the design of the facility. A plant for the 
reprocessing of irradiated fuel elements includes the equipment and 
components which normally come in direct contact with and directly 
control the irradiated fuel and

[[Page 743]]

the major nuclear material and fission product processing streams.
    (1) Irradiated fuel element chopping machines.
    Remotely operated equipment especially designed or prepared for use 
in a reprocessing plant and intended to cut, chop, or shear irradiated 
nuclear fuel assemblies, bundles, or rods. This equipment breaches the 
cladding of the fuel to expose the irradiated nuclear material to 
dissolution. Especially designed metal cutting shears are the most 
commonly employed, although advanced equipment, such as lasers, may be 
used.
    (2) Dissolvers.
    Critically safe tanks (e.g., small diameter, annular, or slab tanks) 
especially designed or prepared for use in a reprocessing plant, 
intended for dissolution of irradiated nuclear fuel and which are 
capable of withstanding hot, highly corrosive liquid, and which can be 
remotely loaded and maintained.
    Dissolvers normally receive the chopped-up spent fuel. In these 
critically safe vessels, the irradiated nuclear material is dissolved in 
nitric acid and the remaining hulls removed from the process stream.
    (3) Solvent extractors and solvent extraction equipment.
    Especially designed or prepared solvent extractors such as packed or 
pulse columns, mixer settlers, or centrifugal contactors for use in a 
plant for the reprocessing of irradiated fuel. Solvent extractors must 
be resistant to the corrosive effect of nitric acid. Solvent extractors 
are normally fabricated to extremely high standards (including special 
welding and inspection and quality assurance and quality control 
techniques) out of low carbon stainless steels, titanium, zirconium, or 
other high quality materials.
    Solvent extractors both receive the solution of irradiated fuel from 
the dissolvers and the organic solution which separates the uranium, 
plutonium, and fission products. Solvent extraction equipment is 
normally designed to meet strict operating parameters, such as long 
operating lifetimes with no maintenance requirements or adaptability to 
easy replacement, simplicity of operation and control, and flexibility 
for variations in process conditions.
    (4) Chemical holding or storage vessels.
    Especially designed or prepared holding or storage vessels for use 
in a plant for the reprocessing of irradiated fuel. The holding or 
storage vessels must be resistant to the corrosive effect of nitric 
acid. The holding or storage vessels are normally fabricated of 
materials such as low carbon stainless steels, titanium or zirconium, or 
other high quality materials. Holding or storage vessels may be designed 
for remote operation and maintenance and may have the following features 
for control of nuclear criticality:
    (i) Walls or internal structures with a boron equivalent of at least 
2 percent, or
    (ii) A maximum diameter of 175 mm (7 in) for cylindrical vessels, or
    (iii) A maximum width of 75 mm (3 in) for either a slab or annular 
vessel.
    (5) Neutron measurement systems for process control.
    Neutron measurement systems especially designed or prepared for 
integration and use with automated process control systems in a plant 
for the reprocessing of irradiated fuel elements. These systems involve 
the capability of active and passive neutron measurement and 
discrimination in order to determine the fissile material quantity and 
composition. The complete system is composed of a neutron generator, a 
neutron detector, amplifiers, and signal processing electronics.
    The scope of this entry does not include neutron detection and 
measurement instruments that are designed for nuclear material 
accountancy and safeguarding or any other application not related to 
integration and use with automated process control systems in a plant 
for the reprocessing of irradiated fuel elements.
    (6) Plutonium nitrate to plutonium oxide conversion systems. 
Complete systems especially designed or prepared for the conversion of 
plutonium nitrate to plutonium oxide, in particular adapted so as to 
avoid criticality and radiation effects and to minimize toxicity 
hazards.
    (7) Plutonium metal production systems. Complete systems especially 
designed or prepared for the production of plutonium metal, in 
particular adapted so as to avoid criticality and radiation effects and 
to minimize toxicity hazards.
    (8) Process control instrumentation specially designed or prepared 
for monitoring or controlling the processing of material in a 
reprocessing plant.
    (9) Any other components especially designed or prepared for use in 
a reprocessing plant or in any of the components described in this 
appendix.

[79 FR 39297, July 10, 2014]



  Sec. Appendix J to Part 110--Illustrative List of Uranium Conversion 
   Plant Equipment and Plutonium Conversion Plant Equipment Under NRC 
                       Export Licensing Authority

    Note: Uranium conversion plants and systems may perform one or more 
transformations from one uranium chemical species to another, including: 
conversion of uranium ore concentrates to UO3, conversion of UO3 to UO2, 
conversion of uranium oxides to UF4 or UF6, conversion of UF4 to UF6, 
conversion of UF6 to UF4, conversion of UF4 to uranium metal, and 
conversion of uranium fluorides to UO2. Many key equipment items for 
uranium conversion plants are common

[[Page 744]]

to several segments of the chemical process industry, including 
furnaces, rotary kilns, fluidized bed reactors, flame tower reactors, 
liquid centrifuges, distillation columns and liquid-liquid extraction 
columns. However, few of the items are available ``off-the-shelf''; most 
would be prepared according to customer requirements and specifications. 
Some require special design and construction considerations to address 
the corrosive properties of the chemicals handled (HF, F2, CLF3, and 
uranium fluorides). In all of the uranium conversion processes, 
equipment which individually is not especially designed or prepared for 
uranium conversion can be assembled into systems which are especially 
designed or prepared for uranium conversion.

    (a) Uranium Conversion Plant Equipment.
    (1) Especially designed or prepared systems for the conversion of 
uranium ore concentrates to UO3.
    Conversion of uranium ore concentrates to UO3 can be performed by 
first dissolving the ore in nitric acid and extracting purified uranyl 
nitrate using a solvent such as tributyl phosphate. Next, the uranyl 
nitrate is converted to UO3 either by concentration and denitration or 
by neutralization with gaseous ammonia to produce ammonium diuranate 
with subsequent filtering, drying, and calcining.
    (2) Especially designed or prepared systems for the conversion of 
UO3 to UF6.
    Conversion of UO3 to UF6 can be performed directly by fluorination. 
The process requires a source of fluorine gas or chlorine trifluoride.
    (3) Especially Designed or Prepared Systems for the conversion of 
UO3 to UO2.
    Conversion of UO3 to UO2 can be performed through reduction of UO3 
with cracked ammonia gas or hydrogen.
    (4) Especially Designed or Prepared Systems for the conversion of 
UO2 to UF4.
    Conversion of UO2 to UF4 can be performed by reacting UO2 with 
hydrogen fluoride gas (HF) at 300-500 [deg]C.
    (5) Especially Designed or Prepared Systems for the conversion of 
UF4 to UF6.
    Conversion of UF4 to UF6 is performed by exothermic reaction with 
fluorine in a tower reactor. UF6 is condensed from the hot effluent 
gases by passing the effluent stream through a cold trap cooled to -10 
[deg]C. The process requires a source of fluorine gas.
    (6) Especially Designed or Prepared Systems for the conversion of 
UF4 to U metal.
    Conversion of UF4 to U metal is performed by reduction with 
magnesium (large batches) or calcium (small batches). The reaction is 
carried out at temperatures above the melting point of uranium (1130 
[deg]C).
    (7) Especially designed or prepared systems for the conversion of 
UF6 to UO2.
    Conversion of UF6 to UO2 can be performed by one of three processes. 
In the first, UF6 is reduced and hydrolyzed to UO2 using hydrogen and 
steam. In the second, UF6 is hydrolyzed by solution in water, ammonia is 
added to precipitate ammonium diuranate, and the diuranate is reduced to 
UO2 with hydrogen at 820 [deg]C. In the third process, gaseous UF6, CO2, 
and NH3 are combined in water, precipitating ammonium uranyl carbonate. 
The ammonium uranyl carbonate is combined with steam and hydrogen at 
500-600 [deg]C to yield UO2. UF6 to UO2 conversion is often performed as 
the first stage of a fuel fabrication plant.
    (8) Especially Designed or Prepared Systems for the conversion of 
UF6 to UF4. Conversion of UF6 to UF4 is performed by reduction with 
hydrogen.
    (9) Especially designed or prepared systems for the conversion of 
UO2 to UCl4 as feed for electromagnetic 
enrichment.

    Note: Plutonium conversion plants and systems may perform one or 
more transformations from one plutonium chemical species to another, 
including: conversion of plutonium nitrate to PuO2, 
conversion of PuO2 to PuF4 and conversion of 
PuF4 to plutonium metal. Plutonium conversion plants are 
usually associated with reprocessing facilities, but may also be 
associated with plutonium fuel fabrication facilities. Many of the key 
equipment items for plutonium conversion plants are common to several 
segments of the chemical process industry. For example, the types of 
equipment employed in these processes may include the following items: 
furnaces, rotary kilns, fluidized bed reactors, flame tower reactors, 
liquid centrifuges, distillation columns and liquid-liquid extraction 
columns. Hot cells, glove boxes and remote manipulators may also be 
required. However, few of the items are available off-the-shelf; most 
would be prepared according to the requirements and specifications of 
the customer. Particular care is essential in designing for the special 
radiological, toxicity and criticality hazards associated with 
plutonium. In some circumstances, special design and construction 
considerations are required to address the corrosive properties of some 
of the chemicals handled (e.g., HF). Finally, it should be noted that, 
for all plutonium conversion processes, items of equipment which 
individually are not especially designed or prepared for plutonium 
conversion can be assembled into systems that are especially designed or 
prepared for use in plutonium conversion.

    (b) Plutonium Conversion Plant Equipment
    (1) Especially designed or prepared systems for the conversion of 
plutonium nitrate to oxide.
    The main functions involved in this process are: process feed 
storage and adjustment, precipitation and solid/liquor separation, 
calcination, product handling, ventilation, waste management, and 
process control. The

[[Page 745]]

process systems are particularly adapted so as to avoid criticality and 
radiation effects and to minimize toxicity hazards. In most reprocessing 
facilities, this process involves the conversion of plutonium nitrate to 
plutonium dioxide. Other processes can involve the precipitation of 
plutonium oxalate or plutonium peroxide.
    (2) Especially designed or prepared systems for plutonium metal 
production.
    This process usually involves the fluorination of plutonium dioxide, 
normally with highly corrosive hydrogen fluoride, to produce plutonium 
fluoride, which is subsequently reduced using high purity calcium metal 
to produce metallic plutonium and a calcium fluoride slag. The main 
functions involved in this process are the following: fluorination 
(e.g., involving equipment fabricated or lined with a precious metal), 
metal reduction (e.g., employing ceramic crucibles), slag recovery, 
product handling, ventilation, waste management and process control. The 
process systems are particularly adapted so as to avoid criticality and 
radiation effects and to minimize toxicity hazards. Other processes 
include the fluorination of plutonium oxalate or plutonium peroxide 
followed by reduction to metal.
    (c) Any other components especially designed or prepared for use in 
a uranium conversion plant or plutonium conversion plant or in any of 
the components described in this appendix.

[61 FR 35606, July 8, 1996, as amended at 65 FR 70291, Nov. 22, 2000; 79 
FR 39298, July 10, 2014]



    Sec. Appendix K to Part 110--Illustrative List of Equipment and 
 Components Under NRC Export Licensing Authority for Use in a Plant for 
    the Production of Heavy Water, Deuterium and Deuterium Compounds

    Note: Heavy water can be produced by a variety of processes. 
However, two processes have proven to be commercially viable: The water-
hydrogen sulphide exchange process (GS process) and the ammonia-hydrogen 
exchange process.

    A. The GS process is based upon the exchange of hydrogen and 
deuterium between water and hydrogen sulphide within a series of towers 
which are operated with the top section cold and the bottom section hot. 
Water flows down the towers while the hydrogen sulphide gas circulates 
from the bottom to the top of the towers. A series of perforated trays 
are used to promote mixing between the gas and the water. Deuterium 
migrates to the water at low temperatures and to the hydrogen sulphide 
at high temperatures. Gas or water, enriched in deuterium, is removed 
from the first stage towers at the junction of the hot and cold sections 
and the process is repeated in subsequent stage towers. The product of 
the last stage, water enriched up to 30 percent in deuterium, is sent to 
a distillation unit to produce reactor grade heavy water; i.e., 99.75 
percent deuterium oxide.
    B. The ammonia-hydrogen exchange process can extract deuterium from 
synthesis gas through contact with liquid ammonia in the presence of a 
catalyst. The synthesis gas is fed into exchange towers and then to an 
ammonia converter. Inside the towers the gas flows from the bottom to 
the top while the liquid ammonia flows from the top to the bottom. The 
deuterium is stripped from the hydrogen in the synthesis gas and 
concentrated in the ammonia. The ammonia then flows into an ammonia 
cracker at the bottom of the tower while the gas flows into an ammonia 
converter at the top. Further enrichment takes place in subsequent 
stages and reactor-grade heavy water is produced through final 
distillation. The synthesis gas feed can be provided by an ammonia plant 
that can be constructed in association with a heavy water ammonia-
hydrogen exchange plant. The ammonia-hydrogen exchange process can also 
use ordinary water as a feed source of deuterium.
    C.1. Much of the key equipment for heavy water production plants 
using either the GS process or the ammonia-hydrogen exchange process are 
common to several segments of the chemical and petroleum industries; 
particularly in small plants using the GS process. However, few items 
are available ``off-the-shelf.'' Both processes require the handling of 
large quantities of flammable, corrosive, and toxic fluids at elevated 
pressures. Therefore, in establishing the design and operating standards 
for plants and equipment using these processes, careful attention to 
materials selection and specifications is required to ensure long 
service life with high safety and reliability factors. The choice is 
primarily a function of economics and need. Most equipment, therefore, 
is prepared to customer requirements.
    In both processes, equipment which individually is not especially 
designed or prepared for heavy water production can be assembled into 
especially designed or prepared systems for producing heavy water. 
Examples of such systems are the catalyst production system used in the 
ammonia-hydrogen exchange process and the water distillation systems 
used for the final concentration of heavy water to reactor-grade in 
either process.
    C.2. Equipment especially designed or prepared for the production of 
heavy water utilizing either the water-hydrogen sulphide exchange 
process or the ammonia-hydrogen exchange process:

[[Page 746]]

    (i) Water-hydrogen Sulphide Exchange Towers.
    Exchange towers with diameters of 1.5 m or greater and capable of 
operating at pressures greater than or equal to 2 MPa (300 psi) 
especially designed or prepared for heavy water production utilizing the 
water-hydrogen sulphide exchange process.
    (ii) Blowers and Compressors.
    Single stage, low head (i.e., 0.2 MPa or 30 psi) centrifugal blowers 
or compressors for hydrogen-sulphide gas circulation (i.e., gas 
containing more than 70 percent H2S). The blowers or compressors have a 
throughput capacity greater than or equal to 56 m\3\/second (120,000 
standard cubic feet per minute) while operating at pressures greater 
than or equal to 1.8 MPa (260 psi) suction and have seals designed for 
wet H2S service.
    (iii) Ammonia-Hydrogen Exchange Towers.
    Ammonia-hydrogen exchange towers greater than or equal to 35 m 
(114.3 ft) in height with diameters of 1.5 m (4.9 ft) to 2.5 m (8.2 ft) 
capable of operating at pressures greater than 15 MPa (2225 psi). The 
towers have at least one flanged, axial opening of the same diameter as 
the cylindrical part through which the tower internals can be inserted 
or withdrawn.
    (iv) Tower Internals and Stage Pumps Used in the Ammonia-hydrogen 
Exchange Process.
    Tower internals include especially designed stage contactors which 
promote intimate gas/liquid contact. Stage pumps include especially 
designed submersible pumps for circulation of liquid ammonia within a 
contacting stage internal to the stage towers.
    (v) Ammonia Crackers Utilizing the Ammonia-hydrogen Exchange 
Process.
    Ammonia crackers with operating pressures greater than or equal to 3 
MPa (450 psi) especially designed or prepared for heavy water production 
utilizing the ammonia-hydrogen exchange process.
    (vi) Ammonia Synthesis Converters or Synthesis Units.
    Ammonia synthesis converters or synthesis units especially designed 
or prepared for heavy water production utilizing the ammonia-hydrogen 
exchange process.
    These converters or units take synthesis gas (nitrogen and hydrogen) 
from an ammonia/hydrogen high-pressure exchange column (or columns), and 
the synthesized ammonia is returned to the exchange column (or columns).
    (vii) Infrared Absorption Analyzers.
    Infrared absorption analyzers capable of ``on-line'' hydrogen/
deuterium ratio analysis where deuterium concentrations are equal to or 
greater than 90 percent.
    (viii) Catalytic Burners Used in the Ammonia-hydrogen Exchange 
Process.
    Catalytic burners for the conversion of enriched deuterium gas into 
heavy water especially designed or prepared for heavy water production 
utilizing the ammonia-hydrogen exchange process.
    (ix) Complete Heavy Water Upgrade Systems or Columns.
    Complete heavy water upgrade systems or columns especially designed 
or prepared for the upgrade of heavy water to reactor-grade deuterium 
concentration. These systems, which usually employ water distillation to 
separate heavy water from light water, are especially designed or 
prepared to produce reactor-grade heavy water (i.e., typically 99.75 
percent deuterium oxide) from heavy water feedstock of lesser 
concentration.
    D. Any other components especially designed or prepared for use in a 
plant for the production of heavy water, deuterium, and deuterium 
compounds or in any of the components described in this appendix.

[79 FR 39298, July 10, 2014]



 Sec. Appendix L to Part 110--Illustrative List of Byproduct Materials 
        Under NRC Export/Import Licensing Authority a

Actinium 225 (Ac 225)
Actinium 227 (Ac 227)
Actinium 228 (Ac 228)
Americium 241 (Am 241)
Americium 242m (Am 242m)
Americium 242 (Am 242)
Americium 243 (Am 243)
Antimony 124 (Sb 124)
Antimony 125 (Sb 125)
Antimony 126 (Sb 126)
Arsenic 73 (As 73)
Arsenic 74 (As 74)
Arsenic 76 (As 76)
Arsenic 77 (As 77)
Barium 131 (Ba 131)
Barium 133 (Ba 133)
Barium 140 (Ba 140)
Bismuth 207 (Bi 207)
Bismuth 210 (Bi 210)
Bromine 82 (Br 82)
Cadmium 109 (Cd 109)
Cadmium 113 (Cd 113)
Cadmium 115m (Cd 115m)
Cadmium 115 (Cd 115)
Calcium 45 (Ca 45)
Calcium 47 (Ca 47)
Californium 248 (Cf 248)
Californium 249 (Cf 249)
Californium 250 (Cf 250)
Californium 251 (Cf 251)
Californium 252 (Cf 252)
Californium 253 (Cf 253)
Californium 254 (Cf 254)
Carbon 11 (C 11)
Carbon 14 (C 14)
Cerium 141 (Ce 141)
Cerium 143 (Ce 143)
Cerium 144 (Ce 144)
Cesium 129 (Cs 129)
Cesium 131 (Cs 131)
Cesium 134m (Cs 134m)
Cesium 134 (Cs 134)
Cesium 135 (Cs 135)
Cesium 136 (Cs 136)
Cesium 137 (Cs 137)
Chlorine 36 (Cl 36)
Chlorine 38 (Cl 38)
Chromium 51 (Cr 51)
Cobalt 57 (Co 57)
Cobalt 58m (Co 58m)
Cobalt 58 (Co 58)
Cobalt 60 (Co 60)
Copper 64 (Cu 64)
Curium 240 (Cm 240)
Curium 241 (Cm 241)
Curium 242 (Cm 242)
Curium 243 (Cm 243)
    \a\ Any accelerator-produced material produced, extracted, or 
converted for use for a commercial, medical, or research activity.

[[Page 747]]

Curium 244 (Cm 244)
Curium 245 (Cm 245)
Curium 247 (Cm 247)
Dysprosium 165 (Dy 165)
Dysprosium 166 (Dy 166)
Einsteinium 252 (Es 252)
Einsteinium 253 (Es 253)
Einsteinium 254 (Es 254)
Einsteinium 255 (Es 255)
Erbium 169 (Er 169)
Erbium 171 (Er 171)
Europium 152 (Eu 152)
Europium 152 9.2 h
 (Eu 152 9.2 h)
Europium 152 13 yr
 (Eu 152 13 yr)
Europium 154 (Eu 154)
Europium 155 (Eu 155)
Fermium 257 (Fm 257)
Fluorine 18 (F 18)
Gadolinium 148 (Gd 148)
Gadolinium 153 (Gd 153)
Gadolinium 159 (Gd 159)
Gallium 67 (Ga 67)
Gallium 72 (Ga 72)
Germanium 68 (Ge 68)
Germanium 71 (Ge 71)
Gold 195 (Au 195)
Gold 198 (Au 198)
Gold 199 (Au 199)
Hafnium 172 (Hf 172)
Hafnium 181 (Hf 181)
Holmium 166m (Ho 166m)
Holmium 166 (Ho 166)
Hydrogen 3 (H 3)
Indium 111 (In 111)
Indium 113m (In 113m)
Indium 114m (In 114m)
Indium 115m (In 115m)
Indium 115 (In 115)
Iodine 123 (I 123)
Iodine 125 (I 125)
Iodine 126 (I 126)
Iodine 129 (I 129)
Iodine 131 (I 131)
Iodine 132 (I 132)
Iodine 133 (I 133)
Iodine 134 (I 134)
Iodine 135 (I 135)
Iridium 192 (Ir 192)
Iridium 194 (Ir 194)
Iron 52 (Fe 52)
Iron 55 (Fe 55)
Iron 59 (Fe 59)
Krypton 85 (Kr 85)
Krypton 87 (Kr 87)
Lanthanum 140 (La 140)
Lead 210 (Pb 210)
Lutetium 177 (Lu 177)
Manganese 52 (Mn 52)
Manganese 54 (Mn 54)
Manganese 56 (Mn 56)
Mendelevium 258 (Md 258)
Mercury 197m (Hg 197m)
Mercury 197 (Hg 197)
Mercury 203 (Hg 203)
Molybdenum 99 (Mo 99)
Neodymium 147 (Nd 147)
Neodymium 149 (Nd 149)
Neptunium 235 (Np 235)
Neptunium 237 (Np 237)
Nickel 59 (Ni 59)
Nickel 63 (Ni 63)
Nickel 65 (Ni 65)
Niobium 93m (Nb 93m)
Niobium 94 (Nb 94)
Niobium 95 (Nb 95)
Niobium 97 (Nb 97)
Nitrogen 13 (N 13)
Osmium 185 (Os 185)
Osmium 191m (Os 191m)
Osmium 191 (Os 191)
Osmium 193 (Os 193)
Oxygen 15 (O 15)
Palladium 103 (Pd 103)
Palladium 109 (Pd 109)
Phosphorus 32 (P 32)
Phosphorus 33 (P 33)
Platinum 191 (Pt 191)
Platinum 193m (Pt 193m)
Platinum 193 (Pt 193)
Platinum 197m (Pt 197m)
Platinum 197 (Pt 197)
Polonium 208 (Po 208)
Polonium 209 (Po 209)
Polonium 210 (Po 210)
Potassium 42 (K 42)
Potassium 43 (K 43)
Praseodymium 142 (Pr 142)
Praseodymium 143 (Pr 143)
Promethium 145 (Pm 145)
Promethium 147 (Pm 147)
Promethium 149 (Pm 149)
Radium 223 (Ra 223)
Radium 226 (Ra 226) \b\
Rhenium 186 (Re 186)
Rhenium 188 (Re 188)
Rhodium 103m (Rh 103m)
Rhodium 105 (Rh 105)
Rubidium 81 (Rb 81)
Rubidium 86 (Rb 86)
Rubidium 87 (Rb 87)
Ruthenium 97 (Ru 97)
Ruthenium 103 (Ru 103)
Ruthenium 105 (Ru 105)
Ruthenium 106 (Ru 106)
Samarium 151 (Sm 151)
Samarium 153 (Sm 153)
Scandium 46 (Sc 46)
Scandium 47 (Sc 47)
Scandium 48 (Sc 48)
Selenium 75 (Se 75)
Silicon 31 (Si 31)
Silver 105 (Ag 105)
Silver 110m (Ag 110m)
Silver 111 (Ag 111)
Sodium 22 (Na 22)
Sodium 24 (Na 24)
Strontium 85 (Sr 85)
Strontium 89 (Sr 89)
Strontium 90 (Sr 90)
Strontium 91 (Sr 91)
Strontium 92 (Sr 92)
Sulphur 35 (S 35)
Tantalum 182 (Ta 182)
Technetium 96 (Tc 96)
Technetium 97m (Tc 97m)
Technetium 97 (Tc 97)
Technetium 99m (Tc 99m)
Technetium 99 (Tc 99)
Tellurium 125m (Te 125m)
Tellurium 127m (Te 127m)
Tellurium 127 (Te 127)
Tellurium 129m (Te 129m)
Tellurium 129 (Te 129)
Tellurium 131m (Te 131m)
Tellurium 132 (Te 132)
Terbium 160 (Tb 160)
Thallium 200 (Tl 200)
Thallium 201 (Tl 201)
Thallium 202 (Tl 202)
Thallium 204 (Tl 204)
Thulium 170 (Tm 170)
Thulium 171 (Tm 171)
Tin 113 (Sn 113)
Tin 123 (Sn 123)
Tin 125 (Sn 125)
Tin 126 (Sn 126)
Titanium 44 (Ti 44)
Tritium (H3)
Tungsten 181 (W 181)
Tungsten 185 (W 185)
Tungsten 187 (W 187)
Vanadium 48 (V 48)
Xenon 131m (Xe 131m)
Xenon 133 (Xe 133)
Xenon 135 (Xe 135)
Ytterbium 175 (Yb 175)
Yttrium 87 (Y 87)
Yttrium 88 (Y 88)
Yttrium 90 (Y 90)
Yttrium 91 (Y 91)
Yttrium 92 (Y 92)
Yttrium 93 (Y 93)
Zinc 65 (Zn 65)
Zinc 69m (Zn 69m)
Zinc 69 (Zn 69)
Zirconium 93 (Zr 93)
Zirconium 95 (Zr 95)
Zirconium 97 (Zr 97)
    \b\ Discrete sources of radium-226 (Ra-226).

[58 FR 13005, Mar. 9, 1993, as amended at 59 FR 48998, Sept. 26, 1994. 
Redesignated and amended at 61 FR 35603, 35607, July 8, 1996; 65 FR 
70292, Nov. 22, 2000; 71 FR 20339, Apr. 20, 2006; 75 FR 44093, July 28, 
2010]

[[Page 748]]



   Sec. Appendix M to Part 110--Categorization of Nuclear Material \d\

                                         [From IAEA INFCIRC/225, Rev. 1]
----------------------------------------------------------------------------------------------------------------
                                                                                Category
            Material                      Form        ----------------------------------------------------------
                                                              I                  II                III \e\
----------------------------------------------------------------------------------------------------------------
1. Plutonium \a\................  Unirradiated \b\...  2 kg or more...  Less than 2 kg but   500 g or less.
                                                                         more than 500 g.
2. Uranium-235 \c\..............  Unirradiated: \b\..
                                   Uranium enriched    5 kg or more...  Less than 5 kg but   1 kg or less.
                                   to 20 pct U \235\                     more than 1 kg.
                                   or more.
                                   Uranium enriched    ...............  10 kg or more......  Less than 10 kg.
                                   to 10 pct U \235\
                                   but less than 20
                                   pct.
                                   Uranium enriched    ...............  ...................  10 kg or more.
                                   above natural, but
                                   less than 10 pct U
                                   \235\.
3. Uranium-233..................  Unirradiated \b\...  2 kg or more...  Less than 2 kg but   500 g or less.
                                                                         more than 500 g.
----------------------------------------------------------------------------------------------------------------
\a\ All plutonium except that with isotopic concentration exceeding 80 pct in plutonium-238.
\b\ Material not irradiated in a reactor or material irradiated in a reactor but with a radiation level equal to
  or less than 100 rd/h at 1 m unshielded.
\c\ Natural uranium, depleted uranium, thorium and quantities of uranium enriched to less than 10% not falling
  into Category III should be protected in accordance with prudent management practice.
\d\ Irradiated fuel should be protected as category I, II, or III nuclear material depending on the category of
  the fresh fuel. However, fuel which by virtue of its original fissile material content is included as category
  I or II before irradiation should only be reduced one category level, while the radiation level from the fuel
  exceeds 100 rd/h at 1 m unshielded.
\e\ Physical security determinations will not be required for 15 g or less of plutonium, uranium-233 or high-
  enriched uranium, or for 1 kg or less of uranium with an enrichment between 10 and 20 pct in uranium-235.


(Sec. 161, as amended, Pub. L. 83-703, 68 Stat. 948 (42 U.S.C. 2201); 
sec. 201, as amended, Pub. L. 93-438, 88 Stat. 1243 (42 U.S.C. 5841))

[43 FR 21641, May 19, 1978. Redesignated and amended at 49 FR 47204, 
Dec. 3, 1984. Further redesignated at 55 FR 30450, July 26, 1990; 58 FR 
13005, Mar. 9, 1993; 61 FR 35603, July 8, 1996]



   Sec. Appendix N to Part 110--Illustrative List of Lithium Isotope 
Separation Facilities, Plants and Equipment Under NRC's Export Licensing 
                                Authority

    a. Facilities or plants for the separation of lithium isotopes.
    b. Equipment for the separation of lithium isotopes, such as:
    (1) Packed liquid-liquid exchange columns especially designed for 
lithium amalgams;
    (2) Mercury and/or lithium amalgam pumps;
    (3) Lithium amalgam electrolysis cells;
    (4) Evaporators for concentrated lithium hydroxide solution.
    c. Any other components especially designed or prepared for use in a 
reprocessing plant or in any of the components described in this 
appendix.

[65 FR 70292, Nov. 22, 2000, as amended at 79 FR 39299, July 10, 2014]



     Sec. Appendix O to Part 110--Illustrative List of Fuel Element 
Fabrication Plant Equipment and Components Under NRC's Export Licensing 
                                Authority

    Note Nuclear fuel elements are manufactured from source or special 
nuclear material. For oxide fuels, the most common type of fuel 
equipment for pressing pellets, sintering, grinding and grading will be 
present. Mixed oxide fuels are handled in glove boxes (or equivalent 
containment) until they are sealed in the cladding. In all cases, the 
fuel is hermetically sealed inside a suitable cladding which is designed 
to be the primary envelope encasing the fuel so as to provide suitable 
performance and safety during reactor operation. Also, in all cases, 
precise control of processes, procedures and equipment to extremely high 
standards is necessary in order to ensure predictable and safe fuel 
performance.

    (a) Items that are considered especially designed or prepared for 
the fabrication of fuel elements include equipment that:
    (1) Normally comes in direct contact with, or directly processes or 
controls, the production flow of nuclear material;
    (2) Seals the nuclear material within the cladding;
    (3) Checks the integrity of the cladding or the seal;
    (4) Checks the finished treatment of the sealed fuel; or
    (5) Is used for assembling reactor fuel elements.
    (b) This equipment or systems of equipment may include, for example:
    (1) Fully automatic pellet inspection stations especially designed 
or prepared for checking final dimensions and surface defects of fuel 
pellets;

[[Page 749]]

    (2) Automatic welding machines especially designed or prepared for 
welding end caps onto the fuel pins (or rods);
    (3) Automatic test and inspection stations especially designed or 
prepared for checking the integrity of completed fuel pins (or rods). 
This item typically includes equipment for:
    (i) X-ray examination of pin (or rod) end cap welds;
    (ii) Helium leak detection from pressurized pins (or rods); and
    (iii) Gamma-ray scanning of the pins (or rods) to check for correct 
loading of the fuel pellets inside.
    (4) Systems especially designed or prepared to manufacture nuclear 
fuel cladding.
    (c) Any other components especially designed or prepared for use in 
a fuel element fabrication plant or in any of the components described 
in this appendix.

[79 FR 39299, July 10, 2014]



   Sec. Appendix P to Part 110--Category 1 and 2 Radioactive Material

                                   Table 1--Import and Export Threshold Limits
----------------------------------------------------------------------------------------------------------------
                                                      Category 1                          Category 2
                                         -----------------------------------------------------------------------
          Radioactive material             Terabecquerels                      Terabecquerels
                                                (TBq)        Curies (Ci) \1\        (TBq)        Curies (Ci) \1\
----------------------------------------------------------------------------------------------------------------
Americium-241...........................                60             1,600               0.6                16
Americium-241/Be........................                60             1,600               0.6                16
Californium-252.........................                20               540               0.2               5.4
Curium-244..............................                50             1,400               0.5                14
Cobalt-60...............................                30               810               0.3               8.1
Cesium-137..............................               100             2,700               1.0                27
Gadolinium-153..........................             1,000            27,000              10.0               270
Iridium-192.............................                80             2,200               0.8                22
Plutonium-238\2\........................                60             1,600               0.6                16
Plutonium-239/Be \2\....................                60             1,600               0.6                16
Promethium-147..........................            40,000         1,100,000               400            11,000
Radium-226 \a\..........................                40             1,100               0.4                11
Selenium-75.............................               200             5,400               2.0                54
Strontium-90 (Y-90).....................             1,000            27,000              10.0               270
Thulium-170.............................            20,000           540,000               200             5,400
Ytterbium-169...........................               300             8,100               3.0               81
----------------------------------------------------------------------------------------------------------------
\1\ The values to be used to determine whether a license is required are given in TBq. Curie (Ci) values are
  provided for practical usefulness only and are rounded after conversion.
\2\ The limits for Pu-238 and Pu-239/Be in this table apply for imports to the U.S. The limits for exports of Pu-
  238 and Pu-239/Be can be found in Sec. 110.21.
\a\ Discrete sources of radium-226.

  Calculation of Shipments Containing Multiple Sources or Radionuclides

    The ``sum of fractions'' methodology for evaluating combinations of 
radionuclides being transported, is to be used when import or export 
shipments contain multiple sources or multiple radionuclides. The 
threshold limit values used in a sum of the fractions calculation must 
be the metric values (i.e., TBq).
    I. If multiple sources and/or multiple radionuclides are present in 
an import or export shipment, the sum of the fractions of the activity 
of each radionuclides must be determined to verify the shipment is less 
than the Category 1 or 2 limits of Table 1, as appropriate. If the 
calculated sum of the fractions ratio, using the following equation, is 
greater than or equal to 1.0, then the import or export shipment exceeds 
the threshold limits of Table 1 and the applicable security provisions 
of this part apply.
    II. Use the equation below to calculate the sum of the fractions 
ratio by inserting the actual activity of the applicable radionuclides 
or of the individual sources (of the same radionuclides) in the 
numerator of the equation and the corresponding threshold activity limit 
from the Table 1 in the denominator of the equation. Ensure the 
numerator and denominator values are in the same units and all 
calculations must be performed using the TBq (i.e., metric) values of 
Table 1.

R1 = activity for radionuclides or source number 1
R2 = activity for radionuclides or source number 2
RN = activity for radionuclides or source number n
AR1 = activity limit for radionuclides or source number 1
AR2 = activity limit for radionuclides or source number 2
ARN = activity limit for radionuclides or source number n

[[Page 750]]

[GRAPHIC] [TIFF OMITTED] TR01JY05.055


[70 FR 37993, July 1, 2005, as amended at 71 FR 20339, Apr. 20, 2006; 82 
FR 52826, Nov. 15, 2017]



PART 140_FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS
--Table of Contents



                      Subpart A_General Provisions

Sec.
140.1 Purpose.
140.2 Scope.
140.3 Definitions.
140.4 Interpretations.
140.5 Communications.
140.6 Reports.
140.7 Fees.
140.8 Specific exemptions.
140.9 Modification of indemnity agreements.
140.9a Information collection requirements: OMB approval.

 Subpart B_Provisions Applicable Only to Applicants and Licensees Other 
      Than Federal Agencies and Nonprofit Educational Institutions

140.10 Scope.
140.11 Amounts of financial protection for certain reactors.
140.12 Amount of financial protection required for other reactors.
140.13 Amount of financial protection required of certain holders of 
          construction permits and combined licenses under 10 CFR part 
          52.
140.13a Amount of financial protection required for plutonium processing 
          and fuel fabrication plants.
140.13b Amount of liability insurance required for uranium enrichment 
          facilities.
140.14 Types of financial protection.
140.15 Proof of financial protection.
140.16 Commission review of proof of financial protection.
140.17 Special provisions applicable to licensees furnishing financial 
          protection in whole or in part in the form of liability 
          insurance.
140.18 Special provisions applicable to licensees furnishing financial 
          protection in whole or in part in the form of adequate 
          resources.
140.19 Failure by licensees to maintain financial protection.
140.20 Indemnity agreements and liens.
140.21 Licensee guarantees of payment of deferred premiums.
140.22 Commission guarantee and reimbursement agreements.

        Subpart C_Provisions Applicable Only to Federal Agencies

140.51 Scope.
140.52 Indemnity agreements.

     Subpart D_Provisions Applicable Only to Nonprofit Educational 
                              Institutions

140.71 Scope.
140.72 Indemnity agreements.

               Subpart E_Extraordinary Nuclear Occurrences

140.81 Scope and purpose.
140.82 Procedures.
140.83 Determination of extraordinary nuclear occurrence.
140.84 Criterion I--Substantial discharge of radioactive material or 
          substantial radiation levels offsite.
140.85 Criterion II--Substantial damages to persons offsite or property 
          offsite.

                          Subpart F_Violations

140.87 Violations.
140.89 Criminal penalties.

                         Appendixes to Part 140

140.91 Appendix A--Form of nuclear energy liability policy for 
          facilities.
140.92 Appendix B--Form of indemnity agreement with licensees furnishing 
          insurance policies as proof of financial protection.
140.93 Appendix C--Form of indemnity agreement with licensees furnishing 
          proof of financial protection in the form of licensee's 
          resources.
140.94 Appendix D--Form of indemnity agreement with Federal agencies.
140.95 Appendix E--Form of indemnity agreement with nonprofit 
          educational institutions.
140.96 Appendix F--Indemnity locations.
140.107 Appendix G--Form of indemnity agreement with licensees 
          processing plutonium for use in plutonium processing and fuel 
          fabrication plants and furnishing insurance policies as proof 
          of financial protection.
140.108 Appendix H--Form of indemnity agreement with licensees 
          possessing plutonium for use in plutonium processing and fuel 
          fabrication plants and furnishing proof of financial 
          protection in the form of the licensee's resources.
140.109 Appendix I.

    Authority: Atomic Energy Act of 1954, secs. 161, 170, 223, 234 (42 
U.S.C. 2201, 2210, 2273, 2282); Energy Reorganization Act of

[[Page 751]]

1974, secs. 201, 202 (42 U.S.C. 5841, 5842); 44 U.S.C. 3504 note.

    Source: 25 FR 2944, Apr. 7, 1960, unless otherwise noted.



                      Subpart A_General Provisions



Sec. 140.1  Purpose.

    The regulations in this part are issued to provide appropriate 
procedures and requirements for determining:
    (a) The financial protection required of licensees and for the 
indemnification and limitation of liability of certain licensees and 
other persons pursuant to section 170 of the Atomic Energy Act of 1954, 
as amended; and
    (b) The liability insurance required of uranium enrichment facility 
licensees pursuant to section 193 of the Atomic Energy Act of 1954, as 
amended.

[57 FR 18394, Apr. 30, 1992]



Sec. 140.2  Scope.

    (a) The regulations in this part apply:
    (1) To each person who is an applicant for or holder of a license 
issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, 
and
    (2) With respect to an extraordinary nuclear occurrence, to each 
person who is an applicant for or holder of a license to operate a 
production facility or a utilization facility (including an operating 
license issued under part 50 of this chapter and a combined license 
under part 52 of this chapter), and to other persons indemnified with 
respect to the involved facilities.
    (3) To each person licensed pursuant to part 70 of this chapter to 
possess and use plutonium in a plutonium processing and fuel fabrication 
plant.
    (4) To each person licensed pursuant to parts 40 and 70 of this 
chapter to construct and operate a uranium enrichment facility.
    (b)(1) Subpart B of this part does not apply to any person subject 
to subparts C or D of this part. Subpart C of this part applies only to 
persons found by the Commission to be Federal agencies. Subpart D of 
this part applies only to persons found by the Commission to be 
nonprofit educational institutions with respect to licenses and 
applications for licenses for the conduct of educational activities.
    (2) Any applicant or licensee subject to this part may apply for a 
finding that such applicant or licensee is subject to the provisions of 
subparts C or D of this part. The application should state the grounds 
for the requested finding. Any application for a finding pursuant to 
this paragraph may be included in an application for license.
    (c) Subpart E of this part sets forth the procedures the Commission 
will follow and the criteria the Commission will apply in making a 
determination as to whether or not there has been an extraordinary 
nuclear occurrence. The form of nuclear energy liability policy for 
facilities (appendix A) and the forms of indemnity agreements with 
licensees (appendices B, C, D, and E) include provisions requiring the 
waiver of certain defenses with respect to an extraordinary nuclear 
occurrence. These provisions and subpart E are incorporated in this part 
pursuant to Pub. L. 89-645 (80 Stat. 891). They provide additional 
assurance of prompt compensation under available indemnity and 
underlying financial protection for injury or damage resulting from the 
hazardous properties of radioactive materials or radiation, and they in 
no way detract from the protection to the public otherwise provided 
under this part.

[25 FR 2944, Apr. 7, 1960, as amended at 33 FR 15998, Oct. 31, 1968; 42 
FR 48, Jan. 3, 1977; 56 FR 64980, Dec. 13, 1991; 57 FR 18394, Apr. 30, 
1992; 72 FR 49564, Aug. 28, 2007]



Sec. 140.3  Definitions.

    As used in this part,
    (a) Act means the Atomic Energy Act of 1954 (68 Stat. 919) including 
any amendments thereto.
    (b) Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives.
    (c) Federal agency means a Government agency such that any liability 
in tort based on the activities of such agency would be satisfied by 
funds appropriated by the Congress and paid out of the United States 
Treasury.

[[Page 752]]

    (d) Financial protection means the ability to respond in damages for 
public liability and to meet the cost of investigating and defending 
claims and settling suits for such damages.
    (e) Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the Government.
    (f) Nuclear reactor means any apparatus, other than an atomic 
weapon, designed or used to sustain nuclear fission in a self-supporting 
chain reaction.
    (g) Person means: (1) Any individual, corporation, partnership, 
firm, association, trust, estate, public or private institution, group, 
Government agency other than the Commission or the Department, except 
that the Department shall be considered a person within the meaning of 
the regulations in this part to the extent that its facilities and 
activities are subject to the licensing and related regulatory authority 
of the Commission pursuant to section 202 of the Energy Reorganization 
Act of 1974 (88 Stat. 1244), any State or any political subdivision 
thereof, or any political entity within a State, any foreign government 
or nation or any political subdivision of any such government or nation, 
or other entity; and (2) any legal successor, representative, agent, or 
agency of the foregoing.
    (h) Plutonium processing and fuel fabrication plant means a plant in 
which the following operations or activities are conducted:
    (1) Operations for manufacture of reactor fuel containing plutonium, 
where the license or licenses authorize the possession of either five or 
more kilograms of plutonium, excluding that contained in sealed sources 
and welded or otherwise sealed unirradiated or irradiated fuel rods, at 
the site of the plant or authorize the processing of one or more 
kilograms of plutonium, excluding that contained in sealed sources and 
welded or otherwise sealed unirradiated or irradiated fuel rods, at the 
plant, including any of the following processes: (i) Preparation of fuel 
material; (ii) formation of fuel material into desired shapes; (iii) 
application of protective cladding; (iv) recovery of scrap material; and 
(v) storage associated with such operations; or
    (2) Research and development activities involving any of the 
operations described in paragraph (h)(1) of this section, except for 
research and development activities where the operator is licensed to 
possess or use plutonium in amounts less than those specified in 
paragraph (h)(1).
    (i) Source material means source material as defined in the 
regulations contained in part 40 of this chapter.
    (j) Special nuclear material means: (1) Plutonium, uranium 233, 
uranium enriched in the isotope 233 or in the isotope 235, and any other 
material which the Commission, pursuant to the provisions of section 51 
of the Act, determines to be special nuclear material, but does not 
include source material; or (2) any material artifically enriched by any 
of the foregoing, but does not include source material.
    (k) Testing reactor means a nuclear reactor which is of a type 
described in Sec. 50.21(c) of this chapter and for which an application 
has been filed for a license authorizing operation at:
    (1) A thermal power level in excess of 10 megawatts; or
    (2) A thermal power level in excess of 1 megawatt, if the reactor is 
to contain:
    (i) A circulating loop through the core in which the applicant 
proposes to conduct fuel experiments; or
    (ii) A liquid fuel loading; or
    (iii) An experimental facility in the core in excess of 16 square 
inches in cross-section.
    (l) Department means the Department of Energy established by the 
Department of Energy Organization Act (Pub. L. 95-91, 91 Stat. 565, 42 
U.S.C. 7101 et seq.), to the extent that the Department, or its duly 
authorized representatives, exercises functions formerly vested in the 
U.S. Atomic Energy Commission, its Chairman, members, officers and 
components and transferred to the U.S. Energy Research and Development 
Administration and to the Administrator thereof pursuant to sections 104 
(b), (c) and (d) of the Energy

[[Page 753]]

Reorganization Act of 1974 (Pub. L. 93-438, 88 Stat. 1233 at 1237, 42 
U.S.C. 5814) and retransferred to the Secretary of Energy pursuant to 
section 301(a) of the Department of Energy Organization Act (Pub. L. 95-
91, 91 Stat. 565 at 577-578, 42 U.S.C. 7151).
    (m) Uranium enrichment facility means:
    (1) Any facility used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or
    (2) Any equipment or device, or important component part especially 
designed for such equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.

[25 FR 2944, Apr. 7, 1960, as amended at 40 FR 8793, Mar. 3, 1975; 42 FR 
48, Jan. 3, 1977; 45 FR 14201, Mar. 5, 1980; 57 FR 18394, Apr. 30, 1992]



Sec. 140.4  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretations of the meaning of the regulations in this part by any 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 140.5  Communications.

    Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed to: ATTN: Document Control Desk, 
Director, Office of Nuclear Reactor Regulation, Director, Office of New 
Reactors, or Director, Office of Nuclear Material Safety and Safeguards, 
as appropriate, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; by hand delivery to the NRC's offices at 11555 Rockville 
Pike, Rockville, Maryland; or, where practicable, by electronic 
submission, for example, via Electronic Information Exchange, or CD-ROM. 
Electronic submissions must be made in a manner that enables the NRC to 
receive, read, authenticate, distribute, and archive the submission, and 
process and retrieve it a single page at a time. Detailed guidance on 
making electronic submissions can be obtained by visiting the NRC's Web 
site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[73 FR 5726, Jan. 31, 2008, as amended at 74 FR 62686, Dec. 1, 2009; 79 
FR 75742, Dec. 19, 2014; 80 FR 74982, Dec. 1, 2015]



Sec. 140.6  Reports.

    (a) In the event of bodily injury or property damage arising out of 
or in connection with the possession or use of the radioactive material 
at the location or in the course of transportation, or in the event any 
claim is made therefor, written notice containing particulars sufficient 
to identify the licensee and reasonably obtainable information with 
respect to the time, place, and circumstances thereof, or to the nature 
of the claim, shall be furnished by or for the licensee to the Director, 
Office of Nuclear Reactor Regulation, Director, Office of New Reactors, 
or Director, Office of Nuclear Material Safety and Safeguards, as 
appropriate, using an appropriate method listed in Sec. 140.5, but in 
any case as promptly as practicable. The terms the radioactive material, 
the location, and in the course of transportation as used in this 
section shall have the meanings defined in the applicable indemnity 
agreement between the licensee and the Commission.
    (b) The Commission may require any person subject to this part to 
keep such records and furnish such reports to the Commission as the 
Commission deems necessary for the administration of the regulations in 
this part.

[25 FR 2944, Apr. 7, 1960, as amended at 41 FR 16447, Apr. 19, 1976; 42 
FR 49, Jan. 3, 1977; 68 FR 58824, Oct. 10, 2003; 73 FR 5726, Jan. 31, 
2008; 79 FR 75742, Dec. 19, 2014]



Sec. 140.7  Fees.

    (a)(1) Each reactor licensee shall pay a fee to the Commission based 
on the following schedule:

[[Page 754]]

    (i) For indemnification from $500 million to $400 million inclusive, 
a fee of $30 per year per thousand kilowatts of thermal capacity 
authorized in the license;
    (ii) For indemnification from $399 million to $300 million 
inclusive, a fee of $24 per year per thousand kilowatts of thermal 
capacity authorized in the license;
    (iii) For indemnification from $299 million to $200 million 
inclusive, a fee of $18 per year per thousand kilowatts of thermal 
capacity authorized in the license;
    (iv) For indemnification from $199 million to $100 million 
inclusive, a fee of $12 per year per thousand kilowatts of thermal 
capacity authorized in the license; and
    (v) For indemnification from $99 million to $1 million inclusive, a 
fee of $6 per year per thousand kilowatts of thermal capacity authorized 
in the license.
    (2) No fee will be less than $100 per annum for any nuclear reactor. 
This fee is for the period beginning with the date on which the 
applicable indemnity agreement is effective. The various levels of 
indemnity fees are set forth in the schedule in this paragraph. The 
amount of indemnification for determining indemnity fees will be 
computed by subtracting from the statutory limit of liability the amount 
of financial protection required of the licensee. In the case of 
licensees subject to the provision of Sec. 140.11(a)(4), this total 
amount will be the amount, as determined by the Commission, of the 
financial protection available to licensees at the close of the calendar 
year preceding the one in which the fee becomes due. For those instances 
in which a certified financial statement is provided as a guarantee of 
payment of deferred premiums in accordance with Sec. 140.21(e), a fee 
of $1,000 or the indemnity fee, whichever is greater, is required.
    (b) Where a licensee manufactures a number of nuclear reactors each 
having a power level not exceeding 3\1/3\ megawatts, for sale to others 
and operates them at the licensee's location temporarily prior to 
delivery, the licensee shall report to the Commission the maximum number 
of such reactors to be operated at that location at any one time. In 
such cases, the fee shall equal $100 multiplied by the number of 
reactors reported by the licensee. In the event the number of reactors 
operated at any one time exceed the estimate so reported, the licensee 
shall report the additional number of reactors to the Commission and 
additional charges will be made. If experience shows that less than the 
estimated number of reactors have been operated, appropriate adjustment 
in subsequent bills will be made by the Commission.
    (c) Each person licensed to possess and use plutonium in a plutonium 
processing and fuel fabrication plant shall pay to the Commission a fee 
of $5,000 per year for indemnification. This fee is for the period 
beginning with the date on which the applicable indemnity agreement is 
effective.
    (d) Indemnity fee payments, made payable to the U.S. Nuclear 
Regulatory Commission, are to be made in U.S. funds by check, draft, 
money order, credit card, or electronic funds transfer such as ACH 
(Automated Clearing House) using EDI (Electronic Data Interchange). 
Federal agencies may also make payments by the On-Line Payment and 
Collections System (OPAC's). Where specific payment instructions are 
provided on the invoices, payment should be made accordingly, e.g. 
invoices of $5,000 or more should be paid via ACH through NRC's Lockbox 
Bank at the address indicated on the invoice. Credit card payments 
should be made up to the limit established by the credit card bank, in 
accordance with specific instructions provided with the invoices, to the 
Lockbox Bank designated for credit card payments.

[25 FR 2944, Apr. 7, 1960, as amended at 42 FR 49, Jan. 3, 1977; 63 FR 
31851, June 10, 1998]



Sec. 140.8  Specific exemptions.

    The Commission may, upon application of any interested person or 
upon its own initiative, grant such exemptions from the requirements of 
the regulations in this part as it determines are authorized by law and 
are otherwise in the public interest.

[34 FR 19546, Dec. 11, 1969]

[[Page 755]]



Sec. 140.9  Modification of indemnity agreements.

    The Commission will publish in the Federal Register a notice of its 
intent to enter into an indemnity agreement, or agreement amending an 
indemnity agreement, which contains provisions different from the form 
of the applicable indemnity agreement set forth in the appendices to 
this part, as such appendices may be amended from time to time.

[48 FR 1030, Jan. 10, 1983]



Sec. 140.9a  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0039.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 140.6, 140.7, 140.13, 140.13a, 140.13b, 
140.15, 140.17, 140.20, and 140.21.

[62 FR 52190, Oct. 6, 1997]



 Subpart B_Provisions Applicable Only to Applicants and Licensees Other 
      Than Federal Agencies and Nonprofit Educational Institutions



Sec. 140.10  Scope.

    This subpart applies to each person who is an applicant for or 
holder of a license issued under 10 CFR parts 50 or 54 to operate a 
nuclear reactor, or is the applicant for or holder of a combined license 
issued under parts 52 or 54 of this chapter, except licenses held by 
persons found by the Commission to be Federal agencies or nonprofit 
educational institutions licensed to conduct educational activities. 
This subpart also applies to persons licensed to possess and use 
plutonium in a plutonium processing and fuel fabrication plant.

[72 FR 49564, Aug. 28, 2007]



Sec. 140.11  Amounts of financial protection for certain reactors.

    (a) Each licensee is required to have and maintain financial 
protection:
    (1) In the amount of $1,000,000 for each nuclear reactor he is 
authorized to operate at a thermal power level not exceeding ten 
kilowatts;
    (2) In the amount of $1,500,000 for each nuclear reactor he is 
authorized to operate at a thermal power level in excess of ten 
kilowatts but not in excess of one megawatt;
    (3) In the amount of $2,500,000 for each nuclear reactor other than 
a testing reactor or a reactor licensed under section 104b of the Act 
which he is authorized to operate at a thermal power level exceeding one 
megawatt but not in excess of ten megawatts; and
    (4) In an amount equal to the sum of $450,000,000 and the amount 
available as secondary financial protection (in the form of private 
liability insurance available under an industry retrospective rating 
plan providing for deferred premium charges equal to the pro rata share 
of the aggregate public liability claims and costs, excluding costs 
payment of which is not authorized by section 170o.(1)(D) of the Act, in 
excess of that covered by primary financial protection) for each nuclear 
reactor which is licensed to operate and which is designed for the 
production of electrical energy and has a rated capacity of 100,000 
electrical kilowatts or more: Provided, however, that under such a plan 
for deferred premium charges for each nuclear reactor that is licensed 
to operate, no more than $121,255,000 with respect to any nuclear 
incident (plus any surcharge assessed under subsection 170o.(1)(E) of 
the Act) and no more than $18,963,000 per incident within one calendar 
year shall be charged. Except that, where a person is authorized to 
operate a combination of 2 or more nuclear reactors located at a single 
site, each of which has a rated capacity of 100,000 or more electrical 
kilowatts but not more than 300,000 electrical kilowatts with a combined 
rated capacity of not more than

[[Page 756]]

1,300,000 electrical kilowatts, each such combination of reactors shall 
be considered to be a single nuclear reactor for the sole purpose of 
assessing the applicable financial protection required under this 
section.
    (b) In any case where a person is authorized under parts 50, 52, or 
54 of this chapter to operate two or more nuclear reactors at the same 
location, the total primary financial protection required of the 
licensee for all such reactors is the highest amount which would 
otherwise be required for any one of those reactors; provided, that such 
primary financial protection covers all reactors at the location.

[25 FR 2944, Apr. 7, 1960]

    Editorial Note: For Federal Register citations affecting Sec. 
140.11, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.12  Amount of financial protection required for other 
reactors.

    (a) Each licensee is required to have and maintain financial 
protection for each nuclear reactor for which the amount of financial 
protection is not determined in Sec. 140.11, in an amount determined 
pursuant to the formula and other provisions of this section: Provided, 
That in no event shall the amount of financial protection required for 
any nuclear reactor under this section be less than $4,500,000 or more 
than $74,000,000.
    (b)(1) The formula is:

x = B times P

    (2) In the formula:

x = Amount of financial protection in dollars.
B = Base amount of financial protection.
P = Population factor.

    (3) The base amount of financial protection is equal to $185 times 
the maximum power level, expressed in thermal kilowatts, as authorized 
by the applicable license.
    (4) The population factor (P) shall be determined as follows:
    (i) Step 1. The area to be considered includes all minor civil 
divisions (as shown in the 1950 Census of Population, Bureau of the 
Census, or later data available from the Bureau) which are wholly or 
partly within a circle with the facility at its center and having a 
radius in miles equal to the square root of the maximum authorized power 
level in thermal megawatts.
    (ii) Step 2. Identify all minor civil divisions according to the 
same census which are in whole or in part within the circle determined 
in Step 1. Determine the population of each such minor civil division 
(according to the same census or later data available from the Bureau of 
the Census). For each minor civil division, divide its population by the 
square of the estimated distance to the nearest mile from the reactor to 
the geographic center of the minor civil division: Provided, That no 
such distance shall be deemed to be less than one mile. If the sum of 
the quotients thus obtained for all minor civil divisions wholly or 
partly within the circle is 1,000 or less, the population factor is 1. 
If the sum of these quotients is more than 1,000 but not more than 
3,000, the population factor is 1.2. If the sum of these quotients is 
more than 3,000 but not more than 5,000, the population factor is 1.4. 
If the sum of these quotients is more than 5,000 but not more than 
7,000, the population factor is 1.6. If the sum of these quotients is 
more than 7,000 but not more than 9,000, the population factor is 1.8. 
If the sum of these quotients is more than 9,000 the population factor 
is 2.0.
    (c) In any case where a person is authorized under parts 50, 52, or 
54 of this chapter to operate two or more nuclear reactors at the same 
location, the total financial protection required of the licensee for 
all such reactors is the highest amount which would otherwise be 
required for any one of those reactors; provided, that such financial 
protection covers all reactors at the location.
    (d) Except in cases where the amount of financial protection 
calculated under this section is a multiple of $100,000, amounts 
determined pursuant to this section shall be adjusted to the next 
highest multiple of $100,000.

[25 FR 2944, Apr. 7, 1960, as amended at 26 FR 1397, Feb. 17, 1961; 32 
FR 8125, June 7, 1967; 72 FR 49565, Aug. 28, 2007]

[[Page 757]]



Sec. 140.13  Amount of financial protection required of certain 
holders of construction permits and combined licenses under 10
CFR part 52.

    Each holder of a part 50 construction permit, or a holder of a 
combined license under part 52 of this chapter before the date that the 
Commission had made the finding under 10 CFR 52.103(g), who also holds a 
license under part 70 of this chapter authorizing ownership, possession 
and storage only of special nuclear material at the site of the nuclear 
reactor for use as fuel in operation of the nuclear reactor after 
issuance of either an operating license under 10 CFR part 50 or combined 
license under 10 CFR part 52, shall, during the period before issuance 
of a license authorizing operation under 10 CFR part 50, or the period 
before the Commission makes the finding under Sec. 52.103(g) of this 
chapter, as applicable, have and maintain financial protection in the 
amount of $1,000,000. Proof of financial protection shall be filed with 
the Commission in the manner specified in Sec. 140.15 of this chapter 
before issuance of the license under part 70 of this chapter.

[72 FR 49565, Aug. 28, 2007]



Sec. 140.13a  Amount of financial protection required for plutonium
processing and fuel fabrication plants.

    (a) Each holder of a license issued pursuant to part 70 of this 
chapter to possess and use plutonium at a plutonium processing and fuel 
fabrication plant is required to have and maintain financial protection 
in the form specified in Sec. 140.14 in the amount of $200,000,000. 
Proof of financial protection shall be filed with the Commission in the 
manner in Sec. 140.15 prior to issuance of the license under part 70 of 
this chapter.
    (b) In any case, when a person is authorized pursuant to part 70 of 
this chapter to possess and use plutonium at two or more plutonium 
processing and fuel fabrication plants at the same location, the total 
financial protection required of the licensee for all such plants is the 
highest amount which would otherwise be required for any one of those 
plants: Provided, however, That such financial protection covers all 
such plants at the location.

[42 FR 49, Jan. 3, 1977, as amended at 42 FR 20140, Apr. 18, 1977; 44 FR 
20632, Apr. 6, 1979; 54 FR 24158, June 6, 1989]



Sec. 140.13b  Amount of liability insurance required for uranium
enrichment facilities.

    Each holder of a license issued under Parts 40 or 70 of this chapter 
for a uranium enrichment facility that involves the use of source 
material or special nuclear material is required to have and maintain 
liability insurance. The liability insurance must be the type and in the 
amounts the Commission considers appropriate to cover liability claims 
arising out of any occurrence within the United States that causes, 
within or outside the United States, bodily injury, sickness, disease, 
death, loss of or damage to property, or loss of use of property arising 
out of or resulting from the radioactive, toxic, explosive, or other 
hazardous properties of chemical compounds containing source material or 
special nuclear material. Proof of liability insurance must be filed 
with the Commission as required by Sec. 140.15 before issuance of a 
license for a uranium enrichment facility under parts 40 and 70 of this 
chapter.

[57 FR 18394, Apr. 30, 1992]



Sec. 140.14  Types of financial protection.

    (a) The amounts of financial protection required under this part may 
be furnished and maintained in the form of:
    (1) An effective policy of liability insurance from private sources; 
or
    (2) Adequate resources to provide the financial protection required 
by Sec. Sec. 140.11, 140.12; 140.13 or Sec. 140.13a; or
    (3) Such other type of financial protection as the Commission may 
approve; or
    (4) Any combination of the foregoing.
    (b) In any case where the Commission has approved proof of financial 
protection filed by a licensee the licensee shall not substitute one 
type of financial protection for another type without first obtaining 
the written approval of the Commission.

[25 FR 2944, Apr. 7, 1960, as amended at 42 FR 49, Jan. 3, 1977]

[[Page 758]]



Sec. 140.15  Proof of financial protection.

    (a)(1) Licensees who maintain financial protection in whole or in 
part in the form of liability insurance shall provide proof of financial 
protection that consists of a copy of the liability policy (or policies) 
together with a certificate by the insurers issuing the policy stating 
that the copy is a true copy of the currently effective policy issued to 
the licensee. The licensee may furnish proof of financial protection in 
the form of the nuclear energy liability insurance policy set forth in 
Sec. 140.91 or in any other form acceptable to the Commission.
    (2) Such proof may alternatively, consist of a copy of the 
declarations page of a nuclear energy liability policy in the form set 
forth in Sec. 140.91 and issued to the licensee: Provided, That such 
policy form has been filed by the insurers with the Commission. The 
declarations page shall be accompanied by a certificate by the insurers 
stating that said copy is a true copy of the declarations page of a 
currently effective policy and identifying the policy (including 
endorsements) by reference to the policy form which has been filed by 
them with the Commission.
    (3) The Commission will accept any other form of nuclear energy 
liability insurance as proof of financial protection if it determines 
that the provisions of such insurance provide financial protection under 
the requirements of the Commission's regulations and the Act.
    (b) Proof of financial protection in the case of licensees who 
maintain financial protection in whole or in part in the form specified 
in Sec. 140.14(a)(2) shall consist of a showing that the licensee 
clearly has adequate resources to provide the financial protection 
required under this part. For this purpose the applicant or licensee 
shall file with the Commission:
    (1) Annual financial statements for the three complete calendar or 
fiscal years preceding the date of filing, together with an opinion 
thereon by a certified public accountant. The financial statements shall 
include balance sheets, operating statements and such supporting 
schedules as may be needed for interpretation of the balance sheets and 
operating statements.
    (2) If the most recent statements required under paragraph (b)(1) of 
this section have been prepared as of a date more than 90 days prior to 
the date of filing, similar financial statements, prepared as of a date 
not more than 90 days prior to the date of filing, should be included. 
These statements need not be reviewed by a certified public accountant.
    (c) The Commission may require any licensee to file with the 
Commission such additional proof of financial protection or other 
financial information as the Commission determines to be appropriate for 
the purpose of determining whether the licensee is maintaining financial 
protection as required under this part.
    (d) Proof of financial protection shall be subject to the approval 
of the Commission.
    (e) The licensee shall promptly notify the Commission of any 
material change in proof of financial protection or in other financial 
information filed with the Commission under this part.

[25 FR 2944, Apr. 7, 1960, as amended at 33 FR 15999, Oct. 31, 1968; 49 
FR 11148, Mar. 26, 1984]



Sec. 140.16  Commission review of proof of financial protection.

    The Commission will review proof of financial protection filed by 
any licensee or applicant for license. If the Commission finds that the 
licensee or applicant for license is maintaining financial protection in 
accordance with the requirements of this part, approval of the financial 
protection will be evidenced by incorporation of appropriate provision 
in the license.



Sec. 140.17  Special provisions applicable to licensees furnishing
financial protection in whole or in part in the form of liability 
insurance.

    In any case where a licensee undertakes to maintain financial 
protection in the form of liability insurance for all or part of the 
financial protection required by this part,
    (a) The Commission may require proof that the organization or 
organizations which have issued such policies are legally authorized to 
issue them and do business in the United States and have clear ability 
to meet their obligations; and

[[Page 759]]

    (b) At least 30 days prior to the termination of any such policy, 
the licensee shall notify the Commission of the renewal of such policy 
or shall file other proof of financial protection.



Sec. 140.18  Special provisions applicable to licensees furnishing
financial protection in whole or in part in the form of adequate
resources.

    In any case where a licensee undertakes to maintain financial 
protection in the form specified in Sec. 140.14(a)(2) for all or part 
of the financial protection required by this part, the Commission may 
require such licensee to file with the Commission such financial 
information as the Commission determines to be appropriate for the 
purpose of determining whether the licensee is maintaining financial 
protection as required by this part.

[42 FR 43385, Aug. 29, 1977]



Sec. 140.19  Failure by licensees to maintain financial protection.

    In any case where the Commission finds that the financial protection 
maintained by a licensee is not adequate to meet the requirements of 
this part, the Commission may suspend or revoke the license or may issue 
such order with respect to licensed activities as the Commission 
determines to be appropriate or necessary in order to carry out the 
provisions of this part and of section 170 of the Act.



Sec. 140.20  Indemnity agreements and liens.

    (a) The Commission will execute and issue agreements of indemnity 
pursuant to the regulations in this part or such other regulations as 
may be issued by the Commission. Such agreements, as to any licensee, 
shall be effective on:
    (1)(i) The effective date of the license (issued pursuant to part 50 
of this chapter) authorizing the licensee to operate the nuclear reactor 
involved; or
    (ii) The date that the Commission makes the finding under Sec. 
52.103(g) of this chapter; or
    (iii) The effective date of the license (issued under part 70 of 
this chapter) authorizing the licensee to possess and store special 
nuclear material at the site of the nuclear reactor for use as fuel in 
operation of the nuclear reactor after issuance of an operating license 
for the reactor, whichever is earlier. No such agreement, however, shall 
be effective prior to September 26, 1957; or
    (2) August 1, 1977 or the effective date of the license (issued 
pursuant to part 70 of this chapter) authorizing the licensee to possess 
and use plutonium at the site of the plutonium processing and fuel 
fabrication plant for processing in that plant, whichever date is later.
    (b) If the licensee fails to pay assessed deferred premiums, the 
Commission reserves the right to pay those premiums on behalf of the 
licensee and to recover the amount of such premiums from the licensee.
    (c) The Commission shall require the immediate submission of 
financial statements by those licensees who indicate, after an 
assessment of the retrospective premium by the insurance pools, that 
they will not pay the assessment. Such financial statements shall 
include, as a minimum, exhibits indicating internally generated funds 
from operations and accumulated retained earnings. Subsequent submission 
of financial statements by such licensees may be requested by the 
Commission, as required.
    (d) If premiums are paid by the Commission as provided in paragraph 
(b) of this section, payment by the Commission shall create a lien in 
the amount paid in favor of the United States upon all property and 
rights to property, whether real or personal, belonging to such 
licensee. The lien shall arise at the time payment is made by the 
Commission and shall continue until the liability for the amount (or a 
judgment against the licensee arising out of such liability) is 
satisfied or becomes unenforceable. The Commission will issue a 
certificate of release of any such lien if it finds that the liability 
for the amount has been fully satisfied or has become legally 
unenforceable.
    (e) If the Commission determines that the licensee is financially 
able to reimburse the Commission for a deferred premium payment made in 
its behalf, and the licensee, after notice of such determination by the 
Commission fails to make such reimbursement within 120 days, the 
Commission will

[[Page 760]]

take appropriate steps to suspend the license for 30 days. The 
Commission may take such further action as is necessary if reimbursement 
is not made within the 30-day suspension period including but not 
limited to termination of the operating license.
    (f)(1)(i) The general form of indemnity agreement to be entered into 
by the Commission with reactor licensees who furnish financial 
protection in the form of the nuclear energy liability insurance policy 
set forth in appendix A is contained in Sec. 140.92, appendix B. The 
general form of indemnity agreement to be entered into by the Commission 
with reactor licensees who furnish financial protection in the form 
specified in Sec. 140.14(a)(2) is set forth in Sec. 140.93, appendix 
C.
    (ii) The general form of indemnity agreement to be entered into by 
the Commission with persons licensed to possess and use plutonium in a 
plutonium processing and fuel fabrication plant and who furnish 
financial protection in the form of the nuclear energy liability 
insurance policy set forth in appendix A \2\ is contained in Sec. 
140.107, appendix G. The general form of indemnity agreement to be 
entered into by the Commission with such licensees who furnish financial 
protection in the form specified in Sec. 140.14(a)(2) is set forth in 
Sec. 140.108, appendix H.
---------------------------------------------------------------------------

    \2\ The form of the nuclear energy liability insurance policy for 
these licensees will be the subject of pertinent endorsements after 
discussion with the insurance pools.
---------------------------------------------------------------------------

    (2) The form of indemnity agreement to be entered into by the 
Commission with any particular licensee under this subpart shall contain 
such modifications of the applicable form in Sec. Sec. 140.92, 140.93, 
140.107 and 140.108, appendices A, B, C, G and H, as are provided for in 
applicable licenses, regulations or orders of the Commission.
    (3) Each licensee who has executed an indemnity agreement under this 
subpart shall enter into such agreements amending such indemnity 
agreement as are required by applicable licenses, regulations, or orders 
of the Commission.

[42 FR 49, Jan. 3, 1977, as amended at 72 FR 49565, Aug. 28, 2007]



Sec. 140.21  Licensee guarantees of payment of deferred premiums.

    Each licensee required to have and maintain financial protection for 
each nuclear reactor as determined in Sec. 140.11(a)(4) shall at the 
issuance of the license and annually, on the anniversary of the date on 
which the indemnity agreement is effective, provide evidence to the 
Commission that it maintains one of the following types of guarantee of 
payment of deferred premium in the amount specified in Sec. 
140.11(a)(4) for each reactor it is licensed to operate:
    (a) Surety bond,
    (b) Letter of credit,
    (c) Revolving credit/term loan arrangement,
    (d) Maintenance of escrow deposits of government securities,
    (e) Annual certified financial statement showing either that a cash 
flow (i.e., cash available to a company after all operating expenses, 
taxes, interest charges, and dividends have been paid) can be generated 
and would be available for payment of retrospective premiums within 
three (3) months after submission of the statement, or a cash reserve or 
a combination of cash flow and cash reserve, or
    (f) Such other type of guarantee as may be approved by the 
Commission.

[42 FR 50, Jan. 3, 1977, as amended at 71 FR 15012, Mar. 27, 2006; 74 FR 
62686, Dec. 1, 2009; 79 FR 38769, July 9, 2014]



Sec. 140.22  Commission guarantee and reimbursement agreements.

    Each licensee required to have and maintain financial protection for 
each nuclear reactor as determined in Sec. 140.11(a)(4) shall execute 
an indemnity agreement with the Commission that provides for the payment 
by the Commission of deferred premiums not paid by the licensee and 
reimbursement of the Commission by the licensee. The general forms of 
agreement to be entered into by the Committee and licensees are set 
forth in Sec. 140.92, appendix B and Sec. 140.93, appendix C.

[42 FR 50, Jan. 3, 1977]

[[Page 761]]



        Subpart C_Provisions Applicable Only to Federal Agencies



Sec. 140.51  Scope.

    This subpart applies only to persons found by the Commission to be 
Federal agencies, which have applied for or are holders of licenses 
issued pursuant to part 50 of this chapter authorizing operation of 
nuclear reactors.

    Note: Federal agencies are not required to furnish financial 
protection.



Sec. 140.52  Indemnity agreements.

    (a) The Commission will execute and issue agreements of indemnity 
with each Federal agency subject to this subpart pursuant to the 
regulations in this part or such other regulations as may be issued by 
the Commission. Such agreements, as to any licensee, shall be effective 
on:
    (1) The effective date of the license (issued pursuant to part 50 of 
this chapter) authorizing the licensee to operate the nuclear reactor 
involved; or
    (2) The effective date of the license (issued pursuant to part 70 of 
this chapter) authorizing the licensee to possess and store special 
nuclear material at the site of the nuclear reactor for use as fuel in 
operation of the nuclear reactor after issuance of an operating license 
for the reactor, whichever is earlier. No such agreement, however, shall 
be effective prior to September 26, 1957.
    (b)(1) The general form of indemnity agreement to be entered into 
with licensees subject to this subpart is contained in Sec. 140.94 
appendix D.
    (2) The form of indemnity agreement to be entered into by the 
Commission with any particular licensee under this subpart shall contain 
such modifications of the form in Sec. 140.94, as are provided for in 
applicable licenses, regulations or orders of the Commission.
    (3) Each licensee who has executed an indemnity agreement under this 
subpart shall enter into such agreements amending such indemnity 
agreement as are required by applicable licenses, regulations or orders 
of the Commission.

[27 FR 2885, Mar. 29, 1962, as amended at 33 FR 15999, Oct. 31, 1968]



     Subpart D_Provisions Applicable Only to Nonprofit Educational 
                              Institutions



Sec. 140.71  Scope.

    This subpart applies only to applicants for and holders of licenses 
issued for the conduct of educational activities to persons found by the 
Commission to be nonprofit educational institutions, except that this 
subpart does not apply to Federal agencies.

    Note: Financial protection is not required with respect to licenses 
issued for the conduct of educational activities to persons found by the 
Commission to be non-profit educational institutions.



Sec. 140.72  Indemnity agreements.

    (a) The Commission will execute and issue agreements of indemnity 
with each non-profit educational institution subject to this subpart 
pursuant to the regulations in this part or such other regulations as 
may be issued by the Commission. Such agreements, as to any licensee, 
shall be effective on:
    (1) The effective date of the license (issued pursuant to part 50 of 
this chapter) authorizing the licensee to operate the nuclear reactor 
involved; or
    (2) The effective date of the license (issued pursuant to part 70 of 
this chapter) authorizing the licensee to possess and store special 
nuclear material at the site of the nuclear reactor for use as fuel in 
operation of the nuclear reactor after issuance of an operating license 
for the reactor, whichever is earlier. No such agreement, however, shall 
be effective prior to September 26, 1957.
    (b)(1) The general form of indemnity agreement to be entered into 
with licensees subject to this subpart is contained in Sec. 140.95 
appendix E.
    (2) The form of indemnity agreement to be entered into by the 
Commission with any particular licensee under this subpart shall contain 
such modifications of the form in Sec. 140.95 appendix E, as are 
provided for in applicable licenses, regulations or orders of the 
Commission.
    (3) Each licensee who has executed an indemnity agreement under this 
subpart shall enter into such agreements amending such indemnity 
agreement as are required by applicable licenses,

[[Page 762]]

regulations or orders of the Commission.

[27 FR 2885, Mar. 29, 1962, as amended at 33 FR 15999, Oct. 31, 1968]



               Subpart E_Extraordinary Nuclear Occurrences



Sec. 140.81  Scope and purpose.

    (a) Scope. This subpart applies to applicants for and holders of 
licenses authorizing operation of production facilities and utilization 
facilities, including combined licenses under part 52 of this chapter, 
and to other persons indemnified with respect to such facilities.
    (b) Purpose. One purpose of this subpart is to set forth the 
criteria which the Commission proposes to follow in order to determine 
whether there has been an ``extraordinary nuclear occurrence.'' The 
other purpose is to establish the conditions of the waivers of defenses 
proposed for incorporation in indemnity agreements and insurance 
policies or contracts furnished as proof of financial protection.
    (1) The system is to come into effect only where the discharge or 
dispersal constitutes a substantial amount of source, special nuclear or 
byproduct material, or has caused substantial radiation levels offsite. 
The various limits in present NRC regulations are not appropriate for 
direct application in the determination of an ``extraordinary nuclear 
occurrence,'' for they were arrived at with other purposes in mind, and 
those limits have been set at a level which is conservatively arrived at 
by incorporating a significant safety factor. Thus, a discharge or 
dispersal which exceeds the limits in NRC regulations, or in license 
conditions, although possible cause for concern, is not one which would 
be expected to cause substantial injury or damage unless it exceeds by 
some significant multiple the appropriate regulatory limit. Accordingly, 
in arriving at the values in the criteria to be deemed ``substantial'' 
it is more appropriate to adopt values separate from NRC health and 
safety regulations, and, of course, the selection of these values will 
not in any way affect such regulations. A substantial discharge, for 
purposes of the criteria, represents a perturbation of the environment 
which is clearly above that which could be anticipated from the conduct 
of normal activities. The criteria are intended solely for the purposes 
of administration of the Commission's statutory responsibilities under 
Pub. L. 89-645, and are not intended to indicate a level of discharge or 
dispersal at which damage to persons or property necessarily will occur, 
or a level at which damage is likely to occur, or even a level at which 
some type of protective action is indicated. It should be clearly 
understood that the criteria in no way establish or indicate that there 
is a specific threshold of exposure at which biological damage from 
radiation will take place. It cannot be emphasized too frequently that 
the levels set to be used as criteria for the first part of the 
determination, that is, the criteria for amounts offsite or radiation 
levels offsite which are substantial, are not meant to indicate that, 
because such amounts or levels are determined to be substantial for 
purposes of administration, they are ``substantial'' in terms of their 
propensity for causing injury or damage.
    (2) It is the purpose of the second part of the determination that 
the Commission decide whether there have in fact been or will probably 
be substantial damages to persons offsite or property offsite. The 
criteria for substantial damages were formulated, and the numerical 
values selected, on a wholly different basis from that on which the 
criteria used for the first part of the determination with respect to 
substantial discharge were derived. The only interrelation between the 
values selected for the discharge criteria and the damage criteria is 
that the discharge values are set so low that it is extremely unlikely 
the damage criteria could be satisfied unless the discharge values have 
been exceeded.
    (3) The first part of the test is designed so that the Commission 
can assure itself that something exceptional has occurred; that 
something untoward and unexpected has in fact taken place and that this 
event is of sufficient significance to raise the possibility that some 
damage to persons or property offsite has resulted or may result. If 
there appears to be no damage, the

[[Page 763]]

waivers will not apply because the Commission will be unable, under the 
second part of the test, to make a determination that ``substantial 
damages'' have resulted or will probably result. If damages have 
resulted or will probably result, they could vary from de minimis to 
serious, and the waivers will not apply until the damages, both actual 
and probable, are determined to be ``substantial'' within the second 
part of the test.
    (4) The presence or absence of an extraordinary nuclear occurrence 
determination does not concomitantly determine whether or not a 
particular claimant will recover on his claim. In effect, it is intended 
primarily to determine whether certain potential obstacles to recovery 
are to be removed from the route the claimant would ordinarily follow to 
seek compensation for his injury or damage. If there has not been an 
extraordinary nuclear occurrence determination, the claimant must 
proceed (in the absence of settlement) with a tort action subject to 
whatever issues must be met, and whatever defenses are available to the 
defendant, under the law applicable in the relevant jurisdiction. If 
there has been an extraordinary nuclear occurrence determination, the 
claimant must still proceed (in the absence of settlement) with a tort 
action, but the claimant's burden is substantially eased by the 
elimination of certain issues which may be involved and certain defenses 
which may be available to the defendant. In either case the defendant 
may defend with respect to such of the following matters as are in issue 
in any given claim: The nature of the claimant's alleged damages, the 
causal relationship between the event and the alleged damages, and the 
amount of the alleged damages.

[33 FR 15999, Oct. 31, 1968, as amended at 40 FR 8793, Mar. 3, 1975; 72 
FR 49565, Aug. 28, 2007]



Sec. 140.82  Procedures.

    (a) The Commission may initiate, on its own motion, the making of a 
determination as to whether or not there has been an extraordinary 
nuclear occurrence. In the event the Commission does not so initiate the 
making of a determination, any affected person, or any licensee or 
person with whom an indemnity agreement is executed or a person 
providing financial protection may petition the Commission for a 
determination of whether or not there has been an extraordinary nuclear 
occurrence. If the Commission does not have, or does not expect to have, 
within 7 days after it has received notification of an alleged event, 
enough information available to make a determination that there has been 
an extraordinary nuclear occurrence, the Commission will publish a 
notice in the Federal Register setting forth the date and place of the 
alleged event and requesting any persons having knowledge thereof to 
submit their information to the Commission.
    (b) When a procedure is initiated under paragraph (a) of this 
section, the Commission will designate members of the principal staff to 
begin immediately to assemble the relevant information and prepare a 
report on which the Commission can make its determination.

[33 FR 15999, Oct. 31, 1968, as amended at 40 FR 8794, Mar. 3, 1975]



Sec. 140.83  Determination of extraordinary nuclear occurrence.

    If the Commission determines that both of the criteria set forth in 
Sec. Sec. 140.84 and 140.85 have been met, it will make the 
determination that there has been an extraordinary nuclear occurrence. 
If the Commission publishes a notice in the Federal Register in 
accordance with Sec. 140.82(a) and does not make a determination within 
90 days thereafter that there has been an extraordinary nuclear 
occurrence, the alleged event will be deemed not to be an extraordinary 
nuclear occurrence. The time for the making of a determination may be 
extended by the Commission by notice published in the Federal Register.

[33 FR 15999, Oct. 31, 1968]



Sec. 140.84  Criterion I--Substantial discharge of radioactive 
material or substantial radiation levels offsite.

    The Commission will determine that there has been a substantial 
discharge or dispersal of radioactive material offsite, or that there 
have been substantial levels of radiation offsite, when, as

[[Page 764]]

a result of an event comprised of one or more related happenings, 
radioactive material is released from its intended place of confinement 
or radiation levels occur offsite and either of the following findings 
are also made:
    (a) The Commission finds that one or more persons offsite were, 
could have been, or might be exposed to radiation or to radioactive 
material, resulting in a dose or in a projected dose in excess of one of 
the levels in the following table:

                     Total Projected Radiation Doses
------------------------------------------------------------------------
                       Critical organ                        Dose (rems)
------------------------------------------------------------------------
Thyroid....................................................           30
Whole body.................................................           20
Bone marrow................................................           20
Skin.......................................................           60
Other organs or tissues....................................           30
------------------------------------------------------------------------


Exposures from the following types of sources of radiation shall be 
included:
    (1) Radiation from sources external to the body;
    (2) Radioactive material that may be taken into the body from its 
occurrence in air or water; and
    (3) Radioactive material that may be taken into the body from its 
occurrence in food or on terrestrial surfaces.
    (b) The Commission finds that:
    (1) Surface contamination of at least a total of any 100 square 
meters of offsite property has occurred as the result of a release of 
radioactive material from a production or utilization facility and such 
contamination is characterized by levels of radiation in excess of one 
of the values listed in Column 1 or Column 2 of the following table, or
    (2) Surface contamination of any offsite property has occurred as 
the result of a release of radioactive material in the course of 
transportation and such contamination is characterized by levels of 
radiation in excess of one of the values listed in column 2 of the 
following table:

                 Total Surface Contamination Levels \1\
------------------------------------------------------------------------
                                   Column 1 Offsite
                                       property,
                                     contiguous to
                                    site, owned or
         Type of emitter           leased by person     Column 2 Other
                                     with whom an      offsite property
                                       indemnity
                                     agreement is
                                       executed
------------------------------------------------------------------------
Alpha emission from transuranic   3.5 microcuries     0.35 microcuries
 isotopes.                         per square meter.   per square meter.
Alpha emission from isotopes      35 microcuries per  3.5 microcuries
 other than transuranic isotopes.  square meter.       per square meter.
Beta or gamma mission...........  40 millirads/hour   4 millirads/hour @
                                   @ 1 cm.\2\.         1 cm.\2\
------------------------------------------------------------------------
\1\ The maximum levels (above background), observed or projected, 8 or
  more hours after initial deposition.
\2\ Measured through not more than 7 milligrams per square centimeter of
  total absorber.


[33 FR 15999, Oct. 31, 1968, as amended at 40 FR 8794, Mar. 3, 1975]



Sec. 140.85  Criterion II--Substantial damages to persons offsite
or property offsite.

    (a) After the Commission has determined that an event has satisfied 
Criterion I, the Commission will determine that the event has resulted 
or will probably result in substantial damages to persons offsite or 
property offsite if any of the following findings are made:
    (1) The Commission finds that such event has resulted in the death 
or hospitalization, within 30 days of the event, of five or more people 
located offsite showing objective clinical evidence of physical injury 
from exposure to the radioactive, toxic, explosive, or other hazardous 
properties of source, special nuclear, or byproduct material; or
    (2) The Commission finds that $2,500,000 or more of damage offsite 
has been or will probably be sustained by any one person, or $5 million 
or more of such damage in the aggregate has been or will probably be 
sustained, as the result of such event; or
    (3) The Commission finds that $5,000 or more of damage offsite has 
been or will probably be sustained by each of 50 or more persons, 
provided that $1 million or more of such damage in the aggregate has 
been or will probably be sustained, as the result of such event.
    (b) As used in paragraphs (a) (2) and (3) of this section, 
``damage'' shall be that arising out of or resulting from

[[Page 765]]

the radioactive, toxic, explosive, or other hazardous properties of 
source, special nuclear, or byproduct material, and shall be based upon 
estimates of one or more of the following:
    (1) Total cost necessary to put affected property back into use,
    (2) Loss of use of affected property,
    (3) Value of affected property where not practical to restore to 
use,
    (4) Financial loss resulting from protective actions appropriate to 
reduce or avoid exposure to radiation or to radioactive materials.

[33 FR 15999, Oct. 31, 1968]



                          Subpart F_Violations



Sec. 140.87  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55080, Nov. 24, 1992]



Sec. 140.89  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 140 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 140 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 140.1, 140.2, 140.3, 140.4, 140.5, 140.7, 140.8, 140.9, 
140.9a, 140.10, 140.14, 140.16, 140.18, 140.19, 140.20, 140.51, 140.52, 
140.71, 140.72, 140.81, 140.82, 140.83, 140.84, 140.85, 140.87, 140.89, 
140.91, 140.92, 140.93, 140.94, 140.95, 140.96, 140.107, 140.108, and 
140.109.

[57 FR 55080, Nov. 24, 1992]

                         Appendixes to Part 140



Sec. 140.91  Appendix A--Form of nuclear energy liability policy 
for facilities.

    While the text of the policy which follows is exemplary of a 
contract acceptable to the Commission as evidence of the financial 
protection required of the licensee by section 170 of the Atomic Energy 
Act of 1954, as amended, variations on this text submitted by the 
licensee also will be considered by the Commission in determining 
whether the licensee meets the financial protection requirements of the 
Act. The full text of the policy is published solely for the purpose of 
completeness. Publication of this text should not be construed as a 
Commission endorsement of any particular provision pertaining solely to 
the business relationship between the insurers and the insureds or to 
any other matter not within the Commission's statutory jurisdiction 
under the Atomic Energy Act.

                     Nuclear Energy Liability Policy

                             (Facility Form)

    The undersigned members of _____, hereinafter called the 
``companies,'' each for itself, severally and not jointly, and in the 
respective proportions hereinafter set forth, agree with the insured, 
named in the declarations made a part hereof, in consideration of the 
premium and in reliance upon the statements in the declarations and 
subject to the limit of liability, exclusions, conditions and other 
terms of this policy;

                           insuring agreements

    I. Coverage A--Bodily injury and property damage liability. To pay 
on behalf of the insured:

[[Page 766]]

    (1) All sums which the insured shall become legally obligated to pay 
as damages because of bodily injury or property damage caused by the 
nuclear energy hazard, and the companies shall defend any suit against 
the insured alleging such bodily injury or property damage and seeking 
damages which are payable under the terms of this policy; but the 
companies may make such investigation, negotiation and settlement of any 
claim or suit as they deem expedient;
    (2) Costs taxed against the insured in any such suit and interest on 
any judgment therein;
    (3) Premiums on appeal bonds and on bonds to release attachments in 
any such suit, but without obligation to apply for or furnish such 
bonds;
    (4) Reasonable expenses, other than loss of earnings, incurred by 
the insured at the companies' request.
    Coverage B--Damage to property of an insured away from the facility. 
With respect to property damage caused by the nuclear energy hazard to 
property of an insured which is away from the facility, to pay to such 
insured those sums which such insured would have been legally obligated 
to pay as damages therefor, had such property belonged to another.
    Coverage C--Subrogation--Offsite employees. With respect to bodily 
injury sustained by any employee of an insured and caused by the nuclear 
energy hazard, to pay to the workmen's compensation carrier of such 
insured all sums which such carrier would have been entitled to recover 
and retain as damages from another person or organization, had such 
person or organization alone been legally responsible for such bodily 
injury, by reason of the rights acquired by subrogation by the payment 
of the benefits required of such carrier under the applicable workmen's 
compensation or occupational disease law. An employer who is a duly 
qualified self-insurer under such law shall be deemed to be a workmen's 
compensation carrier within the meaning of this coverage. This Coverage 
C does not apply to bodily injury sustained by any person who is 
employed at and in connection with the facility. This Coverage C shall 
not constitute workmen's compensation insurance as required under the 
laws of any state.
    II. Definition of insured. The unqualified word insured includes (a) 
the named insured and (b) any other person or organization with respect 
to his legal responsibility for damages because of bodily injury or 
property damage caused by the nuclear energy hazard.
    Subdivision (b) above does not include as an insured the United 
States of America or any of its agencies.
    Subject to Condition 3 and the other provisions of this policy, the 
insurance applies separately to each insured against whom claim is made 
or suit is brought.
    III. Definitions. Wherever used in this policy:
    Bodily injury means bodily injury, sickness or disease, including 
death resulting therefrom, sustained by any person;
    Property damage means physical injury to or destruction or 
radioactive contamination of property, and loss of use of property so 
injured, destroyed or contaminated, and loss of use of property while 
evacuated or withdrawn from use because possibly so contaminated or 
because of imminent danger of such contamination;
    Nuclear material means source material, special nuclear material or 
byproduct material;
    Source material, special nuclear material, and byproduct material 
have the meanings given them in the Atomic Energy Act of 1954, or in any 
law amendatory thereof;
    Spent fuel means any fuel element or fuel component, solid or 
liquid, which has been used or exposed to radiation in any nuclear 
reactor;
    Waste means any waste material (1) containing byproduct material and 
(2) resulting from the operation by any person or organization of any 
nuclear facility included within the definition of nuclear facility 
under paragraph (1) or (2) thereof;
    The facility means the facility described in the declarations and 
includes the location designated in Item 3 of the declarations and all 
property and operations at such location;
    Nuclear facility means the facility as defined in any Nuclear Energy 
Liability Policy (Facility Form) issued by the companies or by 
_________________.
The term nuclear facility also means
    (1) Any nuclear reactor,
    (2) Any equipment or device designed or used for (a) separating the 
isotopes of uranium or plutonium, (b) processing or utilizing spent 
fuel, or (c) handling, processing or packaging waste,
    (3) Any equipment or device used for the processing, fabricating or 
alloying of special nuclear material if at any time the total amount of 
such material in the custody of the insured at the premises where such 
equipment or device is located consists of or contains more than 25 
grams of plutonium or uranium-233 or any combination thereof, or more 
than 250 grams of uranium-235,
    (4) Any structure, basin, excavation, premises or place prepared or 
used for the storage or disposal of waste, and includes the site on 
which any of the foregoing is located, all operations conducted on such 
site and all premises used for such operations;
    Indemnified nuclear facility means
    (1) The facility as defined in any Nuclear Energy Liability Policy 
(Facility Form) issued by the companies or by _______________________,
    (2) Any other nuclear facility,


[[Page 767]]


if financial protection is required pursuant to the Atomic Energy Act of 
1954, or any law amendatory thereof, with respect to any activities or 
operations conducted thereat;
    Nuclear reactor means any apparatus designed or used to sustain 
nuclear fission in a self-supporting chain reaction or to contain a 
critical mass of fissionable material;
    Nuclear energy hazard means the radioactive, toxic, explosive or 
other hazardous properties of nuclear material, but only if:
    (1) The nuclear material is at the facility or has been discharged 
or dispersed therefrom without intent to relinquish possession or 
custody thereof to any person or organization, or
    (2) The nuclear material is in an insured shipment which is (a) in 
the course of transportation, including handling and temporary storage 
incidental thereto, within the territorial limits of the United States 
of America, its territories or possessions, Puerto Rico or the Canal 
Zone and (b) away from any other nuclear facility;
    Insured shipment means a shipment of source material, special 
nuclear material, spent fuel of waste, herein called material, (1) to 
the facility from a nuclear facility owned by the United States of 
America, but only if the transportation of the material is not by 
predetermination to be interrupted by the removal of the material from a 
transporting conveyance for any purpose other than the continuation of 
its transportation, or (2) from the facility to any other location 
except an indemnified nuclear facility, but only until the material is 
removed from a transporting conveyance for any purpose other than the 
continuation of its transportation.
    IV. Application of policy. This policy applies only to bodily injury 
or property damage (1) which is caused during the policy period by the 
nuclear energy hazard and (2) which is discovered and for which written 
claim is made against the insured, not later than two years after the 
end of the policy period.

                               Exclusions

    This policy does not apply:
    (a) To any obligation for which the insured or any carrier as his 
insurer may be held liable under any workmen's compensation, 
unemployment compensation or disability benefits law, or under any 
similar law;
    (b) Except with respect to liability of another assumed by the 
insured under contract, to bodily injury to any employee of the insured 
arising out of and in the course of his employment by the insured; but 
this exclusion does not apply to bodily injury to any person who is not 
employed at and in connection with the facility if the insured has 
complied with the requirements of the applicable workmen's compensation 
or occupational disease law respecting the securing of compensation 
benefits thereunder to his employees;
    (c) To liability assumed by the insured under contract, other than 
an assumption in a contract with another of the liability of any person 
or organization which would be imposed by law on such person or 
organization in the absence of an express assumption of liability;
    (d) To bodily injury or property damage due to the manufacturing, 
handling or use at the location designated in Item 3 of the 
declarations, in time of peace or war, of any nuclear weapon or other 
instrument of war utilizing special nuclear material or byproduct 
material;
    (e) To bodily injury or property damage due to war, whether or not 
declared, civil war, insurrection, rebellion or revolution, or to any 
act or conditions incident to any of the foregoing;
    (f) To property damage to any property at the location designated in 
Item 3 of the declarations, other than aircraft, watercraft or vehicles 
licensed for highway use, provided such aircraft, watercraft or vehicles 
are not used in connection with the operation of the facility;
    (g) To property damage to nuclear material in the course of 
transportation to or from the facility including handling or storage 
incidental thereto;
    (h) Under Coverage B, to property damage due to neglect of the 
insured to use all reasonable means to save and preserve the property 
after knowledge of the occurrence resulting in such property damage.

                               Conditions

    1. Premium--(1) Definitions. With reference to the premium for this 
policy: advance premium, for any calendar year, is the estimated 
standard premium for that calendar year;
    Standard premium, for any calendar year, is the premium for that 
calendar year computed in accordance with the companies' rules, rates, 
rating plans (other than the Industry Credit Rating Plan), premiums and 
minimum premiums applicable to this insurance;
    Reserve premium means that portion of the standard premium paid to 
the companies and specifically allocated under the Industry Credit 
Rating Plan for incurred losses. The amount of the reserve premium for 
this policy for any calendar year during which this policy is in force 
is the amount designated as such in the Standard Premium Endorsement for 
that calendar year;
    Industry reserve premium, for any calendar year, is the sum of the 
reserve premiums for that calendar year for all Nuclear Energy Liability 
Policies issued by the Nuclear Energy Liability Insurance Association 
and Mutual Atomic Energy Liability Underwriters and subject to the 
Industry Credit Rating Plan;

[[Page 768]]

    Policy refund ratio, for any calendar year, is the ratio of the 
named insured's reserve premium for that calendar year to the industry 
reserve premium for that calendar year;
    Incurred losses means the sum of:
    (1) All losses and expenses by Nuclear Energy Liability Insurance 
Association and Mutual Atomic Energy Liability Underwriters, and
    (2) All reserves for unpaid losses and expenses as estimated by 
Nuclear Energy Liability Insurance Association and Mutual Atomic Energy 
Liability Underwriters because of obligations assumed and the expenses 
incurred in connection with such obligations by members of Nuclear 
Energy Liability Insurance Association and Mutual Atomic Energy 
Liability Underwriters under all Nuclear Energy Liability Policies 
issued by Nuclear Energy Liability Insurance Association and Mutual 
Atomic Energy Liability Underwriters and subject to the Industry Credit 
Rating Plan;
    Reserve for refunds, at the end of any calendar year, is the amount 
by which (1) the sum of all industry reserve premiums for the period 
from January 1, 1957 through the end of such calendar year exceeds (2) 
the total for the same period of (a) all incurred losses, valued as of 
the next following July 1, and (b) all reserve premium refunds made 
under the Industry Credit Rating Plan by members of Nuclear Energy 
Liability Insurance Association and Mutual Atomic Energy Liability 
Underwriters;
    Industry reserve premium refund, for any calendar year, is 
determined by multiplying the reserve for refunds at the end of the 
ninth calendar year thereafter by the ratio of the industry reserve 
premium for the calendar year for which the premium refund is being 
determined to the sum of such amount and the total industry reserve 
premiums for the next nine calendar years thereafter, provided that the 
industry reserve premium refund for any calendar year shall in no event 
be greater than the industry reserve premium for such calendar year.
    (2) Payment of advance and standard premiums. The named insured 
shall pay the companies the advance premium stated in the declarations, 
for the period from the effective date of this policy through December 
31 following. Thereafter, at the beginning of each calendar year while 
this policy is in force, the named insured shall pay the advance premium 
for such year to the companies. The advance premium for each calendar 
year shall be stated in the Advance Premium Endorsement for such 
calendar year issued to the named insured as soon as practicable prior 
to or after the beginning of such year.
    As soon as practicable after each December 31 and after the 
termination of this policy, the standard premium for the preceding 
calendar year shall be finally determined and stated in the Standard 
Premium Endorsement for that calendar year. If the standard premium so 
determined exceeds the advance premium previously paid for such calendar 
year, the named insured shall pay the excess to the companies; if less, 
the companies shall return to the named insured the excess portion paid 
by such insured.
    The named insured shall maintain records of the information 
necessary for premium computation and shall send copies of such records 
to the companies as directed, at the end of each calendar year, at the 
end of the policy period and at such other times during the policy 
period as the companies may direct.
    (3) Use of reserve premiums. All reserve premiums paid or payable 
for this policy may be used by the members of Nuclear Energy Liability 
Insurance Association or Mutual Atomic Energy Liability Underwriters to 
discharge their obligations with respect to incurred losses whether such 
losses are incurred under this policy or under any other policy issued 
by the Nuclear Energy Liability Insurance Association or Mutual Atomic 
Energy Liability Underwriters.
    (4) Reserve premium refunds. A portion of the reserve premium for 
this policy for the first calendar year of any group of ten consecutive 
calendar years shall be returnable to the named insured provided there 
is a reserve for refunds at the end of the tenth calendar year.
    (5) Computation of reserve premium refunds. The reserve premium 
refund due the named insured for any calendar year shall be determined 
by multiplying any industry reserve premium refund for such calendar 
year by the policy refund ratio for such calendar year. The reserve 
premium refund for any calendar year shall be finally determined as soon 
as practicable after July 1 of the tenth calendar year thereafter.
    (6) Final premium. The final premium for this policy shall be the 
sum of the standard premiums for each calendar year, or portion thereof, 
during which this policy remains in force less the sum of all refunds of 
reserve premiums due the named insured under the provisions of this 
Condition 1.
    (7) Reserve premium refund agreement. Each member of Nuclear Energy 
Liability Insurance Association or Mutual Atomic Energy Liability 
Underwriters subscribing this policy for any calendar year, or portion 
thereof, thereby agrees for itself, severally and not jointly, and in 
the respective proportion of its liability assumed under this policy for 
that calendar year, to return to the named insured that portion of any 
reserve premium refund due the named insured for that calendar year, 
determined in accordance with the provisions of this Condition 1.
    2. Inspection; suspension. The companies shall be permitted to 
inspect the facility and to examine the insured's books and records

[[Page 769]]

at any time, as far as they relate to the subject-matter of this 
insurance.
    If a representative of the companies discovers a condition which he 
believes to be unduly dangerous with respect to the nuclear energy 
hazard, a representative of the companies may request that such 
condition be corrected without delay. In the event of noncompliance with 
such request, a representative of the companies may, by notice to the 
named insured, to any other person or organization considered by the 
companies to be responsible for the continuance of such dangerous 
condition, and to the United States Atomic Energy Commission, suspend 
the insurance with respect to the named insured and such other person or 
organization effective 12:00 midnight of the next business day of such 
Commission following the date that such Commission receives such notice. 
The period of such suspension shall terminate as of the time stated in a 
written notice from the companies to the named insured and to each such 
person or organization that such condition has been corrected.
    3. Limit of liability; termination of policy upon exhaustion of 
limit. Regardless of the number of persons and organizations who are 
insureds under this policy, and regardless of the number of claims made 
and suits brought against any or all insureds because of one or more 
occurrences resulting in bodily injury or property damage caused during 
the policy period by the nuclear energy hazard, the limit of the 
companies' liability stated in the declarations is the total liability 
of the companies for their obligations under this policy and the 
expenses incurred by the companies in connection with such obligations, 
including.
    (a) Payments in settlement of claims and in satisfaction of 
judgments against the insureds for damages because of bodily injury or 
property damage, payments made under parts (2), (3) and (4) of Coverage 
A and payments made in settlement of claims under Coverages B and C;
    (b) Payments for expenses incurred in the investigation, 
negotiation, settlement and defense of any claim or suit, including, but 
not limited to, the cost of such services by salaried employees of the 
companies, fees and expenses of independent adjusters, attorneys' fees 
and disbursements, expenses for expert testimony, inspection and 
appraisal of property, examination, X-ray or autopsy or medical expenses 
of any kind;
    (c) Payments for expenses incurred by the companies in investigating 
an occurrence resulting in bodily injury or property damage or in 
minimizing its effects.

Each payment made by the companies in discharge of their obligations 
under this policy or for expenses incurred in connection with such 
obligations shall reduce by the amount of such payment the limit of the 
companies' liability under this policy.
    If, during the policy period or subsequent thereto, the total of 
such payments made by the companies shall exhaust the limit of the 
companies' liability under this policy, all liability and obligations of 
the companies under this policy shall thereupon terminate and shall be 
conclusively presumed to have been discharged. This policy, if not 
theretofore canceled, shall thereupon automatically terminate.
    Regardless of the number of years this policy shall continue in 
force and the number of premiums which shall be payable or paid, the 
limit of the companies' liability stated in the declarations shall not 
be cumulative from year to year.
    4. Limitation of liability; common occurrence. Any occurrence or 
series of occurrences resulting in bodily injury or property damage 
arising out of the radioactive, toxic, explosive or other hazardous 
properties of
    (a) Nuclear material discharged or dispersed from the facility over 
a period of days, weeks, months or longer and also arising out of such 
properties of other nuclear material so discharged or dispersed from one 
or more other nuclear facilities insured by the companies under a 
Nuclear Energy Liability Policy (Facility Form), or
    (b) Source material, special nuclear material, spent fuel or waste 
in the course of transportation for which insurance is afforded under 
this policy and also arising out of such properties of other source 
material, special nuclear material, spent fuel or waste in the course of 
transportation for which insurance is afforded under one or more other 
Nuclear Energy Liability Policies (Facility Form) issued by the 
companies, shall be deemed to be a common occurrence resulting in bodily 
injury or property damage caused by the nuclear energy hazard.
    With respect to such bodily injury and property damage (1) the total 
aggregate liability of the companies under all Nuclear Energy Liability 
Policies (Facility Form), including this policy, applicable to such 
common occurrence shall be the sum of the limits of liability of all 
such policies, the limit of liability of each such policy being as 
determined by Condition 3 thereof, but in no event shall such total 
aggregate liability of the companies exceed $_______;\1\ (2) the total 
liability of the companies under this policy shall not exceed that 
proportion of the total aggregate liability of the companies, as stated 
in clause (1) above, which (a) the limit of liability of this policy, as 
determined by Condition 3, bears to (b) the sum of

[[Page 770]]

the limits of liability of all such policies issued by the companies, 
the limit of liability of each such policy being as determined by 
Condition 3, thereof.
---------------------------------------------------------------------------

    \1\ For policies issued by Nuclear Energy Liability-Property 
Insurance Association the amount will be ``$124,000,000,'' for policies 
issued by Mutual Atomic Energy Liability Underwriters, the amount will 
be ``$36,000,000.''
---------------------------------------------------------------------------

    The provisions of this condition shall not operate to increase the 
limit of the companies' liability under this policy.
    5. Notice of occurrence, claim, or suit. In the event of bodily 
injury or property damage to which this policy applies or of an 
occurrence which may give rise to claims therefor, written notice 
containing particulars sufficient to identify the insured and also 
reasonably obtainable information with respect to the time, place and 
circumstances thereof, and the names and addresses of the injured and of 
available witnesses, shall be given by or for the insured to ______or 
the companies as soon as practicable. If claim is made or suit is 
brought against the insured, he shall immediately forward to _____ or 
the companies every demand, notice, summons or other process received by 
him or his representative.
    6. Assistance and cooperation of the insured. The insured shall 
cooperate with the companies and, upon the companies' request, attend 
hearings and trials and assist in making settlements, securing and 
giving evidence, obtaining the attendance of witnesses and in the 
conduct of any legal proceedings in connection with the subject matter 
of this insurance. The insured shall not, except at his own cost, make 
any payment, assume any obligation or incur any expense.
    7. Action against companies--Coverages A and C. No action shall lie 
against the companies or any of them unless, as a condition precedent 
thereto, the insured shall have fully complied with all the terms of 
this policy, nor until the amount of the insured's obligation to pay 
shall have been finally determined either by judgment against the 
insured after actual trial or by written agreement of the insured, the 
claimant and the companies.
    Any person or organization or the legal representative thereof who 
has secured such judgment or written agreement shall thereafter be 
entitled to recover under this policy to the extent of the insurance 
afforded by this policy. No person or organization shall have any right 
under this policy to join the companies or any of them as parties to any 
action against the insured to determine the insured's liability, nor 
shall the companies or any of them be impleaded by the insured or his 
legal representative. Bankruptcy or insolvency of the insured or of the 
insured's estate shall not relieve the companies of any of their 
obligations hereunder.
    8. Action against companies--Coverage B. No suit or action on this 
policy for the recovery of any claim for property damage to which 
Coverage B applies shall be sustainable in any court of law or equity 
unless all the requirements of this policy shall have been complied with 
and unless commenced within two years after the occurrence resulting in 
such property damage.
    9. Insured's duties when loss occurs--Coverage B. In the event of 
property damage to which Coverage B applies, the insured shall furnish a 
complete inventory of the property damage claimed, showing in detail the 
amount thereof. Within ninety-one days after the occurrence resulting in 
such property damage, unless such time is extended in writing by the 
companies, the insured shall render to the companies a proof of loss, 
signed and sworn to by the insured, stating the knowledge and belief of 
the insured as to the following: identification of such occurrence; the 
interest of the insured in the property destroyed or damaged, and the 
amount of each item of property damage claimed; all encumbrances on such 
property; and all other contracts of insurance, whether valid or not, 
covering any of such property. The insured shall include in the proof of 
loss a copy of all descriptions and schedules in all policies. Upon the 
companies' request, the insured shall furnish verified plans and 
specifications of any such property. The insured, as often as may be 
reasonably required, shall exhibit to any person designated by the 
companies any of such property, and submit to examinations under oath by 
any person named by the companies and subscribe the same; and, as often 
as may be reasonably required, shall produce for examination all books 
of account, records, bills, invoices and other vouchers, or certified 
copies thereof if originals be lost, at such reasonable time and place 
as may be designated by the companies or their representatives, and 
shall permit extracts and copies thereof to be made.
    10. Appraisal--Coverage B. In case the insured and the companies 
shall fail to agree as to the amount of property damage, then, on the 
written demand of either, each shall select a competent and 
disinterested appraiser and notify the other of the appraiser selected 
within twenty days of such demand. The appraisers shall first select a 
competent and disinterested umpire and, failing for fifteen days to 
agree upon such umpire, then, on request of the insured or the 
companies, such umpire shall be selected by a judge of a court of record 
in the state in which the property is located. The appraisers shall then 
appraise each item of property damage and, failing to agree, shall 
submit their differences only to the umpire. An award in writing, so 
itemized, of any two when filed with the companies shall determine the 
amount of property damage. Each appraiser shall be paid by the party 
selecting him and the expenses of the appraisal and umpire shall be paid 
by the parties equally. The companies shall not be held to have waived 
any of their rights by any act relating to appraisal.

[[Page 771]]

    11. Subrogation. In the event of any payment under this policy, the 
companies shall be subrogated to all the insured's rights of recovery 
therefor against any person or organization, and the insured shall 
execute and deliver instruments and papers and do whatever else is 
necessary to secure such rights. Prior to knowledge of bodily injury or 
property damage caused by the nuclear energy hazard the insured may 
waive in writing any right or recovery against any person or 
organization, but after such knowledge the insured shall not waive or 
otherwise prejudice any such right of recovery.
    The companies hereby waive any rights of subrogation acquired 
against the United States of America or any of its agencies by reason of 
any payment under this policy.
    The companies do not relinquish, by the foregoing provisions, any 
right to restitution from the insured out of any recoveries made by the 
insured on account of a loss covered by this policy of any amounts to 
which the companies would be entitled had such provisions, or any of 
them, not been included in this policy.
    12. Other insurance. If the insurance afforded by this policy for 
loss or expense is concurrent with insurance afforded for such loss or 
expense by a Nuclear Energy Liability Policy (Facility Form) issued to 
the named insured by _____ hereinafter called ``concurrent insurance,'' 
the companies shall not be liable under this policy for a greater 
proportion of such loss or expense than the limit of liability stated in 
the declarations of this policy bears to the sum of such limit and the 
limit of liability stated in the declarations of such concurrent policy.
    If the insured has other valid and collectible insurance (other than 
such concurrent insurance or any other nuclear energy liability 
insurance issued by the companies or _____ to any person or 
organization) applicable to loss or expense covered by this policy, the 
insurance afforded by this policy shall be excess insurance over such 
other insurance; provided, with respect to any person who is not 
employed at and in connection with the facility, such insurance as is 
afforded by this policy for bodily injury to an employee of the insured 
arising out of and in the course of his employment shall be primary 
insurance under such other insurance.
    13. Changes. Notice to any agent or knowledge possessed by any agent 
or by any other person shall not effect a waiver or a change in any part 
of this policy or stop the companies from asserting any right under the 
terms of this policy; nor shall the terms of this policy be waived or 
changed except by endorsement issued to form a part of this policy 
executed by _____ on behalf of the companies.
    14. Assignment. Assignment of interest by the named insured shall 
not bind the companies until their consent is endorsed hereon; if, 
however, the named insured shall die or be declared bankrupt or 
insolvent, this policy shall cover such insured's legal representative, 
receiver or trustee as an insured under this policy, but only with 
respect to his liability as such, and then only provided written notice 
of his appointment as legal representative, receiver or trustee is given 
to the companies within ten days after such appointment.
    15. Cancellation. This policy may be canceled by the named insured 
by mailing to the companies and the United States Nuclear Regulatory 
Commission written notice stating when, not less than thirty days 
thereafter, such cancellation shall be effective. This policy may be 
canceled by the companies by mailing to the named insured at the address 
shown in this policy and to the United States Nuclear Regulatory 
Commission written notice stating when, not less than ninety days 
thereafter, such cancellation shall be effective; provided in the event 
of non-payment of premium or if the operator of the facility, as 
designated in the declarations, is replaced by another person or 
organization, this policy may be canceled by the companies by mailing to 
the named insured at the address shown in this policy and to the United 
States Nuclear Regulatory Commission written notice stating when, not 
less than thirty days thereafter, such cancellation shall be effective. 
The mailing of notice as aforesaid shall be sufficient proof of notice. 
The effective date and hour of cancellation stated in the notice shall 
become the end of the policy period. Delivery of such written notice 
either by the named insured or by the companies shall be equivalent to 
mailing.
    Upon termination or cancellation of this policy, other than as of 
the end of December 31 in any year, the earned premium for the period 
this policy has been in force since the preceding December 31 shall be 
computed in accordance with the following provisions:
    (a) If this policy is terminated, pursuant to Condition 3, by reason 
of the exhaustion of the limit of the companies' liability, all premium 
theretofore paid or payable shall be fully earned;
    (b) If the named insured cancels, the earned premium for such period 
shall be computed in accordance with the customary annual short rate 
table and procedure, provided if the named insured cancels after 
knowledge of bodily injury or property damage caused by the nuclear 
energy hazard, all premiums theretofore paid or payable shall be fully 
earned;
    (c) If the companies cancel, the earned premium for such period 
shall be computed pro rata.

Premium adjustment, if any, may be made either at the time cancellation 
is effected or as soon as practicable after cancellation becomes 
effective, but payment or tender of

[[Page 772]]

unearned premium is not a condition of cancellation.
    16. Company representation. (a) Any notice, sworn statement or proof 
of loss which may be required by the provisions of this policy may be 
given to any one of the companies, and such notice, statement or proof 
of loss so given shall be valid and binding as to all companies.
    (b) In any action or suit against the companies, service of process 
may be made on any one of them, and such service shall be deemed valid 
and binding service on all companies.
    (c) _____ is the agent of the companies with respect to all matters 
pertaining to this insurance. All notices or other communications 
required by this policy to be given to the companies may be given to 
such agent, at its office at _____ with the same force and effect as if 
given directly to the companies. Any requests, demands or agreements 
made by such agent shall be deemed to have been made directly by the 
companies.
    17. Authorization of named insured. Except with respect to 
compliance with the obligations imposed on the insured by Conditions 5, 
6, 7, 8, 9, 10 and 11 of this policy, the named insured is authorized to 
act for every other insured in all matters pertaining to this insurance.
    18. Changes in subscribing companies and in their proportionate 
liability. By acceptance of this policy the named insured agrees that 
the members of _____ liable under this policy, and the proportionate 
liability of each such member, may change from year to year, and further 
agrees that regardless of such changes:
    (1) Each company subscribing this policy upon its issuance shall be 
liable only for its stated proportion of any obligation assumed or 
expense incurred under this policy because of bodily injury or property 
damage caused, during the period from the effective date of this policy 
to the close of December 31 next following, by the nuclear energy 
hazard; for each subsequent calendar year, beginning January 1 next 
following the effective date of this policy, the subscribing companies 
and the proportionate liability of each such company shall be stated in 
an endorsement issued to form a part of this policy, duly executed and 
attested by the _____ of ____________ on behalf of each such company, 
and mailed or delivered to the named insured;
    (2) This policy shall remain continuously in effect from the 
effective date stated in the declarations until terminated in accordance 
with Condition 3 or Condition 15;
    (3) Neither the liability of any company nor the limit of liability 
stated in the declarations shall be cumulative from year to year.
    19. Declarations. By acceptance of this policy the named insured 
agrees that the statements in the declarations are the agreements and 
representations of the named insured, that this policy is issued in 
reliance upon the truth of such representations and that this policy 
embodies all agreements between the named insured and the companies or 
any of their agents relating to this insurance.
    In Witness Whereof, each of the subscribing companies has caused 
this policy to be executed and attested on its behalf by the ____ of 
__________ and duly countersigned on the declarations page by an 
authorized representative.
    For the subscribing companies.
                                                        By _____________

                Subscribing Companies Proportion of 100%

         Nuclear Energy Liability Policy No.____ (Facility Form)

                              Declarations

    Item 1. Named Insured ________.
Address ________________.
(No. Street Town or City State)
    Item 2. Policy Period: Beginning at 12:01 a.m. on the _____ day of 
_______, 19__, and continuing through the effective date of the 
cancellation or termination of this policy, standard time at the address 
of the named insured as stated herein.
    Item 3. Description of the Facility:

Location________________________________________________________________

Type____________________________________________________________________

    The Operator of the facility is ____.
    Item 4. The limit of the companies' liability is $___ subject to all 
the terms of this policy having reference thereto.
    Item 5. Advance Premium $___.
    Item 6. These declarations and the schedules forming a part hereof 
give a complete description of the facility, insofar as it relates to 
the nuclear energy hazard, except as noted __________________

    Date of Issue ______, 19__.
Countersigned by _____________
                                             (Authorized representative)

                     Nuclear Energy Liability Policy

                             (Facility Form)

   Amendment of Transportation Coverage (Indemnified Nuclear Facility)

    It is agreed that the definition of insured shipment in Insuring 
Agreement III is amended to read: insured shipment means a shipment of 
source material, special nuclear material, spent fuel or waste, herein 
called material, (1) to the facility from any location except an 
indemnified nuclear facility, but only if the transportation of the 
material is not by predetermination to be interrupted by removal of the 
material from a transporting conveyance for any purpose other than the

[[Page 773]]

continuation of its transportation, or (2) from the facility to any 
other location, but only until the material is removed from a 
transporting conveyance for any purpose other than the continuation of 
its transportation.
    Effective date of this endorsement ___ to form a part of Policy No. 
___.
Issued to _______________
Date of Issue _____________.
    For the subscribing companies.
________________________________________________________________________
                                                      By _______________
Countersigned by _____________
Endorsement No. _______.

                     Optional Amendatory Endorsement

                             (Facility Form)

    It is agreed that:
    I. The first sentence of the definition of nuclear facility is 
amended to read:
nuclear facility means the facility as defined in any Nuclear Energy 
Liability Policy (Facility Form) issued by _____ or by ________.
    II. The definition of indemnified nuclear facility is replaced by 
the following:
indemnified nuclear facility means
    (1) the facility as defined in any Nuclear Energy Liability Policy 
(Facility Form) issued by ____ or by ____ or
    (2) any other nuclear facility,

if financial protection is required pursuant to the Atomic Energy Act of 
1954, or any law amendatory thereof; with respect to any activities or 
operations conducted thereat:
    III. Condition 4 is replaced by the following:
    Limitation of liability; common occurrence. Any occurrence or series 
of occurrences resulting in bodily injury or property damage arising out 
of the radioactive, toxic, explosive, or other hazardous properties of
    (a) nuclear material discharged or dispersed from the facility over 
a period of days, weeks, months or longer and also arising out of such 
properties of other nuclear material so discharged or dispersed from one 
or more other nuclear facilities insured under any Nuclear Energy 
Liability Policy (Facility Form) issued by ______ or,
    (b) source material, special nuclear material, spent fuel or waste 
in the course of transportation for which insurance is afforded under 
this policy and also arising out of such properties of other source 
material, special nuclear material, spent fuel or waste in the course of 
transportation for which insurance is afforded under one or more other 
Nuclear Energy Liability Policies (Facility Form) issued by ________.

shall be deemed to be a common occurrence resulting in bodily injury or 
property damage caused by the nuclear energy hazard.
    With respect to such bodily injury and property damage (1) the total 
aggregate liability of the members of ____, under all Nuclear Energy 
Liability Policies (Facility Form), including this policy, applicable to 
such common occurrence shall be the sum of the limits of liability of 
all such policies, the limit of liability of each such policy being as 
determined by Condition 3 thereof, but in no event shall such total 
aggregate liability of such members exceed $____;\1\ (2) the total 
liability of the companies under this policy shall not exceed that 
proportion of the total aggregate liability of the members of ____, as 
stated in clause (1) above, which (a) the limit of liability of this 
policy, as determined by Condition 3, bears to (b) the sum of the limits 
of liability of all such policies issued by such members the limit of 
liability of each such policy being as determined by Condition 3 
thereof.
---------------------------------------------------------------------------

    \1\ For policies issued by Nuclear Energy Liability-Property 
Insurance Association the amount will be ``$124,000,000,'' for policies 
issued by Mutual Atomic Energy Liability Underwriters, the amount will 
be ``$36,000,000.''
---------------------------------------------------------------------------

    The provisions of this condition shall not operate to increase the 
limit of the companies' liability under this policy.
    IV. The second paragraph of Condition 12 Other Insurance is amended 
to read:
    If the insured has other valid and collectible insurance (other than 
such concurrent insurance or any other nuclear energy liability 
insurance issued by ____ or to any person or organization) applicable to 
loss or expense covered by this policy the insurance afforded by this 
policy shall be excess insurance over such other insurance; provided, 
with respect to any person who is not employed at and in connection with 
the facility, such insurance as is afforded by this policy for bodily 
injury to an employee of the insured arising out of and in the course of 
his employment shall be primary insurance under such other insurance.

                     Nuclear Energy Liability Policy

                             (Facility Form)

              Restoration of Limit of Liability Endorsement

    It is agreed that:
    1. Payments made by the companies under this policy have reduced the 
limit of the companies' liability, stated in Item 4 of the declarations, 
to $____.
    2. Such reduced limit is restored to the amount stated in Item 4 of 
the declarations. Such restored limit applies to obligations assumed or 
expenses incurred because of bodily injury or property damage caused 
during the period from the effective date of this endorsement to the 
termination of the policy, by the nuclear energy hazard.


[[Page 774]]


    Note: When the reduction of the limit of liability results from a 
clearly identifiable nuclear event and restoration is offered 
retroactive to the effective date of the policy for claims other than 
those resulting from said event, above paragraph 2 will be replaced by 
the following:
    2. Such reduced limit is restored to the amount stated in Item 4 of 
the declarations, except with respect to bodily injury or property 
damage resulting from (describe nuclear event).

    3. The reduced limit of liability stated in paragraph 1 above, and 
the limit of liability stated in Item 4 of the declarations, as restored 
by this endorsement, shall not be cumulative; and each payment made by 
the companies after the effective date of this endorsement for any loss 
or expense covered by the policy shall reduce by the amount of such 
payment both the reduced limit of liability stated in paragraph 1 above 
and the limit of liability stated in Item 4 of the declarations, as 
restored by this endorsement, regardless of which limit of liability 
applies with respect to bodily injury or property damage out of which 
such loss or expense arises.
    Effective date of this endorsement ___to form a part of Policy No. 
____
    Issued to ______.
    Date of Issue ______.
    For the subscribing companies

________________________________________________________________________
                                                             By ________
Countersigned by _____________
Endorsement No. ___.

                     Nuclear Energy Liability Policy

                             (Facility Form)

                         Amendatory Endorsement

    This policy does not apply to bodily injury or property damage with 
respect to which the insured is entitled to indemnity from the United 
States Nuclear Regulatory Commission under the provisions of Indemnity 
Agreement No. ___ between the United States Nuclear Regulatory 
Commission and _____, dated _____, as now in effect or as hereafter 
amended.

                                * * * * *

    Effective date of this endorsement to form a part of Policy No.
    Issued to _____.
    Date of issue _____.
    For the subscribing companies ____

                                                        By _____________
Countersigned by ______________
Endorsement No. ___.

                     Nuclear Energy Liability Policy

                             (Facility Form)

                     Waiver of Defenses Endorsement

                   (Extraordinary Nuclear Occurrence)

    The named insured, acting for himself and every other insured under 
the policy, and the members of ____________ agree as follows:
    1. With respect to any extraordinary nuclear occurrence to which the 
policy applies as proof of financial protection and which--
    (a) Arises out of or results from or occurs in the course of the 
construction, possession, or operation of the facility, or
    (b) Arises out of or results from or occurs in the course of the 
transportation of nuclear material to or from the facility, the insureds 
and the companies agree to waive
    (1) Any issue or defense as to the conduct of the claimant or the 
fault of the insureds, including, but not limited to:
    (i) Negligence,
    (ii) Contributory negligence,
    (iii) Assumption of risk, and
    (iv) Unforeseeable intervening causes whether involving the conduct 
of a third person or an act of God,
    (2) Any issue or defense as to charitable or governmental immunity, 
and
    (3) Any issue or defense based on any statue of limitations if suit 
is instituted within 3 years from the date on which the claimant first 
knew, or reasonably could have known, of his bodily injury or property 
damage and the cause thereof, but in no event more than 10 years after 
the date of the nuclear incident.

The waiver of any such issue or defense shall be effective regardless of 
whether such issue or defense may otherwise be deemed jurisdictional or 
relating to an element in the cause of action.
    2. The waivers set forth in paragraph 1 above do not apply to
    (a) Bodily injury or property damage which is intentionally 
sustained by the claimant or which results from a nuclear incident 
intentionally and wrongfully caused by the claimant;
    (b) Bodily injury sustained by any claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefor are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law;
    (c) Any claim for punitive or exemplary damages, provided, with 
respect to any claim for wrongful death under any State law which 
provides for damages only punitive in nature, this exclusion does not 
apply to the extent that the claimant has sustained actual damages, 
measured by the pecuniary injuries resulting from such death but not to

[[Page 775]]

exceed the maximum amount otherwise recoverable under such law.
    3. The waivers set forth in paragraph 1 above shall be effective 
only with respect to bodily injury or property damage to which the 
policy applies under its terms other than this endorsement.
    Such waivers shall not apply to, or prejudice the prosecution or 
defense of any claim or portion of claim which is not within the 
protection afforded under--
    (1) The provisions of the policy applicable to the financial 
protection required of the named insured,
    (2) The agreement of indemnification between the named insured and 
the Nuclear Regulatory Commission made pursuant to section 170 of the 
Atomic Energy Act of 1954, as amended, and
    (3) The limit of liability provisions of subsection 170 e. of the 
Atomic Energy Act of 1954, as amended.

Such waivers shall not preclude a defense based upon the failure of the 
claimant to take reasonable steps to mitigate damages.
    4. Subject to all of the limitations stated in this endorsement and 
in the Atomic Energy Act of 1954, as amended, the waivers set forth in 
paragraph 1 above shall be judicially enforceable in accordance with 
their terms against any insured in an action to recover damages because 
of bodily injury or property damage to which the policy applies as proof 
of financial protection.
    5. As used herein:
    Extraordinary nuclear occurrence means an event which the Nuclear 
Regulatory Commission has determined to be an extraordinary nuclear 
occurrence as defined in the Atomic Energy Act of 1954, as amended, 
financial protection and nuclear incident have the meanings given them 
in the Atomic Energy Act of 1954, as amended.
    Claimant means the person or organization actually sustaining the 
bodily injury or property damage and also includes his assignees, legal 
representatives and other persons or organizations entitled to bring an 
action for damages on account of such injury or damage.

                     Nuclear Energy Liability Policy

                             (Facility Form)

                         Amendatory Endorsement

                         (Application of Policy)

    It is agreed that insuring agreement IV of the policy, captioned 
Application of Policy is amended to read as follows: Application of 
Policy. This policy applies only to bodily injury or property damage: 
(1) Which is caused during the policy period by the nuclear energy 
hazard, and (2) which is discovered and for which written claim is made 
against the insured, not later than 10 years after the end of the policy 
period.

                     Nuclear Energy Liability Policy

                             (Facility Form)

                      Waiver of Defense Endorsement

                   (Extraordinary Nuclear Occurrence)

The named insured, acting for himself and every other insured under the 
policy, and the members of______________________________________________
agree as follows:
    1. With respect to any extraordinary nuclear occurrence to which the 
policy applies as proof of financial protection and which
    (a) Arises out of or results from or occurs in the course the 
construction, possession, or operation of the facility, or
    (b) Arises out of or results from or occurs in the course of the 
transportation of nuclear material to or from the facility.

the insured and the companies agree to waive.
    (1) Any issue or defense as to the conduct of the claimant or the 
fault of the insureds, including but not limited to:
    (i) Negligence,
    (ii) Contributory negligence,
    (iii) Assumption of risk, and
    (iv) Unforeseeable intervening causes, whether involving the conduct 
of a third person, or an act of God,
    (2) Any issue or defense as to charitable or governmental immunity, 
and
    (3) Any issue or defense based on any statute of limitations if suit 
is instituted within three (3) years from the date on which the claimant 
first knew, or reasonably could have known, of his bodily injury or 
property damage and the cause thereof, but in no event more than twenty 
(20) years after the date of the nuclear incident.

The waiver of any such issue or defense shall be effective regardless of 
whether such issue or defense may otherwise be deemed jurisdictional or 
relating to an element in the cause of action.
    2. The waivers set forth in paragraph 1. above do not apply to
    (a) Bodily injury or property damage which is intentionally 
sustained by the claimant or which results from a nuclear incident 
intentionally and wrongfully caused by the claimant;
    (b) Bodily injury sustained by any claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefor are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law;
    (c) Any claim for punitive or exemplary damages, provided, with 
respect to any claim for wrongful death under any State law which 
provides for damages only punitive in

[[Page 776]]

nature, this exclusion does not apply to the extent that the claimant 
has sustained actual damages, measured by the pecuniary injuries 
resulting from such death but not to exceed the maximum amount otherwise 
recoverable under such law.
    3. The waivers set forth in paragraph 1. above shall be effective 
only with respect to bodily injury or property damage to which the 
policy applies under its terms other than this endorsement; provided, 
however, that with respect to bodily injury or property damage resulting 
from an extraordinary nuclear occurrence. Insuring Agreement IV, 
``Application of Policy,'' shall not operate to bar coverage for bodily 
injury or property damage (a) which is caused during the policy period 
by the nuclear energy hazard and (b) which is discovered and for which 
written claim is made against the insured not later than twenty (20) 
years after the date of the extraordinary nuclear occurrence.
    Such waivers shall not apply to, or prejudice the prosecution or 
defense of any claim or portion of claim which is not within the 
protection afforded under
    (a) The provisions of the policy applicable to the financial 
protection required of the named insured;
    (b) The agreement of indemnification between the named insured and 
the Nuclear Regulatory Commission made pursuant to section 170 of the 
Atomic Energy Act of 1954, as amended; and
    (c) The limit of liability provisions of Subsection 170e. of the 
Atomic Energy Act of 1954, as amended.
    Such waivers shall not preclude a defense based upon the failure of 
the claimant to take reasonable steps to mitigate damages.
    4. Subject to all of the limitations stated in this endorsement and 
in the Atomic Energy Act of 1954, as amended, the waivers set forth in 
paragraph 1. above shall be judicially enforceable in accordance with 
their terms against any insured in an action to recover damages because 
of bodily injury or property damage to which the policy applies as proof 
of financial protection.
    5. As used herein:
    Extraordinary nuclear occurrence means an event which the Nuclear 
Regulatory Commission has determined to be an extraordinary nuclear 
occurrence as defined in the Atomic Energy Act of 1954, as amended.
    Financial protection and nuclear incident have the meanings given 
them in the Atomic Energy Act of 1954, as amended.
    Claimant means the person or organization actually sustaining the 
bodily injury or property damage and also includes his assignees, legal 
representatives and other persons or organizations entitled to bring an 
action for damages on account of such injury or damage.
    Effective date of this endorsement ____________ to form a part of 
Policy No. _______,
 12:01 A.M. Standard Time
    Issued to _________________.
    Date of issue _______.
    Endorsement No. _______.
    For the subscribing companies:
     By ___________,
     General Manager
     Countersigned by ____________.

              Supplementary Endorsement Waiver of Defenses

                  Reactor Construction at the Facility

    It is agreed that in construing the application of paragraph 2.(b) 
of the Waiver of Defenses Endorsement (NE-33a) with respect to an 
extraordinary nuclear occurrence occurring at the facility, a claimant 
who is employed at the facility in connection with the construction of a 
nuclear reactor with respect to which no operating license has been 
issued by the Nuclear Regulatory Commission shall not be considered as 
employed in connection with the activity where the extraordinary nuclear 
occurrence takes place if:
    (1) The claimant is employed exclusively in connection with the 
construction of a nuclear reactor, including all related equipment and 
installations at the facility and
    (2) No operating license has been issued by the Nuclear Regulatory 
Commission with respect to the nuclear reactor, and
    (3) The claimant is not employed in connection with the possession, 
storage, use or transfer of nuclear material at the facility.
    Effective date of this endorsement ____________ to form a part of 
Policy No. _______.
 12:01 A.M. Standard Time
    Issued to _________________.
    Date of issue _______.
    Endorsement No _______.
    For the subscribing companies:
     By ___________,
     General Manager
     Countersigned by ___________.

                     Nuclear Energy Liability Policy

                             (Facility Form)

 Amendment of Definition of Nuclear Energy Hazard (Indemnified Nuclear 
                                Facility)

    It is agreed that: 1. Solely with respect to an insured shipment to 
which the policy applies as proof of financial protection required by 
the Nuclear Regulatory Commission, subdivision (2) of the definition of 
nuclear energy hazard is amended to read:

[[Page 777]]

    (2) The nuclear material is in an insured shipment which is away 
from any other nuclear facility and is in the course of transportation, 
including handling and temporary storage incidental thereto, within
    (a) The territorial limits of the United States of America, its 
territories or possessions, Puerto Rico or the Canal Zone; or
    (b) International waters or airspace, provided that the nuclear 
material is in the course of transportation between two points located 
within the territorial limits described in (a) above and there are no 
deviations in the course of the transportation for the purpose of going 
to any other country, state or nation, except a deviation in the course 
of said transportation for the purpose of going to or returning from a 
port or place of refuge as the result of an emergency.
    2. As used herein, financial protection has the meaning given it in 
the Atomic Energy Act of 1954, as amended.
    Instructions--This form is to be used to modify all Nuclear Energy 
Liability Facility Forms in force on January 1, 1977 which were issued 
to become effective prior to January 1, 1977 and which are offered by 
the named insured as proof of financial protection being maintained as 
required by the Atomic Energy Act of 1954, as amended.
    Effective date of this Endorsement ____________ To form a part of 
Policy No. _______.
12:01 A.M. Standard Time
    Issued to _________________
    Date of issue _______.
    Endorsement No. _______.
    For the subscribing companies:
     By ___________,
     General Manager
     Countersigned by ____________.

                     Nuclear Energy Liability Policy

                             (Facility Form)

 Amendment of Definitions of Nuclear Energy Hazard and Insured Shipment 
                     (Indemnified Nuclear Facility)

    It is agreed that: I. In Insuring Agreement III, DEFINITIONS
    A. Solely with respect to an insured shipment to which this policy 
applies as proof of financial protection required by the Nuclear 
Regulatory Commission, Subdivision (2) of the definition of nuclear 
energy hazard is amended to read:
    (2) The nuclear material is in an insured shipment which is away 
from any other nuclear facility and is in the course of transportation, 
including the handling and temporary storage incidental thereto, within
    (a) The territorial limits of the United States of America, its 
territories or possessions, Puerto Rico or the Canal Zone; or
    (b) International waters or airspace, provided that the nuclear 
material is in the course of transportation between two points located 
within the territorial limits described in (a) above and there are no 
deviations in the course of the transportation for the purpose of going 
to any other country, state or nation, except for a deviation in the 
course of said transportation for the purpose of going to or returning 
from a port or place of refuge as the result of an emergency.
    B. The definition of insured shipment is replaced with the 
following:
    Insured shipment means a shipment of source material, special 
nuclear material, spent fuel or waste, herein called material, (1) to 
the facility from any location except an indemnified nuclear facility, 
but only if the transportation of the material is not by 
predetermination to be interrupted by removal of the material from a 
transporting conveyance for any purpose other than the continuation of 
its transportation, or (2) from the facility to any other location, but 
only until the material is removed from a transporting conveyance for 
any purpose other than the continuation of its transportation.
    II. As used herein, financial protection has the meaning given it in 
the Atomic Energy Act of 1954, as amended.
    Instructions--This form is to be used to modify all Nuclear Energy 
Liability Facility Forms which are issued to become effective on or 
after January 1, 1977 and which are offered by the named insured as 
proof of financial protection being maintained as required by the Atomic 
Energy Act of 1954, as amended.
    Effective date of this endorsement __________ To form a part of 
Policy No. _______.
12:01 A.M. standard time
    Issued to ____________.
    Date of issue _______.
    Endorsement No. _______.
    For the subscribing companies:
     By ____________,
     General Manager.
    Countersigned by ___________.

                 NE-50 (1/1/80), Amendatory Endorsement

                     (Indemnified Nuclear Facility)

    It is agreed that:
    I. In Insuring Agreement III:
    DEFINITIONS
    A. The first sentence of the definition of nuclear facility is 
amended to read: nuclear facility means the facility as defined in any 
Nuclear Energy Liability Policy (Facility Form) issued by Nuclear Energy 
Liability Insurance Association or by Mutual Atomic Energy Liability 
Underwriters.
    B. The definition of indemnified nuclear facility is replaced by the 
following: indemnified nuclear facility means
    (1) the facility as defined in any Nuclear Energy Liability Policy 
(Facility Form) issued

[[Page 778]]

by Nuclear Energy Liability Insurance Association or by Mutual Atomic 
Energy Liability Underwriters, or
    (2) any other nuclear facility, if financial protection is required 
pursuant to the Atomic Energy Act of 1954, or any law amendatory 
thereof, with respect to any activities or operations conducted thereat;
    C. Solely with respect to an insured shipment to which this policy 
applies as proof of financial protection required by the Nuclear 
Regulatory Commission. Subdivision (2) of the definition of nuclear 
energy hazard is amended to read:
    (2) The nuclear material is in an insured shipment which is away 
from any other nuclear facility and is in the course of transportation, 
including the handling and temporary storage incidental thereto, within
    (a) The territorial limits of the United States of America, its 
territories or possessions, or Puerto Rico; or Canal Zone; or
    (b) International waters or airspace, provided that the nuclear 
material is in the course of transportation between two points located 
within the territorial limits described in (a) above and there are no 
deviations in the course of the transportation for the purpose of going 
to any other country, state or nation, except a deviation in the course 
of said transportation for the purpose of going to or returning from a 
port or place of refuge as the result of an emergency.
    D. The definition of insured shipment is replaced with the 
following:
    insured shipment means shipment of source material, special nuclear 
material, spent fuel or waste, or tailings or wastes produced by the 
extraction or concentration of uranium or thorium from any ore processed 
primarily for its source material content, herein called material, (1) 
to the facility from any location except an indemnified nuclear 
facility, but only if the transportation of the material is not by 
predetermination to be interrupted by removal of the material from a 
transporting conveyance for any purpose other than the continuation of 
its transportation, or (2) from the facility to any other location, but 
only until the material is removed from a transporting conveyance for 
any purpose other than the continuation of its transportation.
    E. As used herein, financial protection has the meaning given it in 
the Atomic Energy Act of 1954, as amended.
    II. Insuring Agreement IV is replaced by the following:
    IV. APPLICATION OF POLICY. This policy applies only to bodily injury 
or property damage (1) which is caused during the policy period by the 
nuclear energy hazard and (2) which is discovered and for which written 
claim is made against the insured, not later than ten years after the 
end of the policy period.
    III. Condition 2 is replaced by the following:
    2. INSPECTION: SUSPENSION. The companies shall at any time be 
permitted but not obligated to inspect the facility and all operations 
relating thereto and to examine the insured's books and records as far 
as they relate to the subject of this insurance and any property 
insurance afforded the insured through American Nuclear Insurers. If a 
representative of the companies discovers a condition which he believes 
to be unduly dangerous with respect to the nuclear energy hazard, a 
representative of the companies may request that such condition be 
corrected without delay. In the event of noncompliance with such 
request, a representative of the companies may, by notice to the named 
insured, to any other person or organization considered by the companies 
to be responsible for the continuation of such dangerous condition, and 
to the United States Nuclear Regulatory Commission, suspend this 
insurance with respect to named insured and such other person or 
organization effective 12:00 midnight of the next business day of such 
Commission following the date that such Commission receives such notice. 
The period of such suspension shall terminate as of the time stated in a 
written notice from the companies to the named insured and to each such 
person or organization that such condition has been corrected.
    Neither the right to make such inspections and examinations nor the 
making thereof nor any advice or report resulting therefrom shall 
constitute an undertaking, on behalf of or for the benefit of the 
insured or others, to determine or warrant that such facility or 
operations are safe or healthful, or are in compliance with any law, 
rule or regulation. In consideration of the issuance or continuation of 
this policy, the insured agrees that neither the companies nor any 
pesons or organizations making such inspections or exminations on their 
behalf shall be liable with respect to injury to or destruction of 
property at the facility, or any consequential loss or expense resulting 
therefrom, or any loss resulting from interruption of business or 
manufacture, arising out of the making of or a failure to make any such 
inspection or examination, or any report thereon, or any such suspension 
of insurance, but this provision does not limit the contractual 
obligations of the companies under this policy or any policy affording 
the insured property insurance through American Nuclear Insurers.
    IV. Condition 4 is replaced by the following:
    4. LIMITATION OF LIABILITY: COMMON OCCURRENCE. Any occurrence or 
series of occurrences resulting in bodily injury or property damage 
arising out of the radioactive, toxic, explosive or other hazardous 
properties of

[[Page 779]]

    (a) nuclear material discharged or dispersed from the facility over 
a period of days, weeks, months or longer and also arising out of the 
properties of other nuclear material so discharged or dispersed from one 
or more other nuclear facilities insured under any Nuclear Energy 
Liability Policy (Facility Form) issued by Nuclear Energy Liability 
Insurance Association, or
    (b) source material, special nuclear material, spent fuel or waste 
in the course of transportation for which insurance is afforded under 
this policy and also arising out of such properties of other source 
material, special nuclear material, spent fuel or waste in the course of 
transportation for which insurance is afforded under one or more other 
Nuclear Energy Liability Policies (Facility Form) issued by Nuclear 
Energy Liability Insurance Association, shall be deemed to be a common 
occurrence resulting in bodily injury or property damage caused by the 
nuclear energy hazard.
    With respect to such bodily injury and property damage (1) the total 
aggregate liability of the members of the Nuclear Energy Liability 
Insurance Association under all Nuclear Energy Liability Policies 
(Facility Form), including this policy, applicable to such common 
occurrence shall be the sum of the limits of liability of all such 
policies, the limit of liability of each such policy being as determined 
by Condition 3 thereof, but in no event shall such total aggregate 
liability of such members exceed $124,000,000; (2) the total liability 
of the companies under this policy shall not exceed that proportion of 
the total aggregate liability of the members of Nuclear Energy Liability 
Insurance Association, as stated in clause (1) above, which (a) the 
limit of liability of this policy, as determined by Condition 3, bears 
to (b) the sum of the limits of liability of all such policies issued by 
such members, the limit of liability of each such policy being as 
determined by Condition 3 thereof.
    The provisions of this condition shall not operate to increase the 
limit of the companies' liability under this policy.
    V. The second paragraph of Condition 12, Other Insurance, is amended 
to read:
    If the insured has other valid and collectible insurance (other than 
such concurrent insurance or any other nuclear energy liability 
insurance issued by Nuclear Energy Liability Insurance Association or 
Mutual Atomic Energy Liability Underwriters to any person or 
organization) applicable to loss or expense covered by this policy, the 
insurance afforded by this policy shall be excess insurance over such 
other insurance; provided, with respect to any person who is not 
employed at and in connection with the facility, such insurance as is 
afforded by this policy for bodily injury to an employee of the insured 
arising out of and in the course of his employment shall be primary 
insurance under such other insurance.
    VI. Paragraph (c) of Condition 16, Company Representation, is 
amended to read:
    (c) Nuclear Energy Liability Insurance Association is the agent of 
the companies with respect to all matters pertaining to this insurance. 
All notices or other communications required by this policy to be given 
to the companies may be given to such agent, at its office at the 
Exchange, Suite 245, 270 Farmington Avenue, Farmington, Connecticut 
06032, with the same force and effect as if given directly to the 
companies. Any requests, demand or agreements made by such agent shall 
be deemed to have been made directly by the companies.
    Effective Date of this Endorsement ____ 12:01 a.m. Standard Time to 
form a part of policy No. ___.
    Issued to ____ For the subscribing companies.
    Date of Issue ____.
    By ____ General Manager.
Endorsement No._________________________________________________________
NE-50 (1/1/81)

   NE-51 (1/1/81)--Amendment of Definition of Condition 2 Inspection; 
                     Suspension and Insured Shipment

                     (Indemnified Nuclear Facility)

    It is agreed that:
    (1) Condition 2 Inspection; Suspension is replaced by the following:
    2. Inspection; Suspension. The companies shall at any time be 
permitted but not obligated to inspect the facility and all operations 
relating thereto and to examine the insured's books and records as far 
as they relate to the subject of this insurance and any property 
insurance afforded the insured through American Nuclear Insurers. If a 
representative of the companies discovers a condition which he believes 
to be unduly dangerous with respect to the nuclear energy hazard, a 
representative of the companies may request that such conditions be 
corrected without delay. In the event of noncompliance with such 
requests, a representative of the companies may, by notice to the named 
insured, to any other person or organization considered by the companies 
to be responsible for the continuation of such dangerous condition, and 
to the United States Nuclear Regulatory Commission, suspend this 
insurance with respect to the named insured and such other person or 
organization effective 12:00 midnight of the next business day of such 
Commission following the date that such Commission receives such notice. 
The period of such suspension shall terminate as of the time stated in a 
written notice from the companies to the named insured and to each such 
person or organization that such condition has been corrected.

[[Page 780]]

    Neither the right to make such inspections and examinations nor the 
making thereof nor advice or report resulting therefrom shall constitute 
an undertaking, on behalf of or for the benefit of the insured or 
others, to determine or warrant that such facility or operations are 
safe or healthful, or are in compliance with any law, rule or 
regulation. In consideration of the issuance or continuation of this 
policy, the insured agrees that neither the companies nor any persons or 
organizations making such inspections or examinations on their behalf 
shall be liable with respect to injury to or destruction of property at 
the facility, or any consequential loss or expense resulting therefrom, 
or any loss resulting from interruption of business or manufacture, 
arising out of the making of or a failure to make any such inspection or 
examination, or any report thereon, or any such suspension of insurance, 
but this provision does not limit the contractual obligations of the 
companies under this policy or any policy affording the insured property 
insurance through American Nuclear Insurers.
    (2) The definition of insured shipment in Insuring Agreement III, 
Definitions, is replaced by the following: insured shipment means a 
shipment of source material, special nuclear material, spent fuel, 
waste, or tailings or wastes produced by the extraction or concentration 
of uranium or thorium from any ore processed primarily for its source 
material content herein called material, (1) to the facility from any 
location except an indemnified nuclear facility, but only if the 
transportation of the material is not by predetermination to be 
interrupted by removal from a transporting conveyance for any purpose 
other than the continuation of its transportation, or (2) from the 
facility to any other location, but only until the material is removed 
from a transporting conveyance for any purpose other than the 
continuation of its transportation.
    Effective Date of this Endorsement ____ 12:01 a.m. Standard Time to 
form a part of Policy No. ___
    Issued to ____ For the subscribing companies.
    Date of Issue ____.
    By ____ General Manager.
Endorsement No._________________________________________________________
NE-51 (1/1/81)

          Amendment of Coverage Endorsement for Workers Claims

                             (Facility Form)

                              NE-64(1/1/88)

                                Preamble

    1. The insurance and rating plan presently used by Nuclear Energy 
Liability Insurance Association (NELIA) and Mutual Atomic Energy 
Liability Underwriters (MAELU) do not make a distinction between workers 
claims arising from catastrophic events and those arising from lesser 
events;
    2. NELIA and MAELU believe that the lack of such a distinction will 
adversely affect their ability to continue to attract from world markets 
very large amounts of nuclear energy liability insurance for the nuclear 
industry;
    3. NELIA and MAELU want to avoid this potential loss of capacity and 
to continue to provide nuclear energy liability insurance for workers 
claims. Accordingly NELIA and MAELU desire to restructure their present 
insurance programs, including this policy, effective January 1, 1988.
    Now, Therefore, the Named Insured and the companies do hereby agree 
as follows:

                             1. Definitions

    When used in reference to this endorsement:
    This policy means the policy of which this endorsement forms a part;
    Nuclear related employment means all work performed at one or more 
than one nuclear facility in the United States of America or in 
connection with the transportation of nuclear material to or from any 
such facility. All of a worker's nuclear related employment shall be 
considered as having begun on the first day of such employment, 
regardless of the number of employers involved or interruptions in such 
employment;
    Worker refers to a person who is or was engaged in nuclear related 
employment;
    Workers claims means claims for damages because of bodily injury to 
a worker caused by the radioactive, toxic, explosive or other hazardous 
properties of nuclear material and arising out of or in the course of 
the worker's nuclear related employment;
    Extraordinary nuclear occurrence means an event which the United 
States Nuclear Regulatory Commission has determined to be an 
extraordinary nuclear occurrence as defined in the Atomic Energy Act of 
1954, or in any law amendatory thereof.

                   2. Application of This Endorsement

    This endorsement applies only to such insurance as is afforded by 
this policy for workers claims which do not arise in whole or in part 
out of an extraordinary nuclear occurrence.

                   3. Exclusion of New Workers Claims

    This policy does not apply to bodily injury to a worker which arises 
in whole or in part out of nuclear related employment that begins on or 
after January 1, 1988.

[[Page 781]]

         4. Application of Policy to Workers Claims Not Excluded

    With respect to such insurance as is afforded by this policy for 
workers claims which are not excluded, Insuring Agreement IV does not 
apply and the following Insuring Agreement IV-A does apply:
    IV-A Application of Policy to Workers Claims. This policy applies 
only to bodily injury (1) which is caused during the policy period by 
the nuclear energy hazard and (2) which is discovered and for which 
written claim is made against the insured not later than the close of 
December 31, 1997.

                5. Availability of Supplemental Insurance

    NELIA and MAELU are offering to make insurance under one or more 
Master Worker Policies available to all holders of Nuclear Energy 
Liability Policies (Facility Form). This offer is contingent on 
sufficient support from policy holders, and may be withdrawn or modified 
by Nelia or Maelu as they deem necessary or appropriate.
    The Master Workers Policies will provide, under their separate terms 
and conditions, coverage for new workers claims. Premiums will be 
subject to a separate Industry Retrospective Rating Plan.
    Coverage under the new master worker policies is not automatic. A 
written request must be submitted to Nelia or Maelu through regular 
market channels.
    It is understood and agreed that all of the provisions of this 
endorsement shall remain in full force and effect without regard to this 
section 5, and without regard to whether or not the Named Insureds 
become insureds under the Master Worker Policies, or whether or not 
NELIA or MAELU terminate such policies or withdraw or modify their offer 
to underwrite such policies.

Executed for the companies

Date____________________________________________________________________

By______________________________________________________________________
(Signature or Authorized Officer)
________________________________________________________________________
(Print or Type Name and Title of Officer)

Executed for the Named Insured

________________________________________________________________________
(Named Insured--Type or Print)

Date____________________________________________________________________

By______________________________________________________________________
(Signature of Authorized Officer)

________________________________________________________________________
(Print or Type Name and Title of Officer)

Effective Date of this Endorsement

________________________________________________________________________
12:01 a.m. Standard Time

To form a part of Policy No.____________________________________________

Issued to_______________________________________________________________

Date of Issue___________________________________________________________

For the subscribing companies

By______________________________________________________________________
General Manager

Endorsement No.
Countersigned by________________________________________________________

AMENDMENT OF COVERAGE ENDORSEMENT FOR WORKERS CLAIMS (Facility Form) NE-
                               66(1/1/88)

    It is agreed that:

                             1. Definitions

    When used in reference to this endorsement:
    This policy means the policy of which this endorsement forms a part;
    Nuclear related employment means all work performed at one or more 
than one nuclear facility in the United States of America or in 
connection with the transportation of nuclear material to or from any 
such facility. All of a worker's nuclear related employment shall be 
considered as having begun on the first day of such employment, 
regardless of the number of employers involved or interruptions in such 
employment;
    Worker refers to a person who is or was engaged in nuclear related 
employment;
    Workers claims means claims for damages because of bodily injury to 
a worker caused by the radioactive, toxic, explosive or other hazardous 
properties of nuclear material and arising out of or in the course of 
the worker's nuclear related employment;
    Extraordinary nuclear occurrence means an event which the United 
States Nuclear Regulatory Commission has determined to be an 
extraordinary nuclear occurrence as defined in the Atomic Energy Act of 
1954, or in any law amendatory thereof.

                   2. Application of This Endorsement

    This endorsement applies only to such insurance as is afforded by 
this policy for workers claims which do not arise in whole or in part 
out of an extraordinary nuclear occurrence.

                   3. Exclusion of New Workers Claims

    This policy does not apply to bodily injury to a worker which arises 
in whole or in part out of nuclear related employment that begins on or 
after January 1, 1988.

         4. Application of Policy to Workers Claims Not Excluded

    With respect to such insurance as is afforded by this policy for 
workers claims which are not excluded, Insuring Agreement IV does not 
apply and the following Insuring Agreement IV-A does apply:

              IV-A Application of Policy to Workers Claims

    This policy applies only to bodily injury (1) which is caused during 
the policy period by

[[Page 782]]

the nuclear energy hazard and (2) which is discovered and for which 
written claim is made against the insured not later that the close of 
December 31, 1997.

                5. Availability of Supplemental Insurance

    NELIA and MAELU are offering to make insurance under one or more 
Master Worker Policies available to all holders of Nuclear Energy 
Liability Policies (Facility Form). This offer is contingent on 
sufficient support from policyholders, and may be withdrawn or modified 
by NELIA or MAELU as they deem necessary or appropriate.
    The Master Worker Policies will provide, under their separate terms 
and conditions, coverage for new workers claims. Premiums will be 
subject to a separate Industry Retrospective Rating Plan.
    Coverage under the new master worker policies is not automatic. A 
written request must be submitted to NELIA or MAELU through regular 
market channels.
    It is understood and agreed that all of the provisions of this 
endorsement shall remain in full force and effect without regard to this 
Section 5, and without regard to whether or not the Named Insureds 
become insureds under the Master Worker Policies, or whether or not 
NELIA or MAELU terminate such policies or withdraw or modify their offer 
to underwrite such policies.
    Explanation of Use of This Endorsement: This endorsement is a 
mandatory endorsement which is to be attached to new Facility Form 
Policies issued on or after January 1, 1988.

Effective Date of this Endorsement

________________________________________________________________________
12:01 a.m. Standard Time

To form a part of Policy No.____________________________________________

Issued to_______________________________________________________________

Date of Issue___________________________________________________________
For the subscribing companies

By______________________________________________________________________
General Manager

Endorsement No.
Countersigned by________________________________________________________

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                     Nuclear Energy Liability Policy

Facility Worker Form, herein called Master Worker Policy, NMWP-1(1/1/88)

    The undersigned members of Nuclear Energy Liability Insurance 
Association, hereinafter called the companies, each itself severally and 
not jointly, and in the respective proportion hereinafter set forth, 
agree with the insureds named in Item 1 of the Declarations of each 
Certificate, hereinafter called the Named Insureds, in consideration of 
the payment of the premium, and subject to all of the provisions of the 
applicable Certificate and of this policy, as follows:

      I--Relation Between the Master Worker Policy and Certificates

    No insurance is provided by this policy except through a Certificate 
issued to form a part hereof. The insurance then applies separately to 
the persons and organizations who are defined in Section IV as insureds 
under each such Certificate, except with respect to the Amount of 
Insurance Available.
    The Amount of Insurance Available through such a Certificate to any 
person or organization who is an insured thereunder is limited as 
provided in Section VIII of this policy.

                             II--Definitions

    When used in reference to this policy:
    Bodily injury means bodily injury, sickness or disease, including 
death resulting therefrom;
    Byproduct material has the meaning given in the Atomic Energy Act of 
1954, or in any law amendatory thereof;
    Certificate, unless qualified, refers to a Certificate of Insurance 
(including Declarations and endorsements forming a part thereof) issued 
to form a part of this policy or of a MAELU Policy;
    Claims costs means, with reference to claims or suits the companies 
have the right and duty to defend under this policy;
    (1) Cost taxed against the insured in such suits and interest on any 
judgments therein;
    (2) Premiums on appeal bonds and on bonds to release attachments in 
such suits (but the companies have no obligation to apply for or furnish 
such bonds;
    (3) Reasonable expenses, other than loss of earnings, incurred by 
the insured at the companies' request;
    (4) Payments for expenses incurred in the investigation, 
negotiation, settlement and defense of such claims or suits, including, 
but not limited to, the cost of such allocated claims services by 
employees of the companies, fees and expenses of independent adjusters, 
attorneys' fees and disbursements, expenses for expert testimony, 
examination, x-ray or autopsy or medical expenses of any kind;
    (5) Payments for expenses incurred by the companies in investigating 
an occurrence resulting in bodily injury or in minimizing its effects;
    Discovery period means the period defined in Section VI B hereof;
    Extraordinary nuclear occurrence means an event which the United 
States Nuclear Regulatory Commission has determined to be an 
extraordinary nuclear occurrence as defined in the Atomic Energy Act of 
1954, or in any law amendatory thereof;

[[Page 783]]

    Insured contract means that part of a contract or agreement made 
prior to bodily injury to a new worker under which the insured assumes 
the tort liability of a third person to pay damages because of such 
bodily injury. Tort liability means a liability that would be imposed by 
law on the third person in the absence of an express assumption of 
liability by the third person;
    Insured facility means a facility with respect to which insurance is 
provided through a Certificate;
    Insured shipment means a shipment of source material, special 
nuclear material, spent fuel or waste (herein called material):
    (1) To the facility from any location other than an insured 
facility, but only if the transportation of the material is not by 
predetermination to be interrupted by removal of the material from a 
transporting conveyance for any purpose other than the continuation of 
its transportation; or
    (2) From the facility to any other location, but only until the 
material is removed from a transporting conveyance for any purpose other 
than the continuation of its transportation;
    MAELU means Mutual Atomic Energy Liability Underwriters;
    MAELU Policy means a Nuclear Energy Liability Policy (Facility 
Worker Form) written by members of MAELU;
    NELIA means Nuclear Energy Liability Insurance Association;
    New worker refers to a person who is or was engaged in nuclear 
related employment that begins on or after January 1, 1988;
    New worker's claim means a claim for damages because of bodily 
injury to a new worker caused by the radioactive, toxic, explosive or 
other hazardous properties of nuclear material and arising out of or in 
the course of the new worker's nuclear related employment;
    Non-ratable incurred losses has the meaning given in Attachment 1 to 
this policy;
    Nuclear energy hazard means the radioactive, toxic, explosive or 
other hazardous properties of nuclear material which is:
    (1) At the facility as described in the applicable Certificate 
issued to form a part of this policy or has been discharged or dispersed 
therefrom without intent to relinquish possession of custody thereof to 
any other person or organization; or
    (2) In an insured shipment that is away from any other insured 
nuclear facility and is in the course of transportation, including 
handling and temporary storage incidental thereto within:
    (a) The territorial limits of the United States of America, its 
territories or possessions or Puerto Rico; or
    (b) International waters or airspace, provided that:
    (i) The nuclear material is in the course of transportation between 
two points located within the territorial limits described in (a) above; 
and
    (ii) There are no deviations in the course of the transportation for 
the purpose of going to any other country, state or nation, except to a 
port or place of refuge in an emergency;
    Nuclear facility means any of the following and includes the site on 
which any of them is located, all operations conducted on such site and 
all premises used for such operations:
    (1) The facility as described in any Certificate;
    (2) Any nuclear reactor;
    (3) Any equipment or device designed or used for:
    (a) Separating the isotopes of uranium or plutonium;
    (b) Processing or utilizing spent fuel; or
    (c) Handling, processing or packaging waste;
    (4) Any equipment or device used for the processing, fabricating or 
alloying of special nuclear material if at any time the total amount of 
such material in the custody of the insured at the premises where such 
equipment of device is located consists of or contains more than 25 
grams of plutonium or uranium 233 or any combination thereof, or more 
than 250 grams of uranium 235;
    (5) Any structure, basin, excavation, premises or place prepared or 
used for the storage or disposal of waste;
    Nuclear material means source material, special nuclear material or 
byproduct material;
    Nuclear reactor means any apparatus designed or used to sustain 
nuclear fission in a self-supporting chain reaction or to contain a 
critical mass of fissionable material;
    Nuclear related employment means all work performed at one or more 
than one nuclear facility in the United States of America or in 
connection with the transportation of nuclear material to or from any 
such facility.
    All of a new worker's nuclear related employment shall be considered 
as having begun on the first day of such employment, regardless of the 
number of employers involved or interruptions in such employment;
    Policy period means the period defined in Section VI A hereof;
    Ratable incurred losses has the meaning given in Attachment 1 to 
this policy;
    Source material has the meaning given in the Atomic Energy Act of 
1954, or in any law amendatory thereof, and also includes tailings or 
wastes produced by the extraction of uranium or thorium from ore 
processed primarily for its source material content;
    Special nuclear material has the meaning given in the Atomic Energy 
Act of 1954, or in any law amendatory thereof;
    Spent fuel means any fuel element or fuel component, solid or 
liquid, which has been used or exposed to radiation in any nuclear 
reactor;

[[Page 784]]

    The facility refers to the facility described in the Declarations of 
a Certificate. It includes the location described in Item 3 thereof and 
all property and operations at such location;
    Waste means any waste material that contains byproduct material and 
results from the operation by any person or organization of:
    (1) Any nuclear reactor; or
    (2) Any equipment or device designed or used for:
    (a) Separating the isotopes of uranium or plutonium;
    (b) Processing or utilizing spent fuel; or
    (c) Handling, processing or packaging such waste material.

                              III--Coverage

    In the event that a new worker's claim is made against a person or 
organization who is an insured under a Certificate issued to form a part 
of this policy:
    (1) The companies shall pay on behalf of the insured all sums which 
the insured shall become legally obligated to pay as damages because of 
bodily injury to which this policy applies, sustained by a new worker 
and caused by the nuclear energy hazard.
    The companies shall have the right and duty to defend any suit 
against the insured alleging such injury and seeking damages payable 
under the terms of this policy. But the companies may make such 
investigation and settlement of any claim or suit seeking such damages 
as they deem appropriate.
    (2) The companies shall also pay, as part of the Amount of Insurance 
Available under this policy, the claims costs relating to any such claim 
or suit.
    (3) The companies' obligation to pay damages and claims costs, and 
to defend any claim and suit ends when the Policy Aggregrate Limit has 
been exhausted pursuant to the provisions of Section VIII.

                        IV--Definition of Insured

    When used in reference to a Certificate issued to form a part of 
this policy, the unqualified word insured means:
    (1) each insured named in Item 1 of the Declarations of the 
Certificate; and
    (2) any other person or organization with respect to legal 
responsibility for damages because of bodily injury to a new worker 
caused by the nuclear energy hazard applicable to the Certificate. This 
subsection (2) does not include as an insured the United States of 
America or any of its agencies except the Tennessee Valley Authority.

                              V--Exclusions

    This policy does not apply:
    (1) To any obligation for which the insured or any carrier as his 
insurer may be held liable under any worker's compensation, unemployment 
compensation or disability benefits law, or under any similar law;
    (2) To bodily injury to any employee of the insured arising out of 
or in the course of employment by the insured; but this exclusion (2) 
does not apply to liability assumed by the insured under an insured 
contract;
    (3) To liability assumed by the insured under contract, other than 
an insured contract;
    (4) To bodily injury to a new worker due to the manufacturing, 
handling or use at the location designated in Item 3 of the Declarations 
of any Certificate, in time of peace or war, of any nuclear weapon or 
other instrument of war utilizing special nuclear material or byproduct 
material;
    (5) To bodily injury to a new worker due to war, whether or not 
declared, civil war, insurrection, rebellion or revolution, or to any 
act or condition incident to any of the foregoing;
    (6) To bodily injury to a new worker arising in whole or in part out 
of an extraordinary nuclear occurrence.

       VI--Policy Period; Discovery Period; Application of Policy

                            A. Policy Period

    The policy period of this policy begins at 12:01 a.m. on January 1, 
1988 and ends at the close of December 31, 1992, Eastern Standard Time, 
or when all Certificates issued to form a part hereof have been 
cancelled, whichever first occurs.

                           B. Discovery Period

    The discovery period for claims made under this policy begins at 
12:01 a.m. on January 1, 1988 and ends at the close of December 31, 
1997, Eastern Standard Time.

                        C. Application of Policy

    This policy applies only to bodily injury to a new worker (1) which 
is caused during the policy period by the nuclear energy hazard and (2) 
which is discovered and for which written claim is first made against 
the insured within the discovery period.

                          VII--Other Insurance

    A. This insurance is primary insurance under any insurance afforded 
by a Master Policy-Nuclear Energy Liability Insurance (Secondary 
Financial Protection) issued by NELIA or MAELU.
    B. If an insured has other valid and collectible insurance, except 
under a MAELU Policy, for loss or expense covered by this policy, this 
shall be excess insurance over such other insurance. If the insured has 
insurance under a MAELU Policy, whether the insurance is collectible or 
not, the companies shall then be liable under this policy only for such 
proportion of loss or expense as the

[[Page 785]]

amount stated as the Policy Aggregate Limit in Section VIII of this 
policy bears to the sum of such amount and the corresponding amount 
stated in the MAELU Policy.

                   VIII--Amount of Insurance Available

                        A. Policy Aggregate Limit

    1. The Policy Aggregate Limit is $124 million. This limit is not 
cumulative from year to year. The limit applies to all new worker's 
claims that qualify for coverage under this policy (herein called 
qualified claims).
    2. The Policy Aggregate Limit applies collectively to all new 
worker's claims. Such claims may be paid by NELIA on behalf of the 
companies as the claims, in NELIA's discretion, become ready for 
disposition, and claims costs may be paid as they become due, all 
without regard to the order in which such claims were made and without 
any obligation to maintain, reserve or use any portion of the Policy 
Aggregate Limit for claims reported under any particular Certificate.

                B. Limitation of the Companies' Liability

    1. Regardless of the number of (a) Certificates issued to form a 
part of this policy, (b) persons and organizations who are insureds 
under such Certificates, (c) qualified claims, or (d) years this policy 
or any such Certificates shall continue in force, the Policy Aggregate 
Limit is the total liability of the companies for all of their 
obligations under this policy, including the defense of suits and the 
payment of damages and claims costs.
    2. This policy provides for certain automatic reinstatements of the 
Policy Aggregate Limit. Regardless of such provision, if, during the 
policy period or thereafter, the total payments of the companies for
    (a) Non-ratable incurred losses, and
    (b) Those ratable incurred losses for which the companies have not 
been reimbursed under the Industry Retrospective Rating Plan Premium 
Endorsement described in Attachment 1 to this policy,

equal $124 million, the Policy Aggregate Limit shall be deemed to be 
exhausted, and shall not be further reinstated except by an endorsement 
issued to form a part of this policy for additional premium as 
determined by the companies.
    C. Reduction and Reinstatement of the Policy Aggregate Limit
    1. Each payment made by the companies in discharge of their 
obligations under this policy shall reduce the Policy Aggregate Limit by 
the amount of such payment.
    2. The companies shall, however, automatically reinstate the policy 
aggregate limit until the total amount of such reinstatements equals 
$124 million, but in no event shall there be any automatic 
reinstatements after the Policy Aggregate Limit is exhausted pursuant to 
the provisions of subsection B.2. above. Thereafter, there shall be no 
further reinstatement of the Policy Aggregate Limit except by an 
endorsement issued to form a part of this policy for additional premium 
as determined by the companies.
    3. It is a condition of this insurance that the companies shall have 
the right to reimburse themselves, as a matter of first priority, from 
funds held by NELIA in the Special Reserve Account described in 
Attachment 1 to this policy or from retrospective premiums received by 
NELIA for this insurance. The amount of reimbursement shall be equal to 
95% of each payment made by the companies with respect to their 
obligations under this policy.

             IX--Insured's Duties in Case of Claims or Suits

    A. Notice of Claims or Suits
    In the event of any claim or suit involving bodily injury to which a 
Certificate issued to form a part of this policy applies, written notice 
containing particulars sufficient to identify the insured and also 
reasonably obtainable information with respect to the time, place and 
circumstances thereof shall be given by or for the insured to the 
companies as soon as practicable. The insured shall immediately forward 
to the companies every demand, notice, summons or other process received 
relating to claims or suits against the insured.
    B. Assistance and Cooperation
    The insured shall cooperate with the companies and, upon their 
request, shall:
    (1) Attend hearings and trials; and
    (2) Assist in making settlements, securing and giving evidence, 
obtaining the attendance of witnesses and in the conduct of any legal 
proceedings in connection with the subject matter of this insurance.
    The insured shall not, except at the insured's own cost, make any 
payment, assume any obligation or incur any expense.

                             X--Subrogation

    In the event of any payment through a Certificate to form a part of 
this policy, the companies shall be subrogated to all the insured's 
rights of recovery therefor against any person or organization, and the 
insured shall execute and deliver instruments and papers, and so 
whatever else is necessary to secure such rights. Prior to knowledge of 
bodily injury caused by the nuclear energy hazard the insured may waive 
in writing any or all right of recovery against any person or 
organization, but after such knowledge the insured shall not waive or 
otherwise prejudice any such right of recovery.
    The companies hereby waive any right of subrogation against (1) any 
other insured of (2) the United States of America or any of its

[[Page 786]]

agencies acquired by reason of any payment under this policy.
    It is a condition of this policy that if an insured makes a recovery 
on account of any such injury, the insured shall repay to the companies 
the amount to which the companies would have been entitled had the 
foregoing provisions, or any of them, not been included in the policy.

                      XI--Inspection and Suspension

    The companies shall be permitted, but not obligated, to inspect at 
any time the facility as described in any Certificate and all books, 
records and operation relating thereto, both with respect to this 
insurance, and any other nuclear energy liability insurance and property 
insurance also afford with respect thereto by members of NELIA, American 
Nuclear Insurers, MAELU or MAERP Reinsurance Association.
    If a representative of the companies discovers a condition which he 
or she believes to be unduly dangerous with respect to the risks insured 
under the Certificate, a representative of the companies may request 
such condition to be corrected without delay. In the event of 
noncompliance with the request, an officer of NELIA may, by written 
notice mailed or delivered to the first Named Insured, with similar 
notice to the United States Nuclear Regulatory Commission, suspend the 
insurance afforded by a Certificate issued by NELIA effective 12:00 
midnight of the next business day of such Commission following the date 
that such Commission receives such notice. The period of such suspension 
shall terminate as of the time stated in a written notice from NELIA to 
the first Named Insured that such condition has been corrected.
    Neither the right to make such inspections or suspensions nor the 
making thereof nor any advice or report resulting therefrom shall 
constitute an undertaking, on behalf of or for the benefit of the Named 
Insureds or others to determine or warrant that the facility or 
operations relating thereto are safe or healthful, or are in compliance 
with any law, rule or regulation.
    In consideration of the issuance or continuation of a Certificate, 
the Named Insureds agree that neither the companies nor any persons or 
organizations making such inspections on their behalf shall be liable 
for damage to the facility or any consequential damage or cost resulting 
therefrom, including but not limited to any such damage or cost relating 
to interruption of business or manufacture, arising out of the making of 
or failure to make any such inspection of the facility, any report 
thereon, or any such suspension of insurance, but this provision does 
not limit the companies' contractual obligations under a Certificate 
issued by NELIA or any policy issued by NELIA or American Nuclear 
Insurers affording the insured nuclear energy liability or property 
insurance.

                    XII--Cancellation of Certificates

    The first Named Insured designated in a Certificate issued to from a 
part of this policy any cancel such Certificate by mailing to the 
companies and the United States Nuclear Regulatory Commission written 
notice stating when, not less than 30 days thereafter, such cancellation 
shall be effective.
    The companies may cancel any such Certificate by mailing to the 
first Named Insured designated therein at the address shown in such 
Certificate and to the United States Nuclear Regulatory Commission 
written notice, stating when, not less than 90 days thereafter, such 
cancellation shall be effective; provided in the event of non-payment of 
premium, or if the operator of the facility, as designated in the 
Declarations of the Certificate, is replaced by another person or 
organization, such Certificate may be cancelled by the companies by 
mailing to the first Named Insured at the address shown therein and to 
the United States Nuclear Regulatory Commission written notice, stating 
when, not less than 30 days thereafter, such cancellation shall be 
effective.
    The mailing of notice as aforesaid shall be sufficient proof of 
notice. The effective date and hour of cancellation stated in the notice 
shall become the end of the Certificate period. Delivery of such written 
notice either by the first Named Insured or the companies shall be 
equivalent to mailing.
    Upon cancellation of a Certificate, other than as of the end of 
December 31 in any year, the earned standard premium for the period such 
Certificate has been in force since the preceding December 31 shall be 
computed in accordance with the following provisions:
    (1) If the first Named Insured cancels, the earned standard premium 
for such period shall be computed in accordance with the customary 
annual short rate table and procedure; provided, however, that if the 
first Named Insured cancels after knowledge of bodily injury caused by 
the nuclear energy hazard, all premiums theretofore paid or payable 
shall be fully earned;
    (2) If the companies cancel, the earned standard premium for such 
period shall be computed pro rata.
    Premium adjustment, if any, may be made either at the time of 
cancellation or as soon as practicable after cancellation becomes 
effective, but payment of tender of unearned premium is not a condition 
of cancellation.
    Cancellation of a Certificate shall not affect the rights and 
obligations of the Named Insureds under the Insureds under the Industry 
Retrospective Rating Plan Premium Endorsement forming a part of the 
Certificate.

[[Page 787]]

                        XIII--General Conditions

                               A. Premium

    The Named Insureds designated in a Certificate issued by NELIA shall 
pay the companies the premiums for the Certificate in accordance with 
the provisions of the Industry Retrospective Rating Plan Premium 
Endorsement described in Attachment 1 to this policy.

                        B. Modifications, Waiver

    The provisions of this policy or a Certificate issued to form a part 
hereof shall not be changed or waived except by an endorsement issued by 
the companies to form a part of the policy or Certificate.

                              C. Assignment

    Assignment of interest under a Certificate issued to form a part of 
this policy shall not bind the companies until their consent is endorsed 
thereon. If, however, a Named Insured shall die or be declared bankrupt 
or insolvent, the Certificate shall cover the Named Insured's legal 
representative, receiver or trustee as an insured, but only with respect 
to liability as such, and then only provided written notice of the 
appointment as legal representative, receiver or trustee is given to the 
companies within 10 days after such appointment.

                                 D. Suit

    No suit or action on a Certificate issued to form a part of this 
policy shall lie against the companies or any of them unless, as a 
condition precedent thereto, the insured shall have fully complied with 
all the terms of the policy, nor until the amount of the insured's 
obligation to pay shall have been finally determined either by judgment 
against the insured after actual trial or by written agreement of the 
insured, the claimant and the companies.
    Any person or organization or the legal representative thereof who 
has secured such judgment of written agreement shall thereafter be 
entitled to recover under the Certificate to the extent of the insurance 
afforded by this policy through the Certificate. No person or 
organization shall have any right under the Certificate to join the 
companies or any of them as parties to any action against the insured to 
determine the insured's liability, nor shall the companies or any of 
them be impleaded by the insured or the insured's legal representative.
    Bankruptcy or insolvency of the insured or the insured's estate 
shall not relieve the companies of any of their obligations under this 
policy.

               E. Authorization of The First Named Insured

    Except with respect to compliance with the obligations imposed on 
the insured by the Sections of this policy entitled Insured's Duties in 
Case of Claims or Suits, Subrogation and Suit, the first Named Insured 
designated in the Declarations of a Certificate issued to form a part of 
this policy is authorized to act for every other insured in all matters 
pertaining to this insurance.

                        F. Insured Representation

    Any notice, sworn statement of proof of Loss which may be required 
by the provisions of this policy may be given to any one of the 
companies specified in the Schedule of Subscribing Companies attached 
hereto. Such notice, statement or proof of Loss so given shall be valid 
and binding on all such companies.
    In any action or suit against such companies, service of process may 
be made on any one of them and such service shall be valid and binding 
service on all such companies.
    Nuclear Energy Liability Insurance Association is the agent of the 
companies with respect to all matters pertaining to this insurance. All 
notices or other communications required by this policy may be given to 
such agent at its office at: Nuclear Energy Liability Insurance 
Association, The Exchange, Suite 245, 270 Farmington Avenue, Farmington, 
Connecticut 06032, with the same force and effect as if given directly 
to the companies. Any requests, demands or agreements made by such agent 
shall be deemed to have been made directly by the companies.

  G. Changes in Subscribing Companies and Their Proportionate Liability

    By acceptance of this policy the Named Insureds agree that the 
members of Nuclear Energy Liability Insurance Association liable under 
this policy, and the proportionate liability of each such member, may 
change from year to year, and further agree that regardless of such 
changes:
    (1) Each company subscribing this policy upon its issuance shall be 
liable only for its stated proportion of any obligation assumed or 
expense incurred under this policy because of bodily injury to new 
workers caused, during the period from the effective date of this policy 
to the close of December 31 next following, by the nuclear energy 
hazard; for each subsequent calendar year, beginning January 1 next 
following the effective date of this policy, any change in the 
subscribing companies and the proportionate liability of each such 
company shall be stated in an endorsement issued to form a part of this 
policy, duly executed and attested by the President of Nuclear Energy 
Liability Insurance Association on behalf of each such company, and a 
copy of which will be mailed or delivered to the first Named Insured of 
each Certificate.

[[Page 788]]

    (2) The liability of any subscribing company shall not be cumulative 
from year to year.

                             H. Declarations

    By acceptance of this Master Worker Policy, the Named Insureds 
designated in a Certificate agree that the statements in such 
Certificate are their agreements and representations, that this Master 
Worker Policy and such Certificate are issued in reliance upon the truth 
of such representations and that this Master Worker Policy and such 
Certificate embody all agreements between such Named Insureds and the 
companies or any of their agents relating to this insurance.
    In Witness Whereof, the companies subscribing this policy have 
caused the policy to be executed and attested on their behalf by the 
President of Nuclear Energy Liability Insurance Association and duly 
countersigned by an authorized representative, but this policy shall be 
binding on each company only to the extent of its designated proportion 
of any obligation assumed or expense incurred under this policy.

For the Subscribing Companies:
Date of Issue: ____ 19__

________________________________________________________________________
Countersigned by: (Authorized Representative)

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                     Nuclear Energy Liability Policy

      (Facility Worker Form) herein called the Master Worker Policy

                Certificate of Insurance, NMWPC-1(1/1/88)

    Certificate No. ___
    This is to certify that the insured named in Item 1 of the 
Declarations hereof, hereinafter called the Named Insureds, have 
obtained insurance under the Master Worker Policy issued by Nuclear 
Energy Liability Insurance Association on behalf of its members. The 
insurance is subject to all of the provisions of the Certificate and the 
Master Worker Policy.

                             1--Declarations

                 Item 1.--Named Insureds and Addresses:

                  Item 2.--Certificate Coverage Period:

    Beginning at 12:01 a.m. January 1, 1988 and ending at the close of 
December 31, 1992, Eastern Standard Time, or at the time and date this 
Certificate is cancelled or terminated, whichever first occurs.

                  Item 3.--Description of the Facility:

    Location:
    Type:
    Operator of the Facility:

                 Item 4.--Amount of Insurance Available:

    The amount of insurance afforded by the Master Worker Policy through 
this Certificate shall be determined by Section VIII of the Master 
Worker Policy and all of the other provisions of the policy relating 
thereto.

                       Item 5.--Advance Premium: $

                      2--Application of Certificate

    This Certificate applies only to bodily injury to a new worker (1) 
which is caused, during the Certificate Coverage Period, by the nuclear 
energy hazard and (2) which is discovered and for which written claim is 
first made against an insured under the Certificate within the discovery 
period of the Master Worker Policy.

                  3--Industry Retrospective Rating Plan

    All insurance under the Master Worker Policy is subject to the 
Industry Retrospective Rating Plan in use by the companies. No insurance 
is provided under this Certificate unless and until the first Named 
Insured has accepted in writing the Industry Retrospective Rating Plan 
Premium Endorsement and a copy of the signed endorsement has been issued 
by the companies to form a part of this Certificate.
    In Witness Whereof, the companies subscribing the Master Worker 
Policy have caused this Certificate to be executed and attested on their 
behalf by the President of Nuclear Energy Liability Insurance 
Association and duly countersigned by an authorized representative.
    For the Subscribing Companies:
    Date of Issue _____ 19 ___
Countersigned by:_______________________________________________________
(Authorized Representative)

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                   Nuclear Energy Liability Insurance

 Industry Retrospective Rating Plan Premium Endorsement, NE-W-1(1/1/88)

    It is agreed that:

                             1. Definitions

    With reference to the premium for the Certificate of which this 
endorsement forms a part:
    Master Worker Policy means the Master Worker Policy issued by NELIA;
    Certificate Holder means the first Named Insured in a Certificate 
issued to form a part of the Master Worker Policy;
    Advance premium, for any calendar year, is the estimated standard 
premium for that calendar year;

[[Page 789]]

    Standard premium, for any calendar year, is the premium for that 
calendar year computed in accordance with the companies' rules, rates, 
rating plans (other than the Industry Retrospective Rating Plan), 
premiums and minimum premiums applicable to this insurance. Standard 
premium includes elements for premium taxes, expenses, profit and 
contingencies, guaranteed cost insurance and estimated reserve premium. 
The elements of standard premium, other than for premium taxes and 
estimated reserve premium, are not subject to retrospective adjustment;
    Reserve premium means that portion of the premium for a Certificate 
(including reserve premium charges paid) that is specifically allocated 
under the Industry Retrospective Rating Plan for ratable incurred 
losses;
    Industry reserve premium, for any period, is the sum of the reserve 
premiums for that period for all Certificates issued to form a part of 
the Master Worker Policy;
    Retrospective adjustment ratio, for any period, is the ratio of the 
reserve premium for this Certificate for that period to the industry 
reserve premium for the same period;
    Incurred losses means the sum of all:
    (1) Losses and expenses paid by NELIA, and
    (2) Reserves for losses and expenses as estimated by NELIA, because 
of obligations assumed and expenses incurred in connection with such 
obligations by the members of NELIA under the Master Worker Policy;
    Ratable incurred losses means 95% of incurred losses. Ratable 
incurred losses are the portion of incurred losses which are not covered 
by the guaranteed cost insurance element of standard premiums;
    Non-ratable incurred losses means 5% of incurred losses. Nonratable 
incurred losses are the portion of incurred losses which are covered by 
the guaranteed cost insurance element of standard premiums;
    Reserve for refunds, as of any date, is the algebraic difference 
between:
    (1) All industry reserve premium for the period from January 1, 1988 
through such date, minus
    (2) The total for the same period of (a) all ratable incurred losses 
and (b) all industry reserve premium refunds made under the Industry 
Retrospective Rating Plan by members of NELIA;
    Industry reserve premium charge, for any period, means the amount 
determined pursuant to the provisions of Section 4 of this endorsement 
for payment by the Named Insureds under Certificates;
    Reserve premium charge means the portion of an industry reserve 
premium charge payable by the Named Insureds under Certificates;
    Industry reserve premium refund for any period, means the amount 
determined pursuant to the provisions of Section 4 of this endorsement 
for return to the Named Insureds under Certificates;
    Reserve premium refund means the portion of an industry reserve 
premium refund returnable to the Named Insureds under this Certificate.

               2. Payment of Advance and Standard Premiums

    The Named Insureds shall pay the companies the advance premium 
stated in the declarations, for the period from the effective date of 
this Certificate through December 31 following. Thereafter, at the 
beginning of each calendar year while this Certificate is in force, the 
Named Insureds shall pay the advance premium for such year to the 
companies.
    The advance premium for each calendar year shall be stated in the 
Advance and Standard Premium Endorsement for the year issued by the 
companies as soon as practicable prior to or after the beginning of the 
year.
    As soon as practicable after the end of a calendar year or the 
Certificate Coverage Period, the standard premium for the preceding year 
shall be finally determined and stated in the Advance and Standard 
Premium Endorsement for that year. If the Standard Premium exceeds the 
Advance Premium paid for that year, the Named Insureds shall pay the 
excess to the companies; if less, the companies shall return to the 
Named Insureds the excess portion paid.
    The Named Insureds shall maintain records of the information 
necessary for premium computation and shall send copies of such records 
to the companies as directed, at the end of each calendar year, at the 
end of the Certificate Coverage Period and at such other times as the 
companies may direct.

           3. Special Reserve Account; Use of Reserve Premiums

    NELIA shall maintain on behalf of its members a Special Reserve 
Account for holding collectively all reserve premiums paid for all 
Certificates issued to form a part of the Master Worker Policy. Such 
premiums, together with any undistributed net income realized thereon 
after taxes and investment expenses, shall be used for the following 
purposes only:
    (1) To pay ratable incurred losses or, in the event ratable incurred 
losses are paid under the Master Worker Policy from funds advanced by 
the members of NELIA subscribing the policy, to reimburse such members 
as a matter of first priority for the funds advanced;
    (2) To refund any amounts so held to the Named Insureds, as provided 
in Section 4.
    No members of NELIA and no Named Insureds shall have any individual 
interest in or claim upon amounts held in the special

[[Page 790]]

Reserve Account, except to participate proportionally in any refund or 
reimbursement provided for above.
    All reserve premiums paid or payable for this certificate may be 
used by NELIA to discharge the obligations of its members under the 
Master Worker Policy with respect to the above purposes and arising out 
of claims made under any Certificate issued to form a part of the Master 
Worker Policy.

            4. Payment of Reserve Premium Charges and Refunds

    As soon as practicable after each December 31 the companies will 
review the status of the reserve for refunds and report their findings 
to all Certificate Holders.
    If, at any time, the companies find that there is negative balance 
in the reserve for refunds and that such condition is likely to prevail, 
they shall determine an appropriate industry reserve premium charge. 
Similarly, if the companies find that there is a surplus positive 
balance, they shall determine an appropriate industry reserve premium 
refund.
    The portion of an industry reserve premium charge or an industry 
reserve premium refund that is:
    (1) Payable by the Named Insureds as a reserve premium charge, or
    (2) Due such insureds as reserve premium refund, shall be determined 
by multiplying the industry reserve premium charge or the industry 
reserve premium refund by the retrospective adjustment ratio applicable 
to this Certificate.
    The amount of any reserve premium charge shall be stated in a 
Retrospective Reserve Premium Charge Endorsement. The charge shall be 
paid promptly after receipt of the endorsement.
    When all claims covered by the Master Worker Policy are closed the 
companies shall make a final review and report, and shall determine a 
final industry reserve premium charge or industry reserve premium refund 
equal to the amount of the balance.

                            5. Final Premium

    The final premium for this Certificate shall be (a) the sum of the 
standard premiums for each calendar year, or portion thereof, during 
which the Certificate remains in force plus (b) the sum of all reserve 
premiums, including all reserve premium charges, minus (c) the sum of 
all reserve premium refunds.

                   6. Reserve Premium Charge Agreement

    In consideration of (a) the participation of Named Insureds in other 
Certificates subject to the Industry Retrospective Rating Plan, (b) the 
undertaking of such Named Insureds to pay their appropriate share of any 
industry reserve premium charge and (c) the obligations assumed by the 
members of NELIA under the Master Worker Policy, the Named Insureds, by 
acceptance of the Master Worker Policy, agree:
    (1) That the insurance provided by the Master Policy applies 
collectively to all claims covered by the policy through any and all 
Certificates issued to form a part of the policy.
    (2) That the right of each Named Insured under a Certificate to 
receive reserve premium refunds and the obligation of each such insured 
to pay reserve premiums charges applies to all claims covered by the 
Master Worker Policy and continues until all such claims are closed, 
whether or not such claims were before the inception of the Certificate 
or after its termination.
    (3) To pay all reserve premium charges due promptly after receipt of 
the Retrospective Reserve Premium Charge Endorsement, whether or not the 
Certificate is terminated. Any reserve premium charge shall be overdue 
if not paid within 60 days of the date of the invoice for the charge.
    Overdue reserve premium charges shall bear interest from the due 
date until paid at an annual rate equal to the sum of (a) 3% plus (b) a 
rate of interest equal to Moody's Average Public Utility Bond Yield 
described in the issue of Moody's Bond Survey current on the due date. 
Any reserve premium refund due to Named Insureds under a Certificate 
shall be used to pay any overdue reserve premium charges to such Named 
Insureds.

                   7. Reserve Premium Refund Agreement

    Each member of NELIA subscribing the Master Worker Policy for any 
calendar year, or portion thereof, with respect to which an industry 
reserve premium refund is determined to be payable thereby agrees for 
itself, severally and not jointly, and in the respective proportion of 
its liability assumed under the Master Worker Policy for that calendar 
year, to return promptly to the Named Insureds that portion of such 
refund due such Insureds, as determined in accordance with the 
provisions of this endorsement.
    Accepted and agreed by the first Named Insured in behalf of itself 
and every other Named Insured stated in the Declarations of the 
Certificate of which this endorsement forms a part.
________________________________________________________________________
(First Named Insured--Type or Print
Date____________________________________________________________________
By______________________________________________________________________
(Signature of Authorized Officer)
________________________________________________________________________
(Type of Print Named and Title of Officer)
Effective Date of this Endorsement______________________________________
12:01 a.m. Standard Time
To form a part of Policy No_____________________________________________
Issued to_______________________________________________________________
Date of Issue___________________________________________________________
    For the subscribing companies:
By______________________________________________________________________

[[Page 791]]

General Manager
    Endorsement No:
Countersigned by________________________________________________________

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                   Nuclear Energy Liability Insurance

    Advance Premium and Standard Premium Endorsement, NE-W-2(1/1/88)

                           Calendar Year 1988

                           1. Advance Premium

    It is agreed that the Advance Premium due the companies for the 
period designated above is:
$_______________________________________________________________________

                 2. Standard Premium and Reserve Premium

    In the absence of a change in the Advance Premium indicated above, 
it is agreed that, subject to the previsions of the Industry 
Retrospective Rating Plan, the Standard Premium is said Advance Premium 
and the estimated reserve Premium element of the Standard Premium is:
$_______________________________________________________________________
    Explanation of Use of this Endorsement: This endorsement will be 
used in the first year of the Master Worker Policy. It states the 
Advance Premium and the estimated Reserve Premium for the year for the 
Certificate to which the endorsement is attached.
Effective Date of this Endorsement______________________________________
12:01 a.m. Standard Time
To form a part of Policy No_____________________________________________
Issued to_______________________________________________________________
Date of Issue___________________________________________________________
    For the subscribing companies:
By______________________________________________________________________
General Manager
    Endorsement No:
Countersigned by________________________________________________________

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                   Nuclear Energy Liability Insurance

    Advance Premium and Standard Premium Endorsement, NE-W-3 (1/1/88)

                           Calendar Year ____

    It is agreed that Items 1 and 2 of Endorsement No. are amended to 
read:

                           1. Advance Premium

    It is agreed that the Advance Premium due the companies for the 
period designated above is:

$_______________________________________________________________________

                 2. Standard Premium and Reserve Premium

    In the absence of a change in the advance premium indicated above, 
it is agreed that, subject to the provisions of the Industry 
Retrospective Rating Plan, the Standard Premium is said Advance Premium 
and the estimated Reserve Premium element of the Standard Premium is:

$_______________________________________________________________________
    Explanation of Use of this Endorsement: This endorsement will be 
used for calendar years of the Master Worker Policy after the 1988 
calendar year. It states the Advance Premium and the estimated Reserve 
Premium for the year for the Certificate to which the endorsement is 
attached.

Effective Date of this Endorsement______________________________________
12:01 a.m. Standard Time
To form a part of Policy No_____________________________________________
Issued to_______________________________________________________________
Date of Issue___________________________________________________________
    For the subscribing companies:

By______________________________________________________________________

General Manager
Endorsement No._________________________________________________________
Countersigned by________________________________________________________

             NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION

                   Nuclear Energy Liability Insurance

 Retrospective Reserve Premium Charge Endorsement, NE-W-dash;5 (1/1/88)

                   1. Industry Reserve Premium Charge

    In accordance with Section 4 of the Industry Retrospective Rating 
Plant Premium Endorsement attached to each Certificate to this policy, 
the companies have reviewed the status of the reserve for refunds, found 
that there is a negative balance in the reserve for refunds and have 
determined that an industry reserve premium charge, as indicated below, 
is appropriate:

$_______________________________________________________________________

                    2. Retrospective Adjustment Ratio

    The portion of the industry reserve premium charge payable by the 
Named Insureds under this Certificate is determined by multiplying such 
charge by this Certificate's retrospective adjustment ratio, which is:

________________________________________________________________________

                        3. Reserve Premium Charge

    The Named Insureds' portion of the industry reserve premium charge, 
as calculated above, is:
$_______________________________________________________________________
    Explanation of Use of this Endorsement: This endorsement will be 
issued by the companies under the Master Worker Policy after an industry 
reserve premium charge has been determined because there is a negative 
balance

[[Page 792]]

in the reserve for refunds. It states the reserve premium charge 
applicable to the Certificate to which the endorsement is attached.

Effective Date of this Endorsement______________________________________
12:01 a.m. Standard Time
To form a part of Policy No.____________________________________________
Issued to_______________________________________________________________
Date of Issue___________________________________________________________
    For the subscribing companies
By______________________________________________________________________
General Manager
Endorsement No._________________________________________________________
Countersigned by________________________________________________________

[25 FR 2948, Apr. 7, 1960]

    Editorial Note: For Federal Register citations affecting Sec. 
140.91, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.92  Appendix B--Form of indemnity agreement with licensees 
furnishing insurance policies as proof of financial protection.

    This indemnity agreement ____ is entered into by and between the 
____ (hereinafter referred to as the licensee) and the United States 
Nuclear Regulatory Commission (hereinafter referred to as the 
Commission) pursuant to subsection 170c of the Atomic Energy Act of 
1954, as amended (hereinafter referred to as the Act).

                                Article I

    As used in this agreement,
    1. Nuclear reactor, byproduct material, person, source material, 
special nuclear material, and precautionary evacuation shall have the 
meanings given them in the Atomic Energy Act of 1954, as amended, and 
the regulations issued by the Commission.
    2.(a) For facilities designed for producing substantial amounts of 
electricity and having a rated capacity of 100,000 electrical kilowatts 
or more, and except when otherwise specifically provided, amount of 
financial protection means the amount specified in Item 2a. and b. of 
the Attachment annexed hereto, as modified by paragraph 8, Article II, 
with respect to common occurrences, and the amount available as 
secondary financial protection (in the form of private liability 
insurance available under an industry retrospective rating plan for 
deferred retrospective premium charges).
    (b) For all other facilities, and except where otherwise 
specifically provided, amount of financial protection means the amount 
specified in Item 2a. and b., of the Attachment annexed hereto, as 
modified by paragraph 8, Article II, with respect to common occurrences.
    3. (a) Nuclear incident means any occurrence including an 
extraordinary nuclear occurrence or series of occurrences at the 
location or in the course of transportation causing bodily injury, 
sickness, disease, or death, or loss of or damage to property, or loss 
of use of property, arising out of or resulting from the radioactive, 
toxic, explosive, or other hazardous properties of the radioactive 
material.
    (b) Any occurrence including an extraordinary nuclear occurrence or 
series of occurrences causing bodily injury, sickness, disease or death, 
or loss of or damage to property, or loss of use of property, arising 
out of or resulting from the radioactive, toxic, explosive or other 
hazardous properties of
    i. The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170 c or k of the Act and so discharged or 
dispersed from the location as defined in any such other agreement, or
    ii. The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into by the Commission pursuant to subsection 
170 c or k of the Act as the radioactive material and which is in the 
course of transportation,
shall be deemed to be a common occurrence. A common occurrence shall be 
deemed to constitute a single nuclear incident.
    4. Extraordinary nuclear occurrence means an event which the 
Commission has determined to be an extraordinary nuclear occurrence as 
defined in the Atomic Energy Act of 1954, as amended.
    5. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person 
licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not by pre-determination to be 
interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto;
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto;

[[Page 793]]

    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170 c or k of the Act.
    6. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    7. Public liability means any legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred by a State, or a political 
subdivision of a State, in the course of responding to a nuclear 
incident or precautionary evacuation), except (1) claims under State or 
Federal Workmen's Compensation Acts of employees of persons indemnified 
who are employed (a) at the location or, if the nuclear incident occurs 
in the course of transportation of the radioactive material, on the 
transporting vehicle, and (b) in connection with the licensee's 
possession, use or transfer of the radioactive material; (2) claims 
arising out of an act of war; and (3) claims for loss of, or damage to, 
or loss of use of (a) property which is located at the location and used 
in connection with the licensee's possession, use, or transfer of the 
radioactive material, and (b) if the nuclear incident occurs in the 
course of transportation of the radioactive material, the transporting 
vehicle, containers used in such transportation, and the radioactive 
material.
    8. The location means the location described in Item 4 of the 
Attachment hereto.
    9. The radioactive material means source, special nuclear, and 
byproduct material which (1) is used or to be used in, or is irradiated 
or to be irradiated by, the nuclear reactor or reactors subject to the 
license or licenses designated in the Attachment hereto, or (2) which is 
produced as the result of operation of said reactor(s).
    10. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. At all times during the term of the license or licenses 
designated in Item 3 of the Attachment hereto, the licensee will 
maintain financial protection in the amount specified in Item 2 of the 
Attachment and in the form of the nuclear energy liability insurance 
policy designated in the Attachment. If more than one license is 
designated in Item 3 of the Attachment, the licensee agrees to maintain 
such financial protection until the end of the term of that license 
which will be the last to expire. The licensee shall, notwithstanding 
the expiration, termination, modification, amendment, suspension or 
revocation of any license or licenses designated in Item 3 of the 
Attachment, maintain such financial protection in effect until all the 
radioactive material has been removed from the location and 
transportation of the radioactive material from the location has ended 
as defined in paragraph 5(b), Article I of this section, or until the 
Commission authorizes the termination or the modification of such 
financial protection. The Commission will not unreasonably withhold such 
authorization.
    2. In the event of any payment by the insurer or insurers under a 
policy or policies specified in Item 5 of the Attachment hereto which 
reduces the aggregate limit of such policy or policies below the amount 
of financial protection, the licensee will promptly apply to his 
insurers for reinstatement of the amount specified in Item 2a of the 
Attachment (without reference to paragraph b of Item 2) and will make 
all reasonable efforts to obtain such reinstatement. In the event that 
the licensee has not obtained reinstatement of such amount within ninety 
days after the date of such reduction, and in the absence of good cause 
shown to the contrary, the Commission may issue an order requiring the 
licensee to furnish financial protection for such amount in another 
form.
    3. Any obligations of the licensee under subsection 53e(8) of the 
Act to indemnify the United States and the Commission from public 
liability, together with any public liability satisfied by the insurers 
under the policy or policies designated in the Attachment hereto, shall 
not in the aggregate exceed the amount of financial protection with 
respect to any nuclear incident, including the reasonable costs of 
investigating and settling claims and defending suits for damage.
    4. With respect to any extraordinary nuclear occurrence to which 
this agreement applies, the Commission, and the licensee on behalf of 
itself and other persons indemnified, insofar as their interests appear, 
each agree to waive:
    (a) Any issue or defense as to the conduct of the claimant or fault 
of persons indemnified, including, but not limited to:
    (1) Negligence;
    (2) Contributory negligence;
    (3) Assumption of the risk;
    (4) Unforeseeable intervening causes, whether involving the conduct 
of a third person or an act of God.

As used herein, conduct of the claimant includes conduct of persons 
through whom the claimant derives his cause of action;
    (b) Any issue or defense as to charitable or governmental immunity;
    (c) Any issue or defense based on any statute of limitations if suit 
is instituted within 3 years from the date on which the claimant first 
knew, or reasonably could have known, of his injury or damage and the 
cause thereof.

[[Page 794]]

    The waiver of any such issue or defense shall be effective 
regardless of whether such issue or defense may otherwise be deemed 
jurisdictional or relating to an element in the cause of action. The 
waivers shall be judicially enforceable in accordance with their terms 
by the claimant against the person indemnified.
    5. The waivers set forth in paragraph 4 of this article:
    (a) Shall not preclude a defense based upon a failure to take 
reasonable steps to mitigate damages;
    (b) Shall not apply to injury or damage to a claimant or to a 
claimant's property which is intentionally sustained by the claimant or 
which results from a nuclear incident intentionally and wrongfully 
caused by the claimant;
    (c) Shall not apply to injury to a claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefore are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law: Provided, however, That with respect to an 
extraordinary nuclear occurrence occurring at the facility, a claimant 
who is employed at the facility in connection with the construction of a 
nuclear reactor with respect to which no operating license has been 
issued by the Nuclear Regulatory Commission shall not be considered as 
employed in connection with the activity where the extraordinary nuclear 
occurrence takes place if:
    (1) The claimant is employed exclusively in connection with the 
construction of a nuclear reactor, including all related equipment and 
installations at the facility, and
    (2) No operating license has been issued by the NRC with respect to 
the nuclear reactor, and
    (3) The claimant is not employed in connection with the possession, 
storage, use or transfer of nuclear material at the facility;
    (d) Shall not apply to any claim for punitive or exemplary damages, 
provided, with respect to any claim for wrongful death under any State 
law which provides for damages only punitive in nature, this exclusion 
does not apply to the extent that the claimant has sustained actual 
damages, measured by the pecuniary injuries resulting from such death 
but not to exceed the maximum amount otherwise recoverable under such 
law;
    (e) Shall be effective only with respect to those obligations set 
forth in this agreement;
    (f) Shall not apply to, or prejudice the prosecution or defense of, 
any claim or portion of claim which is not within the protection 
afforded under (1) the limit of liability provisions under subsection 
170(e) of the Atomic Energy Act of 1954, as amended, and (2) the terms 
of this agreement and the terms of the nuclear energy liability 
insurance policy or policies designated in the attachment hereto.
    6. The obligations of the licensee under this agreement shall apply 
only with respect to nuclear incidents occurring during the term of this 
agreement.
    7. Upon the expiration or revocation of any license designated in 
Item 3 of the Attachment, the Commission will enter into an appropriate 
amendment of this agreement with the licensee reducing the amount of 
financial protection required under this Article; provided, that the 
licensee is then entitled to a reduction in the amount of financial 
protection under applicable Commission regulations and orders.
    8. With respect to any common occurrence,
    (a) If the sum of limit of liability of any Nuclear Energy Liability 
Insurance Association policy designated in Item 5 of the Attachment and 
the limits of liability of all other nuclear energy liability insurance 
policies (facility form) applicable to such common occurrence and issued 
by Nuclear Energy Liability Insurance Association exceeds $155,000,000 
the amount of financial protection specified in Item 2 a and b of the 
Attachment shall be deemed to be reduced by that proportion of the 
difference between said sum and $155,000,000 as the limit of liability 
of the Nuclear Energy Liability Insurance Association policy designated 
in Item 5 of the Attachment bears to the sum of the limits of liability 
of all nuclear energy liability insurance policies (facility form) 
applicable to such common occurrence and issued by Nuclear Energy 
Liability Insurance Association;
    (b) If the sum of the limit of liability of any Mutual Atomic Energy 
Liability Underwriters policy designated in Item 5 of the Attachment and 
the limits of liability of all other nuclear energy liability insurance 
policies (facility form) applicable to such common occurrence and issued 
by Mutual Atomic Energy Liability Underwriters exceeds $45,000,000, the 
amount of financial protection specified in Item 2 a and b of the 
Attachment shall be deemed to be reduced by that proportion of the 
difference between said sum and $45,000,000 as the limit of liability of 
the Mutual Atomic Energy Liability Underwriters policy designated in 
Item 5 of the Attachment bears to the sum of the limits of liability of 
all nuclear energy liability insurance policies (facility form) 
applicable to such common occurrence and issued by Mutual Atomic Energy 
Liability Underwriters;
    (c) If any of the other applicable agreements is with a person who 
has furnished financial protection in a form other than a nuclear energy 
liability insurance policy (facility form) issued by Nuclear Energy 
Liability Insurance Association or Mutual Atomic Energy Liability 
Underwriters, and if also the

[[Page 795]]

sum of the amount of financial protection established under this 
agreement and the amounts of financial protection established under all 
other applicable agreements exceeds an amount equal to the sum of 
$200,000,000 and the amount available as secondary financial protection, 
the obligations of the licensee shall not exceed a greater proportion of 
an amount equal to the sum of $200,000,000 and the amount available as 
secondary financial protection, than the amount of financial protection 
established under this agreement bears to the sum of such amount and the 
amounts of financial protection established under all other applicable 
agreements.
    (d) As used in this paragraph 8., Article II, and in Article III, 
other applicable agreements means each other agreement entered into by 
the Commission pursuant to subsection 170(c) of the Act in which 
agreement the nuclear incident is defined as a common occurrence. As 
used in this paragraph 8., Article II, the obligations of the licensee 
means the obligations of the licensee under subsection 53e(8) of the Act 
to indemnify the United States and the Commission from public liability, 
together with any public liability satisfied by the insurers under the 
policy or policies designated in the Attachment, and the reasonable 
costs incurred by the insurers in investigating and settling claims and 
defending suits for damage.
    9. The obligations of the licensee under this Article shall not be 
affected by any failure or default on the part of the Commission or the 
Government of the United States to fulfill any or all of its obligations 
under this agreement. Bankruptcy or insolvency of any person indemnified 
other than the licensee, or the estate of any person indemnified other 
than the licensee, shall not relieve the licensee of any of his 
obligations hereunder.

                               Article III

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee and other persons indemnified, as their interest 
may appear from public liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had belonged to another; 
provided, that the obligation of the Commission under this paragraph 2 
does not apply with respect to:
    (a) Property which is located at the location described in Item 4 of 
the Attachment or at the location described in Item 3 of the 
declarations attached to any nuclear energy liability insurance policy 
designated in Item 5 of the Attachment;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation;
    (d) The radioactive material.
    3. [Reserved]
    4. (a) The obligations of the Commission under this agreement shall 
apply only with respect to such public liability and such damage to 
property of persons legally liable for the nuclear incident (other than 
such property described in the proviso to paragraph 2 of this Article) 
as in the aggregate exceed the amount of financial protection.
    (b) With respect to a common occurrence, the obligations of the 
Commission under this agreement shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to paragraph 2 of this Article) as in the aggregate exceed 
whichever of the following is lower: (1) The sum of the amounts of 
financial protection established under this agreement and all other 
applicable agreements; or (2) an amount equal to the sum of $200,000,000 
and the amount available as secondary financial protection.
    5. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    6. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not 
with respect to any nuclear incident, in the aggregate exceed whichever 
of the following is the lowest: (a) $500,000,000; (b) $560,000,000 less 
the amount of financial protection required under this agreement; or (c) 
with respect to a common occurrence, $560,000,000 less the sum of the 
amounts of financial protection established under this agreement and all 
other applicable agreements.
    7. The obligations of the Commission under this agreement, except to 
the licensee for damage to property of the licensee, shall not be 
affected by any failure on the part of the licensee to fulfill its 
obligations under this agreement. Bankruptcy or insolvency of the 
licensee or any other person indemnified or of the estate of the 
licensee or any other person indemnified shall not relieve the 
Commission of any of its obligations hereunder.

                               Article IV

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim (provided that no government indemnity that would otherwise 
be available to pay public

[[Page 796]]

liability claims is used for these purposes) and shall have the right 
(a) to require the prior approval of the Commission for the settlement 
or payment of any claim or action asserted against the licensee or other 
person indemnified for public liability or damage to property of persons 
legally liable for the nuclear incident which claim or action the 
licensee or the Commission may be required to indemnify under this 
agreement; and (b) to appear through the Attorney General of the United 
States on behalf of the licensee or other person indemnified, take 
charge of such action and settle or defend any such action. If the 
settlement or defense of any such action or claim is undertaken by the 
Commission, the licensee shall furnish all reasonable assistance in 
effecting a settlement or asserting a defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                                Article V

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                               Article VI

    The licensee agrees to pay to the Commission such fees as are 
established by the Commission pursuant to regulations or orders of the 
Commission.

                               Article VII

    The term of this agreement shall commence as of the date and time 
specified in Item 6 of the Attachment and shall terminate at the time of 
expiration of that license specified in Item 3 of the Attachment, which 
is the last to expire; provided that, except as may otherwise be 
provided in applicable regulations or orders of the Commission, the term 
of this agreement shall not terminate until all the radioactive material 
has been removed from the location and transportation of the radioactive 
material from the location has ended as defined in paragraph 5(b), 
Article I of this section. Termination of the term of this agreement 
shall not affect any obligation of the licensee or any obligation of the 
Commission under this agreement with respect to any nuclear incident 
occurring during the term of this agreement.

                              Article VIII

    The following provisions are applicable to each licensee operating a 
facility designed for producing substantial amounts of electricity and 
having a rated capacity of 100,000 electrical kilowatts or more;
    1. Each licensee is required to have and maintain financial 
protection in an amount specified in Item 2 a and b of the Attachment 
annexed hereto, and the amount available as secondary financial 
protection (in the form of private liability insurance available under 
an industry retrospective rating plan providing for deferred premium 
charges); Provided, however, That under such a plan for deferred premium 
charges, such charges for each nuclear reactor which is licensed to 
operate shall not exceed $63,000,000 with respect to any single nuclear 
incident (plus any surcharge assessed under subsection 170o.(1)(E) of 
the Act) nor exceed $10,000,000 per incident within one calendar year. 
If the licensee fails to pay assessed deferred premiums, the Commission 
reserves the right to pay those premiums on behalf of the licensee and 
to recover the amount of such premiums from the licensee.
    2. The Commission shall require the immediate submission of 
financial statements by those licensees who indicate, after an 
assessment of the retrospective premium by the insurance pools, that 
they will not pay the assessment. Such financial statements shall 
include, as a minimum, exhibits indicating internally generated funds 
from operations and accumulated retained earnings. Subsequent submission 
of financial statements by such licensees may be requested by the 
Commission, as required.
    3. If premiums are paid by the Commission as provided in paragraph 
1, payment by the Commission shall create a lien in the amount paid in 
favor of the United States upon all property and rights to property, 
whether real or personal, belonging to such licensee. The lien shall 
arise at the time payment is made by the Commission and shall continue 
until the liability for the amount (or a judgment against the licensee 
arising out of such liability) is satisfied or becomes unenforceable. 
The Commission will issue a certificate of release of any such lien if 
it finds that the liability for the amount has been fully satisfied or 
has become legally unenforceable.
    4. If the Commission determines that the licensee is financially 
able to reimburse the Commission for a deferred premium payment made in 
its behalf, and the licensee, after notice of such determination by the 
Commission fails to make such reimbursement within 120 days, the 
Commission will take appropriate steps to suspend the license for 30 
days. The Commission may take any further action as necessary if 
reimbursement is not made within the 30-day suspension period including, 
but not limited to termination of the operating license.

               United States Nuclear Regulatory Commission

Indemnity Agreement No._________________________________________________
Item 1--Licensee________________________________________________________

[[Page 797]]

Address_________________________________________________________________
Item 2--a. Amount of financial protection_______________________________

    b. With respect to any nuclear incident, the amount specified in 
Item 2a of this Attachment shall be deemed to be (i) reduced to the 
extent that any payment made by the insurer or insurers under a policy 
or policies specified in Item 5 of this Attachment reduces the aggregate 
amount of such insurance policies below the amount specified in Item 2a 
and (ii) restored to the extent that, following such reduction, the 
aggregate amount of such insurance policies is reinstated.
Item 3--License number or numbers_______________________________________

Item 4--Location________________________________________________________

Item 5--Insurance Policy No.(s)_________________________________________

Item 6--The indemnity agreement designated above, of which this 
Attachment is a part, is effective as of _ m., on the _ day of ______, 
19__.
    For the United States Nuclear Regulatory Commission.
                                                            By _________
                                                       For the _________
                                                      (Name of licensee)
                                                            By _________
    Dated at Bethesda, MD, the _______ day of ______, 19__.

[26 FR 3457, Apr. 22, 1961]

    Editorial Note: For Federal Register citations affecting Sec. 
140.92, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.93  Appendix C--Form of indemnity agreement with licensees 
furnishing proof of financial protection in the form of licensee's 
resources.

    This indemnity agreement No. _____ is entered into by and between 
the ____ (hereinafter referred to as the licensee) and the United States 
Nuclear Regulatory Commission (hereinafter referred to as the Commission 
pursuant to subsection 170(c) of the Atomic Energy Act of 1954, as 
amended (hereinafter referred to as the Act).

                                Article I

    As used in this agreement,
    1. Nuclear reactor, byproduct material, person, source material, 
special nuclear material, and precautionary evacuation shall have the 
meanings given them in the Atomic Energy Act of 1954, as amended, and 
the regulations issued by the Commission.
    2.(a) For facilities designed for producing substantial amounts of 
electricity and having a rated capacity of 100,000 electrical kilowatts 
or more, and except where otherwise specifically provided, amount of 
financial protection means the amount specified in Item 2 of the 
Attachment annexed hereto, as modified by paragraph 8, Article II, with 
respect to common occurrences, and the amount available as secondary 
financial protection (in the form of private liability insurance 
available under an industry retrospective rating plan providing for 
deferred retrospective premium charges).
    (b) For all other facilities, and except where otherwise 
specifically provided, amount of financial protection means the amount 
specified in Item 2 of the Attachment annexed hereto, as modified by 
paragraph 8, Article II, with respect to common occurrences.
    3. (a) Nuclear incident means any occurrence including an 
extraordinary nuclear occurrence or series of occurrences at the 
location or in the course of transportation causing bodily injury, 
sickness, disease, or death, or loss of or damage to property, or loss 
of use of property, arising out of or resulting from the radioactive, 
toxic, explosive, or other hazardous properties of the radioactive 
material.
    (b) Any occurrence including an extraordinary nuclear occurrence or 
series of occurrences causing bodily injury, sickness, disease or death, 
or loss of or damage to property, or loss of use of property, arising 
out of or resulting from the radioactive, toxic, explosive or other 
hazardous properties of--
    i. The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170(c) or (k) of the Act and so discharged 
or dispersed from the location as defined in any such other agreement; 
or
    ii. The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into by the Commission pursuant to subsection 
170(c) or (k) of the Act as the radioactive material and which is in the 
course of transportation shall be deemed to be a common occurrence. A 
common occurrence shall be deemed to constitute a single nuclear 
incident.
    4. Extraordinary nuclear occurrence means an event which the 
Commission has determined to be an extraordinary nuclear occurrence as 
defined in the Atomic Energy Act of 1954, as amended.
    5. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person

[[Page 798]]

licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not by pre-determination to be 
interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto;
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto;
    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170(c) or (k) of the Act.
    6. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    7. Public liability means any legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred by a State, or a political 
sudivision of a State, in the course of responding to a nuclear incident 
or precautionary evacuation), except (1) claims under State or Federal 
Workmen's Compensation Acts of employees of persons indemnified who are 
employed (a) at the location or, if the nuclear incident occurs in the 
course of transportation of the radioactive material, on the 
transporting vehicle, and (b) in connection with the licensee's 
possession, use, or transfer of the radioactive material; (2) claims 
arising out of an act of war; and (3) claims for loss of, or damage to, 
or loss of use of (a) property which is located at the location and used 
in connection with the licensee's possession, use or transfer of the 
radioactive material, and (b), if the nuclear incident occurs in the 
course of transportation of the radioactive material, the transporting 
vehicle, containers used in such transportation, and the radioactive 
material.
    8. The location means the location described in Item 4 of the 
Attachment hereto.
    9. The radioactive material means source, special nuclear, and 
byproduct material which (1) is used or to be used in, or is irradiated 
or to be irradiated by, the nuclear reactor or reactors subject to the 
license or licenses designated in the Attachment hereto, or (2) which is 
produced as the result of operation of said reactor(s).
    10. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. The licensee undertakes and agrees to indemnify and hold harmless 
all persons indemnified, as their interest may appear, from public 
liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the incident, the licensee agrees to 
pay to such person those sums which such person would have been 
obligated to pay if such property had belonged to another, provided, 
that the obligation of the licensee under this paragraph 2 does not 
apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to neglect of the person indemnified to use 
all reasonable means to save and preserve the property after knowledge 
of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation; and
    (d) The radioactive material.
    3. Any obligations of the licensee under paragraphs 1 and 2 of this 
Article, and under subsection 53e(8) of the Act to indemnify the United 
States and the Commission from public liability shall not in the 
aggregate exceed the amount of financial protection with respect to any 
nuclear incident, including the reasonable costs of investigating and 
settling claims and defending suits for damage.
    4. With respect to any extraordinary nuclear occurrence to which 
this agreement applies, the Commission, and the licensee on behalf of 
itself and other persons indemnified, insofar as their interests appear, 
each agree to waive:
    (a) Any issue or defense as to the conduct of the claimant or fault 
of persons indemnified, including, but not limited to:
    (1) Negligence;
    (2) Contributory negligence;
    (3) Assumption of the risk;
    (4) Unforeseeable intervening causes, whether involving the conduct 
of a third person or an act of God.

As used herein, conduct of the claimant includes conduct of persons 
through whom the claimant derives his cause of action;
    (b) Any issue or defense as to charitable or governmental immunity;
    (c) Any issue or defense based on any statute of limitations if suit 
is instituted within 3 years from the date on which the claimant first 
knew, or reasonably could have known,

[[Page 799]]

of his injury or damage and the cause thereof.
    The waiver of any such issue or defense shall be effective 
regardless of whether such issue or defense may otherwise be deemed 
jurisdictional or relating to an element in the cause of action. The 
waivers shall be judicially enforceable in accordance with their terms 
by the claimant against the person indemnified.
    5. The waivers set forth in paragraph 4, of this article:
    (a) Shall not preclude a defense based upon a failure to take 
reasonable steps to mitigate damages;
    (b) Shall not apply to injury or damage to a claimant or to a 
claimant's property which is intentionally sustained by the claimant or 
which results from a nuclear incident intentionally and wrongfully 
caused by the claimant;
    (c) Shall not apply to injury to a claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefor are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law: Provided, however, That with respect to an 
extraordinary nuclear occurrence occurring at the facility, a claimant 
who is employed at the facility in connection with the construction of a 
nuclear reactor with respect to which no operating license has been 
issued by the Nuclear Regulatory Commission shall not be considered as 
employed in connection with the activity where the extraordinary nuclear 
occurrence takes place if:
    (1) The claimant is employed exclusively in connection with the 
construction of a nuclear reactor, including all related equipment and 
installations at the facility, and
    (2) No operating license has been issued by the NRC with respect to 
the nuclear reactor, and
    (3) The claimant is not employed in connection with the possession, 
storage, use or transfer of nuclear material at the facility;
    (d) Shall not apply to any claim for punitive or exemplary damages, 
provided, with respect to any claim for wrongful death under any State 
law which provides for damages only punitive in nature, this exclusion 
does not apply to the extent that the claimant has sustained actual 
damages, measured by the pecuniary injuries resulting from such death 
but not to exceed the maximum amount otherwise recoverable under such 
law;
    (e) Shall be effective only with respect to those obligations set 
forth in this agreement and in contracts or other proof of financial 
protection;
    (f) Shall not apply to, or prejudice the prosecution or defense of, 
any claim or portion of claim which is not within the protection 
afforded under (1) the limit of liability provisions under subsection 
170(e), of the Atomic Energy Act of 1954, as amended, and (2) the terms 
of this agreement and the terms of contracts or other proof of financial 
protection.
    6. The obligations of the licensee under this agreement shall apply 
only with respect to nuclear incidents occurring during the term of this 
agreement.
    7. Upon the expiration or revocation of any license designated in 
Item 3 of the Attachment, the Commission will enter into an appropriate 
amendment of this agreement with the licensee reducing the amount of 
financial protection required under this Article; provided, that the 
licensee is then entitled to a reduction in the amount of financial 
protection under applicable Commission regulations and orders.
    8. With respect to a common occurrence, if the sum of the amount of 
financial protection established under this agreement and the amount of 
financial protection established under all other applicable agreements 
exceeds an amount equal to the sum of $200,000,000 and the amount 
available as secondary financial protection, the obligations of the 
licensee described in paragraph 3 of this Article shall not exceed a 
greater proportion of an amount equal to the sum of $200,000,000 and the 
amount available as secondary financial protection than the amount of 
financial protection established under this agreement bears to the sum 
of such amount and the amounts of financial protection established under 
all other applicable agreements. As used in this paragraph, and in 
Article III, other applicable agreements means each other agreement 
entered into by the Commission pursuant to subsection 170(c) or (k) of 
the Act in which agreement the nuclear incident is defined as a common 
occurrence.
    9. The obligations of the licensee under this Article shall not be 
affected by any failure or default on the part of the Commission or the 
Government of the United States to fulfill any or all of its obligations 
under this agreement. Bankruptcy or insolvency of any person indemnified 
other than the licensee, or the estate of any person indemnified other 
than the licensee, shall not relieve the licensee of any of his 
obligations hereunder.

                               Article III

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee and other persons indemnified, as their interest 
may appear, from public liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had

[[Page 800]]

belonged to another; provided, that the obligation of the Commission 
under this paragraph 2 does not apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation;
    (d) The radioactive material.
    3. [Reserved]
    4. (a) The obligations of the Commission under this agreement shall 
apply only with respect to such public liability and such damage to 
property of persons legally liable for the nuclear incident (other than 
such property described in the proviso to paragraph 2 of this Article) 
as in the aggregate exceed the amount of financial protection.
    (b) With respect to a common occurrence, the obligations of the 
Commission under this agreement shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to Paragraph 2 of this Article) as in the aggregate exceed 
whichever of the following is lower: (1) The sum of the amount of 
financial protection established under this agreement and to all other 
applicable agreements; or (2) an amount equal to the sum of $200,000,000 
and the amount available as secondary financial protection.
    5. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    6. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not 
with respect to any nuclear incident, in the aggregate exceed whichever 
of the following is the lowest: (a) $500,000,000; (b) $560,000,000 less 
the amount of financial protection required under this agreement; or (c) 
with respect to a common occurrence, $560,000,000 less the sum of the 
amounts of financial protection established under this agreement and all 
other applicable agreements.
    7. The obligations of the Commission under this agreement, except to 
the licensee for damage to property of the licensee, shall not be 
affected by any failure on the part of the licensee to fulfill its 
obligations under this agreement. Bankruptcy or insolvency of the 
licensee or any other person indemnified shall not relieve the 
Commission of any of its obligations hereunder.

                               Article IV

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim (provided that no government indemnity that would otherwise 
be available to pay public liability claims is used for these purposes) 
and shall have the right (a) to require the prior approval of the 
Commission for the settlement or payment of any claim or action asserted 
against the licensee or other person indemnified for public liability or 
damage to property of persons legally liable for the nuclear incident 
which claim or action the licensee or the Commission may be required to 
indemnify under this agreement; and (b) to appear through the Attorney 
General of the United States on behalf of the licensee or other person 
indemnified, take charge of such action and settle or defend any such 
action. If the settlement or defense of any such action or claim is 
undertaken by the Commission, the licensee shall furnish all reasonable 
assistance in effecting a settlement or asserting a defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                                Article V

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                               Article VI

    The licensee agrees to pay to the Commission such fees as are 
established by the Commission pursuant to regulations or orders of the 
Commission.

                               Article VII

    The term of this agreement shall commence as of the date and time 
specified in Item 6 of the attachment and shall terminate at the time of 
expiration of that license specified in Item 3 of the attachment, which 
is last to expire; provided that, except as may otherwise be provided in 
applicable regulations or orders of the Commission, the term of this 
agreement shall not terminate until all the radioactive material has 
been removed from the location and transportation of the radioactive 
material from the location has ended as defined in subparagraph 5(b), 
Article I. Termination of the term of this agreement shall not affect 
any obligation of the licensee or any obligation of the Commission under 
this agreement

[[Page 801]]

with respect to any nuclear incident occurring during the term of this 
agreement.

                              Article VIII

    The following provisions are applicable to each licensee operating a 
facility designed for producing substantial amounts of electricity and 
having a rated capacity of 100,000 electrical kilowatts or more:
    1. Each licensee is required to have and maintain financial 
protection in an amount specified in Item 2 annexed hereto, and the 
amount available as secondary financial protection (in the form of 
private liability insurance available under an industry retrospective 
rating plan providing for deferred premium charges): Provided, however, 
That under such a plan for deferred premium charges, such charges for 
each nuclear reactor which is licensed to operate shall not exceed 
$63,000,000 with respect to any single nuclear incident (plus any 
surcharge assessed under subsection 170o.(1)(E) of the Act) nor exceed 
$10,000,000 per incident within one calendar year. If the licensee fails 
to pay assessed deferred premiums, the Commission reserves the right to 
pay those premiums on behalf of the licensee and to recover the amount 
of such premiums from the licensee.
    2. The Commission shall require the immediate submission of 
financial statements by those licensees who indicate, after an 
assessment of the restrospective premium by the insurance pools, that 
they will not pay the assessment. Such financial statements shall 
include, as a minimum, exhibits indicating internally generated funds 
from operations and accumulated retained earnings. Subsequent submission 
of financial statements by such licensees may be requested by the 
Commission, as required.
    3. If premiums are paid by the Commission as provided in paragraph 
1, payment by the Commission shall create a lien in the amount paid in 
favor of the United States upon all property and rights to property, 
whether real or personal, belonging to such licensee. The lien shall 
arise at the time payment is made by the Commission and shall continue 
until the liability for the amount (or a judgment against the licensee 
arising out of such liability) is satisfied or becomes unenforceable. 
The Commission will issue a certificate of release of any such lien if 
it finds that the liability for the amount has been fully satisfied or 
has become legally unenforceable.
    4. If the Commission determines that the licensee is financially 
able to reimburse the Commission for a deferred premium payment made in 
its behalf, and the licensee, after notice of such determination by the 
Commission fails to make such reimbursement within 120 days, the 
Commission will take appropriate steps to suspend the license for 30 
days. The Commission may take any further action as necessary if 
reimbursement is not made within the 30-day suspension period including, 
but not limited to, termination of the operating license or combined 
license.

               United States Nuclear Regulatory Commission

                                             Indemnity Agreement No. ___

                               Attachment

Item 1--Licensee________________________________________________________
Address_________________________________________________________________
Item 2--Amount of financial protection__________________________________
Item 3--License number or numbers_______________________________________
Item 4--Location________________________________________________________

Item 5--The Indemnity Agreement designated above, of which this 
Attachment is a part, is effective as of ___M., on the ______ day of 
_____, 19__.

    For the United States Nuclear Regulatory Commission.
                                                         By ____________
                                                    For the ____________
                                                      (Name of licensee)
                                                         By ____________
    Dated at Bethesda, MD, the ______ day of _____, 19__.

[26 FR 3459, Apr. 22, 1961]

    Editorial Note: For Federal Register citations affecting Sec. 
140.93, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.94  Appendix D--Form of indemnity agreement with Federal 
agencies.

    This indemnity agreement No. D___ is entered into by and between the 
____ (hereinafter referred to as the licensee) and the United States 
Nuclear Regulatory Commission (hereinafter referred to as the 
Commission) pursuant to subsection 170(c) of the Atomic Energy Act of 
1954, as amended (hereinafter referred to as the Act).

                                Article I

    As used in this agreement,
    1. Nuclear reactor, byproduct material, person, source material, 
special nuclear material, and precautionary evacuation shall have the 
meanings given them in the Atomic Energy Act of 1954, as amended, and 
the regulations issued by the Commission.
    2. (a) Nuclear incident means any occurrence including an 
extraordinary nuclear occurrence or series of occurrences at the 
location or in the course of transportation causing bodily injury, 
sickness, disease, or death, or loss of or damage to property, or loss 
of use of property, arising out of or resulting from the radioactive, 
toxic, explosive, or

[[Page 802]]

other hazardous properties of the radioactive material.
    (b) Any occurrence including an extraordinary nuclear occurrence or 
series of occurrences causing bodily injury, sickness, disease, or 
death, or loss of or damage to property, or loss of use of property, 
arising out of or resulting from the radioactive, toxic, explosive or 
other hazardous properties of
    (i) The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170(c) or (k) of the Act and so discharged 
or dispersed from the location as defined in any such other agreement, 
or
    (ii) The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into by the Commission pursuant to subsection 
170(c) or (k) of the Act as the radioactive material and which is in the 
course of transportation shall be deemed to be a common occurrence. A 
common occurrence shall be deemed to constitute a single nuclear 
incident.
    3. Extraordinary nuclear occurrence means an event which the 
Commission has determined to be an extraordinary nuclear occurrence as 
defined in the Atomic Energy Act of 1954, as amended.
    4. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person 
licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not by predetermination to be 
interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto;
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto;
    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170(c) or (k) of the Act.
    5. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    6. Public liability means any legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred by a State, or a political 
subdivision of a State, in the course of responding to a nuclear 
incident or precautionary evacuation), except (1) claims under State of 
Federal Workmen's Compensation Acts of employees of persons indemnified 
who are employed (a) at the location or, if the nuclear incident occurs 
in the course of transportation of the radioactive material, on the 
transporting vehicle, and (b) in connection with the licensee's 
possession, use, or transfer of the radioactive material; (2) claims 
arising out of an act of war; and (3) claims for loss of, or damage to, 
or loss of use of (a) property which is located at the location and used 
in connection with the licensee's possession, use, or transfer of the 
radioactive material, and (b) if the nuclear incident occurs in the 
course of transportation of the radioactive material, the transporting 
vehicle, containers used in such transportation, and the radioactive 
material.
    7. The location means the location described in Item 3 of the 
Attachment hereto.
    8. The radioactive material means source, special nuclear, and 
byproduct material which (1) is used or to be used in, or is irradiated 
or to be irradiated by, the nuclear reactor or reactors subject to the 
license or licenses designated in the Attachment hereto, or (2) is 
produced as the result of operation of said reactor(s).
    9. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee and other persons indemnified, as their interest 
may appear, from public liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had belonged to another; 
provided, that the obligation of the Commission under this paragraph 2 
does not apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive

[[Page 803]]

material, the transporting vehicle and containers used in such 
transportation;
    (d) The radioactive material.
    3. [Reserved]
    4. With respect to any extraordinary nuclear occurrence to which 
this agreement applies, the Commission, and the licensee on behalf of 
itself and other persons indemnified, insofar as their interests appear, 
each agree to waive:
    (a) Any issue or defense as to the conduct of the claimant or fault 
of persons indemnified, including, but not limited to:
    (1) Negligence;
    (2) Contributory negligence;
    (3) Assumption of the risk;
    (4) Unforeseeable intervening causes, whether involving the conduct 
of a third person or an act of God.

As used herein, conduct of the claimant includes conduct of persons 
through whom the claimant derives his cause of action;
    (b) Any issue or defense as to charitable or governmental immunity;
    (c) Any issue or defense based on any statute of limitations if suit 
is instituted within 3 years from the date on which the claimant first 
knew, or reasonably could have known, of his injury or damage and the 
cause thereof.
    The waiver of any such issue or defense shall be effective 
regardless of whether such issue or defense may otherwise be deemed 
jurisdictional or relating to an element in the cause of action. The 
waivers shall be judicially enforceable in accordance with their terms 
by the claimant against the person indemnified.
    5. The waivers set forth in paragraph 4 of this article:
    (a) Shall not preclude a defense based upon a failure to take 
reasonable steps to mitigate damages;
    (b) Shall not apply to injury or damage to a claimant or to a 
claimant's property which is intentionally sustained by the claimant or 
which results from a nuclear incident intentionally and wrongfully 
caused by the claimant;
    (c) Shall not apply to injury to a claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefor are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law: Provided, however, That with respect to an 
extraordinary nuclear occurrence occurring at the facility, a claimant 
who is employed at the facility in connection with the construction of a 
nuclear reactor with respect to which no operating license has been 
issued by the Nuclear Regulatory Commission shall not be considered as 
employed in connection with the activity where the extraordinary nuclear 
occurrence takes place if:
    (1) The claimant is employed exclusively in connection with the 
construction of a nuclear reactor, including all related equipment and 
installations at the facility, and
    (2) No operating license has been issued by the NRC with respect to 
the nuclear reactor, and
    (3) The claimant is not employed in connection with the possession, 
storage, use or transfer of nuclear material at the facility;
    (d) Shall not apply to any claim for punitive or exemplary damages, 
provided, with respect to any claim for wrongful death under any State 
law which provides for damages only punitive in nature, this exclusion 
does not apply to the extent that the claimant has sustained actual 
damages, measured by the pecuniary injuries resulting from such death 
but not to exceed the maximum amount otherwise recoverable under such 
law;
    (e) Shall be effective only with respect to those obligations set 
forth in this agreement;
    (f) Shall not apply to, or prejudice the prosecution or defense of, 
any claim or portion of claim which is not within the protection 
afforded under (1) the limit of liability provisions under subsection 
170(e), of the Atomic Energy Act of 1954, as amended, and (2) the terms 
of this agreement.
    6. With respect to a common occurrence, the obligations of the 
Commission under this Article shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to paragraph 2 of this Article) as in the aggregate exceed 
whichever of the following is lower: (1) The sum of the amount of 
financial protection established under all applicable agreements; or (2) 
an amount equal to the sum of $200,000,000 and the amount available as 
secondary financial protection. As used in this Article applicable 
agreements means each agreement entered into by the Commission pursuant 
to subsection 170(c) or (k) of the Act in which agreement the nuclear 
incident is defined as common occurrence.
    7. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    8. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not 
with respect to any nuclear incident, in the aggregate exceed whichever 
of the following is the lower: (a) $500,000,000 or (b) with respect to a 
common occurrence, $560,000,000 less the sum of the amounts of financial 
protection established under all applicable agreements.

[[Page 804]]

    9. Bankruptcy or insolvency of any person indemnified or of the 
estate of any person indemnified shall not relieve the Commission of any 
of its obligations hereunder.

                               Article III

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim (provided that no government indemnity that would otherwise 
be available to pay public liability claims is used for these purposes) 
and shall have the right (a) to require the prior approval of the 
Commission for the settlement or payment of any claim or action asserted 
against the licensee or other persons indemnified for public liability 
or damage to property of persons legally liable for the nuclear incident 
which claim or action the licensee or the Commission may be required to 
indemnify under this agreement; and (b) to appear through the Attorney 
General of the United States on behalf of the licensee or other person 
indemnified, take charge of such action and settle or defend any such 
action. If the settlement or defense of any such action or claim is 
undertaken by the Commission, the licensee shall furnish all reasonable 
assistance in effecting a settlement or asserting a defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                               Article IV

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                                Article V

    The licensee agrees to pay to the Commission such fees as are 
established by the Commission pursuant to regulations or orders of the 
Commission.

                               Article VI

    The term of this agreement shall commence as of the date and time 
specified in Item 4 of the attachment and shall terminate at the time of 
expiration of that license specified in Item 2 of the Attachment, which 
is the last to expire; provided that, except as may otherwise be 
provided in applicable regulations or orders of the Commission, the term 
of this agreement shall not terminate until all the radioactive material 
has been removed from the location and transportation of the radioactive 
material from the location has ended as defined in paragraph 4(b), 
Article I of this section. Termination of the term of this agreement 
shall not affect any obligation of the licensee or any obligation of the 
Commission under this agreement with respect to any nuclear incident 
occurring during the term of this agreement.

               United States Nuclear Regulatory Commission

                                           Indemnity Agreement No. D-___

                               attachment

Item 1--Licensee________________________________________________________
Address_________________________________________________________________
Item 2--License number or numbers_______________________________________
Item 3--Location________________________________________________________

Item 4--The indemnity agreement designated above, of which this 
Attachment is a part, is effective as of ___ m., on the _______ day of 
_____, 19__.

    For the United States Nuclear Regulatory Commission.
                                                         By ____________
                                                    For the ____________
                                                      (Name of licensee)
                                                         By ____________
    Dated at Bethesda, MD, the _______ day of _____, 19__.

[27 FR 2886, Mar. 29, 1962]

    Editorial Note: For Federal Register citations affecting Sec. 
140.94, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.95  Appendix E--Form of indemnity agreement with nonprofit
educational institutions.

    This indemnity agreement No. E-___ is entered into by and between 
the ____ (hereinafter referred to as the licensee) and the United States 
Nuclear Regulatory Commission (hereinafter referred to as the 
Commission) pursuant to subsection 170(k) of the Atomic Energy Act of 
1954, as amended (hereinafter referred to as the Act).

                                Article I

    As used in this agreement,
    1. Nuclear reactor, byproduct material, person, source material, 
special nuclear material, and precautionary evacuation shall have the 
meanings given them in the Atomic Energy Act of 1954, as amended, and 
the regulations issued by the Commission.
    2. (a) Nuclear incident means any occurrence including an 
extraordinary nuclear occurrence or series of occurrences at the 
location or in the course of transportation causing bodily injury, 
sickness, disease, or death, or loss of use of property, arising out of 
or

[[Page 805]]

resulting from the radioactive, toxic, explosive, or other hazardous 
properties of the radioactive material.
    (b) Any occurrence including an extraordinary nuclear occurrence or 
series of occurrences causing bodily injury, sickness, disease or death, 
or loss of or damage to property, or loss of use of property, arising 
out of or resulting from the radioactive, toxic, explosive, or other 
hazardous properties of
    i. The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170(c) or (k) of the Act and so discharged 
or dispersed from the location as defined in any such other agreement; 
or
    ii. The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into by the Commission pursuant to subsection 
170(c) or (k) of the Act as the radioactive material and which is in the 
course of transportation shall be deemed to be a common occurrence. A 
common occurrence shall be deemed to constitute a single nuclear 
incident.
    3. Extraordinary nuclear occurrence means an event which the 
Commission has determined to be an extraordinary nuclear occurrence as 
defined in the Atomic Energy Act of 1954, as amended.
    4. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person 
licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not by predetermination to be 
interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto;
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto;
    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170(c) or (k) of the Act.
    5. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    6. Public liability means are legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred by a State, or a political 
subdivision of a State, in the course of responding to a nuclear 
incident or precautionary evacuation), except (1) claims under State or 
Federal Workmen's Compensation Act of employees of persons indemnified 
who are employed (a) at the location or, if the nuclear incident occurs 
in the course of transportation of the radioactive material, or the 
transporting vehicle, and (b) in connection with the licensee's 
possession, use, or transfer of the radioactive material; (2) claims 
arising out of an act of war; and (3) claims for loss of, or damage to, 
or loss of use of (a) property which is located at the location and used 
in connection with the licensee's possession, use, or transfer of the 
radioactive material, and (b) if the nuclear incident occurs in the 
course of transportation of the radioactive material, the transporting 
vehicle, containers used in such transportation, and the radioactive 
material.
    7. The location means the location described in Item 3 of the 
Attachment hereto.
    8. The radioactive material means source, special nuclear, and 
byproduct material which (1) is used or to be used in, or is irradiated 
or to be irradiated by, the nuclear reactor or reactors subject to the 
license or licenses designated in the Attachment hereto, or (2) which is 
produced as the result of operation of said reactor(s).
    9. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. Any obligations of the licensee under subsection 53e(8) of the 
Act to indemnify the United States and the Commission from public 
liability shall not in the aggregate exceed $250,000 with respect to any 
nuclear incident.
    2. With respect to any extraordinary nuclear occurrence to which 
this agreement applies, the Commission, and the licensee on behalf of 
itself and other persons indemnified, insofar as their interests appear, 
each agree to waive:
    (a) Any issue or defense as to the conduct of the claimant or fault 
of persons indemnified, including, but not limited to
    (1) Negligence;
    (2) Contributory negligence;
    (3) Assumption of the risk;
    (4) Unforeseeable intervening causes, whether involving the conduct 
of a third person or an act of God.


[[Page 806]]


As used herein, conduct of the claimant includes conduct of persons 
through whom the claimant derives his cause of action;
    (b) Any issue or defense as to charitable or governmental immunity:
    (c) Any issue or defense based on any statute of limitations if suit 
is instituted within 3 years from the date on which the claimant first 
knew, or reasonably could have known, of his injury or damage and the 
cause thereof.
    The waiver of any such issue or defense shall be effective 
regardless of whether such issue or defense may otherwise be deemed 
jurisdictional or relating to an element in the cause of action. The 
waivers shall be judicially enforceable in accordance with their terms 
by the claimant against the person indemnified.
    3. The waivers set forth in paragraph 2 of this article:
    (a) Shall not preclude a defense based upon a failure to take 
reasonable steps to mitigate damages;
    (b) Shall not apply to injury or damage to a claimant or to a 
claimant's property which is intentionally sustained by the claimant or 
which results from a nuclear incident intentionally and wrongfully 
caused by the claimant;
    (c) Shall not apply to injury to a claimant who is employed at the 
site of and in connection with the activity where the extraordinary 
nuclear occurrence takes place if benefits therefor are either payable 
or required to be provided under any workmen's compensation or 
occupational disease law: Provided, however, That with respect to an 
extraordinary nuclear occurrence occurring at the facility, a claimant 
who is employed at the facility in connection with the construction of a 
nuclear reactor with respect to which no operating license has been 
issued by the Nuclear Regulatory Commission shall not be considered as 
employed in connection with the activity where the extraordinary nuclear 
occurrence takes place if:
    (1) The claimant is employed exclusively in connection with the 
construction of a nuclear reactor, including all related equipment and 
installations at the facility, and
    (2) No operating license has been issued by the NRC with respect to 
the nuclear reactor, and
    (3) The claimant is not employed in connection with the possession, 
storage, use, or transfer of nuclear material at the facility;
    (d) Shall not apply to any claim for punitive or exemplary damages, 
provided, with respect to any claim for wrongful death under any State 
law which provides for damages only punitive in nature, this exclusion 
does not apply to the extent that the claimant has sustained actual 
damages, measured by the pecuniary injuries resulting from such death 
but not to exceed the maximum amount otherwise recoverable under such 
law;
    (e) Shall be effective only with respect to those obligations set 
forth in this agreement;
    (f) Shall not apply to, or prejudice the prosecution or defense of, 
any claim or portion of claim which is not within the protection 
afforded under (1) the limit of liability provisions under subsection 
170(e) of the Atomic Energy Act of 1954, as amended, and (b) the terms 
of this agreement.

                               Article III

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee and other persons indemnified, as their interest 
may appear, from public liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had belonged to another; 
provided, that the obligation of the Commission under this paragraph 2 
does not apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation;
    (d) The radioactive material.
    3. [Reserved]
    4. (a) The obligations of the Commission under this agreement shall 
apply only with respect to such public liability and such damage to 
property of persons legally liable for the nuclear incident (other than 
such property described in the proviso to paragraph 2 of this Article) 
as in the aggregate exceed $250,000.
    (b) With respect to a common occurrence, the obligations of the 
Commission under this agreement shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to paragraph 2 of this Article) as in the aggregate exceed 
whichever of the following is lower: (1) The sum of the amounts of 
financial protection established under all applicable agreements; or (2) 
an amount equal to the sum of $200,000,000 and the amount available as 
secondary financial protection. As used in this Article applicable 
agreements means each agreement entered into by the Commission pursuant 
to subsection 170(c) or (k) of the Act in which

[[Page 807]]

agreement the nuclear incident is defined as a common occurrence.
    5. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    6. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not 
with respect to any nuclear incident, in the aggregate exceed which ever 
of the following is the lower: (a) $500,000,000 or (b) with respect to a 
common occurrence, $560,000,000 less the sum of the amounts of financial 
protection established under all applicable agreements.
    7. If the licensee is immune from public liability because it is a 
state agency, the Commission shall make payments under the agreement in 
the same manner and to the same extent as the Commission would be 
required to do if the licensee were not such a state agency.
    8. The obligations of the Commission under this agreement, except to 
the licensee for damage to property of the licensee, shall not be 
affected by any failure on the part of the licensee to fulfill its 
obligations under this agreement. Bankruptcy or insolvency of the 
licensee or any other person indemnified or of the estate of the 
licensee or any other person indemnified shall not relieve the 
Commission of any of its obligations hereunder.

                               Article IV

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim including such legal costs of the licensee as are approved 
by the Commission and shall have the right (a) to require the prior 
approval of the Commission for the settlement or payment of any claim or 
action asserted against the licensee or other person indemnified for 
public liability or damage to property of persons legally liable for the 
nuclear incident which claim or action the licensee or the Commission 
may be required to indemnify under this agreement; and (b) to appear 
through the Attorney General of the United States on behalf of the 
licensee or other person indemnified, take charge of such action or 
defend any such action. If the settlement or defense of any such action 
or claim is undertaken by the Commission, the licensee shall furnish all 
reasonable assistance in effecting a settlement or asserting a defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                                Article V

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                               Article VI

    The licensee agrees to pay to the Commission such fees as are 
established by the Commission pursuant to regulations or orders of the 
Commission.

                               Article VII

    The term of this agreement shall commence as of the date and time 
specified in Item 4 of the Attachment and shall terminate at the time of 
expiration of that license specified in Item 2 of the Attachment, which 
is the last to expire; provided that, except as may otherwise be 
provided in applicable regulations or orders of the Commission, the term 
of this agreement shall not terminate until all the radioactive material 
has been removed from the location and transportation of the radioactive 
material from the location has ended as defined in subparagraph 4(b), 
Article I. Termination of the term of this agreement shall not affect 
any obligation of the licensee or any obligation of the Commission under 
this agreement with respect to any nuclear incident occurring during the 
term of this agreement.

               United States Nuclear Regulatory Commission

 Indemnity Agreement No. E-_____________________________________________

                               attachment

Item 1--Licensee _______________________________________________________
Address ________________________________________________________________
Item 2--License number or numbers ______________________________________
Item 3--Location _______________________________________________________

Item 4--The indemnity agreement designated above, of which this 
Attachment is a part, is effective as of ___ m., on the _______ day of 
__________, 19__.
    For the United States Nuclear Regulatory Commission.
                                                       By ______________
                                                  For the ______________
                                                       By ______________
                                                      (Name of licensee)
    Dated at Bethesda, MD, the ______ day of ________, 19__.

[27 FR 2887, Mar. 29, 1962]

    Editorial Note: For Federal Register citations affecting Sec. 
140.95, see the List of CFR Sections Affected, which appears in the

[[Page 808]]

Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 140.96  Appendix F--Indemnity locations.

    (a) Geographical boundaries of indemnity locations. (1) In every 
indemnity agreement between the Commission and a licensee which affords 
indemnity protection for the preoperational storage of fuel at the site 
of a nuclear power reactor under construction, the geographical 
boundaries of the indemnity location will include the entire 
construction area of the nuclear power reactor, as determined by the 
Commission. Such area will not necessarily be coextensive with the 
indemnity location which will be established at the time an operating 
license or combined license under 10 CFR part 52 is issued for such 
additional nuclear power reactors.
    (2) In every indemnity agreement between the Commission and a 
licensee which affords indemnity protection for an existing nuclear 
power reactor, the geographical boundaries of the indemnity location 
shall include the entire construction area of any additional nuclear 
power reactor as determined by the Commission, built as part of the same 
power station by the same licensee. Such area will not necessarily be 
coextensive with the indemnity location which will be established at the 
time an operating license or combined license is issued for such 
additional nuclear power reactors.
    (3) This section is effective May 1, 1973, as to construction 
permits issued before March 2, 1973, and, as to construction permits and 
combined licenses issued on or after March 2, 1973, the provisions of 
this section will apply no later than such time as a construction permit 
or combined license is issued authorizing construction of any additional 
nuclear power reactor.
    (b) [Reserved]

[72 FR 49565, Aug. 28, 2007]



Sec. 140.107  Appendix G--Form of indemnity agreement with licensees 
processing plutonium for use in plutonium processing and fuel 
fabrication plants and furnishing insurance policies as proof of 
financial protection.

    This Indemnity Agreement No. ___ is entered into by and between 
_______ (hereinafter referred to as the licensee) and the United States 
Nuclear Regulatory Commission (hereinafter referred to as the 
Commission) pursuant to subsection 170(c) of the Atomic Energy Act of 
1954, as amended (hereinafter referred to as the Act), and section 201 
of the Energy Reorganization Act of 1974, as amended.

                                Article I

    As used in this agreement:
    1. By product material, person, source material, special nuclear 
material, precautionary evacuation, and extraordinary nuclear occurrence 
shall have the meaning given them in the Atomic Energy Act of 1954, as 
amended, and the regulations issued by the Commission.
    2. Except where otherwise specifically provided, amount of financial 
protection means the amount specified in Item 2a and b, of the 
Attachment annexed hereto as modified by paragraph 6, Article II, with 
respect to common occurrences.
    3. (a) Nuclear incident means any occurrence including an 
extraordinary nuclear occurrence, or series of occurrences at the 
location or in the course of transportation causing bodily injury, 
sickness, disease, or death, or loss of or damage to property, or loss 
of use of property, arising out of or resulting from the radioactive, 
toxic, explosive, or other hazardous properties of the radioactive 
material.
    (b) Any occurrence, including an extraordinary nuclear occurrence, 
or series of occurrences causing bodily injury, sickness, disease or 
death, or loss of or damage to property, or loss of use of property, 
arising out of or resulting from the radioactive, toxic, explosive, or 
other hazardous properties of:
    (i) The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170(c) or (k) of the Act and so discharged 
or dispersed from the location as defined in any such other agreement, 
or
    (ii) The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into by the Commission pursuant to subsection 
170(c) or (k) of the Act as the radioactive material and which is in the 
course of transportation shall be deemed to be a common occurrence. A 
common occurrence shall be deemed to constitute a single nuclear 
incident.
    4. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person 
licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not by predetermination to

[[Page 809]]

be interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto;
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto;
    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170(c) or (k) of the Act.
    5. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    6. Public liability means any legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred by a State, or a political 
subdivision of a State, in the course of responding to a nuclear 
incident or precautionary evacuation), except (1) claims under State or 
Federal Workmen's Compensation Acts of employees of persons indemnified 
who are employed (a) at the location or, if the nuclear incident occurs 
in the course of transportation of the radioactive material, on the 
transporting vehicle, and (b) in connection with the licensee's 
possession, use or transfer of the radioactive material; (2) claims 
arising out of an act of war; and (3) claims for loss of or damage to, 
or loss of use of (a) property which is located at the location and used 
in connection with the licensee's possession, use, or transfer of the 
radioactive material, and (b) if the nuclear incident occurs in the 
course of transportation of the radioactive material, the transporting 
vehicle, containers used in such transportation, and the radioactive 
material.
    7. The location means the location described in Item 4 of the 
Attachment hereto.
    8. The radioactive material means (a) any source, special nuclear, 
or byproduct material which (1) is both used or to be used in, or is 
processed or to be processed by, the licensee's plutonium processing and 
fuel fabrication plant or plants and is subject to the license or 
licenses designated in the Attachment hereto, or (2) is produces as the 
result of the operation of said plant or plants or (b) any source, 
special nuclear, or byproduct material which is waste or contamination 
from material described in paragraph 8(a). The words used or to be used 
and processed or to be processed in this paragraph cover source, special 
nuclear or byproduct material which is in the course of transportation 
as used in the agreement or is received at the plant for use or 
processing in the plant but which is, in fact, for any reason, not so 
used or processed.
    9. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. At all times during the term of the license or licenses 
designated in Item 3 of the Attachment hereto, the licensee will 
maintain financial protection in the amount specified in Item 2 of the 
Attachment and in the form of the nuclear energy liability insurance 
policy designated in the Attachment. If more than one license is 
designated in Item 3 of the Attachment, the licensee agrees to maintain 
such financial protection until the end of the term of that license 
which will be the last to expire. The licensee shall, notwithstanding 
the expiration, termination, modification, amendment, suspension of 
revocation of any license or licenses designated in Item 3 of the 
Attachment, maintain such financial protection in effect until all the 
radioactive material has been removed from the location and 
transportation of the radioactive material from the location has ended 
as defined in subparagraph 4(b), Article I, or until the Commission 
authorizes the termination or the modification of such financial 
protection. The Commission will not unreasonably withhold such 
authorization.
    2. In the event of any payment by the insurer or insurers under a 
policy or policies specified in Item 5 of the Attachment hereto which 
reduces the aggregate limit of such policy or policies below the amount 
of financial protection, the licensee will promptly apply to his 
insurers for reinstatement of the amount specified in Item 2a of the 
Attachment (without reference to paragraph b of Item 2) and will make 
all reasonable efforts to obtain such reinstatement. In the event that 
the licensee has not obtained reinstatement of such amount within ninety 
days after the date of such reduction, and in the absence of good cause 
shown to the contrary, the Commission may issue an order requiring the 
licensee to furnish financial protection for such amount in another 
form.
    3. Any obligations of the licensee under subsection 53e(8) of the 
Act to indemnify the United States and the Commission from public 
liability, together with any public liability satisfied by the insurers 
under the policy or policies designated in the Attachment hereto, shall 
not in the aggregate exceed the amount of financial protection with 
respect to any nuclear incident, including the reasonable costs of 
investigating and settling claims and defending suits for damage.
    4. The obligations of the licensee under this agreement shall apply 
only with respect to nuclear incidents occurring during the term of this 
agreement.

[[Page 810]]

    5. Upon the expiration or revocation of any license designated in 
Item 3 of the Attachment, the Commission will enter into an appropriate 
amendment of this agreement with the licensee reducing the amount of 
financial protection required under this Article: provided, that the 
licensee is then entitled to a reduction in the amount of financial 
protection under applicable Commission regulations and orders.
    6. With respect to any common occurrence,
    (a) If the sum of the limit of liability of any Nuclear Energy 
Liability-Property Insurance Association policy designated in Item 5 of 
the Attachment and the limits of liability of all other nuclear energy 
liability insurance policies (facility form) applicable to such common 
occurrence and issued by Nuclear Energy Liability-Property Insurance 
Association exceeds $155,000,000, the amount of financial protection 
specified in Item 2 a and b of the Attachment shall be deemed to be 
reduced by that proportion of the difference between said sum and 
$155,000,000 as the limit of liability of the Nuclear Energy Liability-
Property Insurance Association policy designated in Item 5 of the 
Attachment bears to the sum of the limits of liability of all nuclear 
energy liability insurance policies (facility form) applicable to such 
common occurrence and issued by Nuclear Energy Liability-Property 
Insurance Association;
    (b) If the sum of the limit of liability of any Mutual Atomic Energy 
Liability Underwriters policy designated in Item 5 of the Attachment and 
the limits of liability of all other nuclear energy liability insurance 
policies (facility form) applicable to such common occurrence and issued 
by Mutual Atomic Energy Liability Underwriters exceeds $45,000,000, the 
amount of financial protection specified in Item 2 a and b of the 
Attachment shall be deemed to be reduced by that proportion of the 
difference between said sum and $45,000,000 as the limit of liability of 
the Mutual Atomic Energy Liability Underwriters policy designated in 
Item 5 of the Attachment bears to the sum of the limits of liability of 
all nuclear energy liability insurance policies (facility form) 
applicable to such common occurrence and issued by Mutual Atomic Energy 
Liability Underwriters;
    (c) If any of the other applicable agreements is with a person who 
has furnished financial protection in a form other than a nuclear energy 
liability insurance policy (facility form) issued by Nuclear Energy 
Liability-Property Insurance Association or Mutual Atomic Energy 
Liability Underwriters, and if also the sum of the amount of financial 
protection established under this agreement and the amounts of financial 
protection established under all other applicable agreements exceeds an 
amount equal to the sum of $200,000,000 and the amount available as 
secondary financial protection, the obligations of the licensee shall 
not exceed a greater proportion of an amount equal to the sum of 
$200,000,000 and the amount available as secondary financial protection 
than the amount of financial protection established under this agreement 
bears to the sum of such amount and the amounts of financial protection 
established under all other applicable agreements.
    (d) As used in this paragraph 6., Article II and in Article III, 
other applicable agreements means each other agreement entered into by 
the Commission pursuant to subsection 170(c). of the Act in which 
agreement the nuclear incident is defined as a common occurrence. As 
used in this paragraph 6., Article II, the obligations of the licensee 
means the obligations of the licensee under subsection 53e(8) of the Act 
to indemnify the United States and the Commission from public liability, 
together with any public liability satisfied by the insurers under the 
policy or policies designated in the Attachment, and the reasonable 
costs incurred by the insurers in investigating and settling claims and 
defending suits for damage.
    7. The obligations of the licensee under this Article shall not be 
affected by any failure or default on the part of the Commission or the 
Government of the United States to fulfill any or all of its obligations 
under this agreement. Bankruptcy or insolvency of any person indemnified 
other than the licensee, or of the estate of any person indemnified 
other than the licensee, shall not relieve the licensee of any of its 
obligations hereunder.

                               Article III

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee and other persons indemnified, as their interest 
may appear, from public liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had belonged to another; 
provided, that the obligation of the Commission under this paragraph 2 
does not apply with respect to:
    (a) Property which is located at the location described in Item 4 of 
the Attachment or at the location described in Item 3 of the 
declarations attached to any nuclear energy liability insurance policy 
designated in Item 5 of the Attachment;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the raidoactive material, the transporting vehicle and containers 
used in such transportation;
    (d) The radioactive material.

[[Page 811]]

    3. [Reserved]
    4. (a) The obligations of the Commission under this agreement shall 
apply only with respect to such public liability and such damage to 
property of persons legally liable for the nuclear incident (other than 
such property described in the proviso to paragraph 2 of this Article) 
as in the aggregate exceed the amount of financial protection.
    (b) With respect to a common occurrence, the obligations of the 
Commission under this agreement shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to paragraph 2 of this Article) as in the aggregate exceed 
$200,000,000.
    5. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    6. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not, 
with respect to any nuclear incident, in the aggregate exceed whichever 
of the following is the lowest: (a) $500,000,000; (b) $560,000,000 less 
the amount of financial protection required under this agreement; or (c) 
with respect to a common occurrence, $560,000,000 less the sum of the 
amounts of financial protection established under this agreement and all 
other applicable agreements.
    7. The obligations of the Commission under this agreement, except to 
the licensee for damage to property of the licensee, shall not be 
affected by any failure on the part of the licensee to fulfill its 
obligations under this agreement. Bankruptcy or insolvency of the 
licensee or any other person indemnified, or of the estate of the 
licensee or any other person indemnified, shall not relieve the 
Commission of any of its obligations hereunder.

                               Article IV

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim (provided that no government indemnity that would otherwise 
be available to pay public liability claims is used for these purposes) 
and shall have the right (a) to require the prior approval of the 
Commission for the settlement or payment of any claim or action asserted 
against the licensee or other person indemnified for public liability or 
damage to property of persons legally liable for the nuclear incident 
which claim or action the licensee or the Commission may be required to 
indemnify under this agreement; and (b) to appear through the Attorney 
General of the United States on behalf of the licensee or other person 
indemnified, take charge of such action and settle or defend any such 
action. If the settlement or defense of any such action or claim is 
undertaken by the Commission, the licensee shall furnish all reasonable 
assistance in effecting a settlement or asserting a defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                                Article V

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                               Article VI

    The licensee agrees to pay the Commission such fees as are 
established by the Commission pursuant to regulations or others of the 
Commission.

                               Article VII

    The term of this agreement shall commence as of the date and time 
specified in Item 6 of the Attachment and shall terminate at the time of 
expiration of that license specified in Item 3 of the Attachment, which 
is the last to expire; provided that, except as may otherwise be 
provided in applicable regulations or orders of the Commission, the term 
of this agreement shall not terminate until all the radioactive material 
has been removed from the location and transportation of the radioactive 
material from the location has ended as defined in paragraph 4(b), 
Article I. Termination of the term of this agreement shall not affect 
any obligation of the licensee or the Commission under this agreement 
with respect to any nuclear incident occurring during the term of this 
agreement.

               United States Nuclear Regulatory Commission

                               attachment

    Indemnity Agreement No. ________
    Item 1--Licensee. _____________
    Item 2--
    a. Amount of financial protection ____
    b. With respect to any nuclear incident, the amount specified in 
Item 2a of this Attachment shall be deemed to be (i) reduced to the 
extent that any payment made by the insurer or insurers under a policy 
or policies specified in Item 5 of this Attachment reduces the aggregate 
amount of such insurance policies below the amount specified in Item 2a 
and (ii) restored to the extent that, following such reduction, the 
aggregate

[[Page 812]]

amount of such insurance polices is reinstated.
    Item 3--License number or numbers___

    Item 4--Location _____________

    Item 5--Insurance Policy No.(s)______

    Item 6--The indemnity agreement designated above, of which this 
Attachment is a part, is effective as of 12:01 a.m., on the _______ day 
of _______, 19__.
    For the U.S. Nuclear Regulatory Commission.

 For____________________________________________________________________
 By_____________________________________________________________________
    Dated at Bethesda, MD, the ____

day of _____ 19__.

[42 FR 51, Jan. 3, 1977, as amended at 42 FR 20141, Apr. 18, 1977; 44 FR 
20633, Apr. 6, 1979; 44 FR 24045, Apr. 24, 1979; 45 FR 37410, June 3, 
1980; 49 FR 11152, Mar. 26, 1984; 54 FR 24160, June 6, 1989]



Sec. 140.108  Appendix H--Form of indemnity agreement with licensees
possessing plutonium for use in plutonium processing and fuel 
fabrication plants and furnishing proof of financial protection
in the form of the licensee's resources.

    This Indemnity Agreement No. ___ is entered into by and between ___ 
(hereinafter referred to as the licensee) and the United States Nuclear 
Regulatory Commission (hereinafter referred to as the Commission) 
pursuant to subsection 170(c) of the Atomic Energy Act of 1954, as 
amended (hereinafter referred to as the Act), and Section 201 of the 
Energy Reorganization Act of 1974, as amended.

                                Article I

    As used in this agreement:
    1. Byproduct material, person, source material, special nuclear 
material, precautionary evacuation, and extraordinary nuclear occurrence 
shall have the meaning given them in the Atomic Energy Act of 1954, as 
amended, and the regulations issued by the Commission.
    2. Amount of financial protection means the amount specified in Item 
2 or the Attachment annexed hereto.
    3. Nuclear incident means any occurrence including an extraordinary 
nuclear occurrence, or series of occurrences at the location or in the 
course of transportation causing bodily injury, sickness, disease, or 
death, or loss of or damage to property, or loss of use of property, 
arising out of or resulting from the radioactive, toxic, explosive, or 
other hazardous properties of the radioactive material.
    (b) Any occurrence, including an extraordinary nuclear occurrence of 
series of occurrences causing bodily injury, sickness, disease or death, 
or loss or damage to property, or loss of use of property, arising out 
of or resulting from the radioactive, toxic, explosive, or other 
hazardous properties of
    i. The radioactive material discharged or dispersed from the 
location over a period of days, weeks, months or longer and also arising 
out of such properties of other material defined as the radioactive 
material in any other agreement or agreements entered into by the 
Commission under subsection 170(c) or (k) of the Act and so discharged 
or dispersed from the location as defined in any such other agreement, 
or
    ii. The radioactive material in the course of transportation and 
also arising out of such properties of other material defined in any 
other agreement entered into the Commission pursuant to subsection 
170(c) or (k) of the Act as the radioactive material and which is in the 
course of transportation shall be deemed to be a common occurrence. A 
common occurrence whall be deemed to constitute a single nuclear 
incident.
    4. In the course of transportation means in the course of 
transportation within the United States, or in the course of 
transportation outside the United States and any other nation, and 
moving from one person licensed by the Commission to another person 
licensed by the Commission, including handling or temporary storage 
incidental thereto, of the radioactive material to the location or from 
the location provided that:
    (a) With respect to transportation of the radioactive material to 
the location, such transportation is not be predetermination to be 
interrupted by the removal of the material from the transporting 
conveyance for any purpose other than the continuation of such 
transportation to the location or temporary storage incidental thereto:
    (b) The transportation of the radioactive material from the location 
shall be deemed to end when the radioactive material is removed from the 
transporting conveyance for any purpose other than the continuation of 
transportation or temporary storage incidental thereto:
    (c) In the course of transportation as used in this agreement shall 
not include transportation of the radioactive material to the location 
if the material is also in the course of transportation from any other 
location as defined in any other agreement entered into by the 
Commission pursuant to subsection 170(c) or (k) of the Act.
    5. Person indemnified means the licensee and any other person who 
may be liable for public liability.
    6. Public liability means any legal liability arising out of or 
resulting from a nuclear incident or precautionary evacuation (including 
all reasonable additional costs incurred

[[Page 813]]

by a State, or a political subdivision of a State, in the course of 
responding to a nuclear incident or precautionary evacuation), except 
(1) claims under State or Federal Workmen's Compensation Acts of 
employees of persons indemnified who are employed (a) at the location 
or, if the nuclear incident occurs in the course of transportation of 
the radioactive material, on the transporting vehicle, and (b) in 
connection with the licensee's possession, use or transfer of the 
radioactive material; (2) claims arising out of an act of war; and (3) 
claims for loss of, or damage to, or loss of use of (a) property which 
is located at the location and used in connection with the licensee's 
possession, use, or transfer of the radioactive material, and (b) if the 
nuclear incident occurs in the course of transportation of the 
radioactive material, the transporting vehicle, containers used in such 
transportation, and the radioactive material.
    7. The location means the location described in Item 4 of the 
Attachment hereto.
    8. The radioactive material means (a) any source, special nuclear, 
or byproduct material which (1) is both used or to be used in, or is 
processed or to be processed by, the licensee's plutonium processing and 
fuel fabrication plant or plants and is subject to the license or 
licenses designated in the Attachment hereto, or (2) is produced as the 
result of the operation of said plant or plants or (b) any source 
special nuclear, or byproduct material which is waste or contamination 
from material described in paragraph 8(a). The words used or to be used 
and processed or to be processed in this paragraph cover source, special 
nuclear or byproduct material which is in the course of transportation 
as used in the agreement or is received at the plant for use or 
processing in the plant but which is, in fact, for any reason, not so 
used or processed.
    9. United States when used in a geographical sense includes Puerto 
Rico and all territories and possessions of the United States.

                               Article II

    1. The licensee undertakes and agrees to indemnify and hold harmless 
all persons indemnified, as their interest may appear, from public 
liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the incident, the licensee agrees to 
pay to such person those sums which such person would have been 
obligated to pay if such property had belonged to another; provided, 
that the obligation of the licensee under this paragraph 2 does not 
apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to neglect of the person indemnified to use 
all reasonable means to save and preserve the property after knowledge 
of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation; and
    (d) The radioactive material.
    3. Any obligations of the licensee under paragraphs 1 and 2 of this 
Article, and subsection 53e(8) of the Act to indemnify the United States 
and the Commission from public liability shall not in the aggregate 
exceed the amount of financial protection with respect to any nuclear 
incident.
    4. The obligations of the licensee under this agreement shall apply 
only with respect to nuclear incidents occurring during the term of this 
agreement.
    5. Upon the expiration or revocation of any license designated in 
Item 3 of the Attachment, the Commission will enter into an appropriate 
amendment of this agreement with the licensee reducing the amount of 
financial protection required under this Article; provided, that the 
licensee is then entitled to a reduction in the amount of financial 
protection under applicable Commission regulations and orders.
    6. With respect to any common occurrence, if the sum of the amount 
of financial protection established under this agreement and the amount 
of financial protection established under all other applicable 
agreements exceeds an amount equal to the sum of $200,000,000 and the 
amount available as secondary financial protection, the obligations of 
the licensee described in paragraph 3 of this Article shall not exceed a 
greater proportion of an amount equal to the sum of $200,000,000 and the 
amount available as secondary financial protection than the amount of 
financial protection established under this agreement bears to the sum 
of such amount and the amounts of financial protection established under 
all other applicable agreements. As used in this paragraph, and in 
Article III, other applicable agreements means each other agreement 
entered into by the Commission pursuant to subsection 170(c) or (k) of 
the Act in which agreement the nuclear incident is defined as a common 
occurrence.
    7. The obligations of the licensee under this Article shall not be 
affected by any failure or default on the part of the Commission or the 
Government or the United States to fulfill any or all of its obligations 
under this agreement. Bankruptcy or insolvency of any person indemnified 
other than the licensee, or of the estate of any person indemnified 
other than the licensee shall not relieve the licensee of any of its 
obligations hereunder.

                               Article III

    1. The Commission undertakes and agrees to indemnify and hold 
harmless the licensee

[[Page 814]]

and other persons indemnified, as their interest may appear, from public 
liability.
    2. With respect to damage caused by a nuclear incident to property 
of any person legally liable for the nuclear incident, the Commission 
agrees to pay to such person those sums which such person would have 
been obligated to pay if such property had belonged to another; 
provided, that the obligation of the Commission under this paragraph 2 
does not apply with respect to:
    (a) Property which is located at the location and used in connection 
with the licensee's possession, use or transfer of the radioactive 
material;
    (b) Property damage due to the neglect of the person indemnified to 
use all reasonable means to save and preserve the property after 
knowledge of a nuclear incident;
    (c) If the nuclear incident occurs in the course of transportation 
of the radioactive material, the transporting vehicle and containers 
used in such transportation;
    (d) The radioactive material.
    3. [Reserved]
    4. (a) The obligations of the Commission under this agreement shall 
apply only with respect to such public liability and such damage to 
property of persons legally liable for the nuclear incident (other than 
such property described in the proviso to paragraph 2 of this Article) 
as in the aggregate exceed the amount of financial protection.
    (b) With respect to a common occurrence, the obligations of the 
Commission under this agreement shall apply only with respect to such 
public liability and such damage to property of persons legally liable 
for the nuclear incident (other than such property described in the 
proviso to paragraph 2 of this Article) as in the aggregate exceed 
$200,000,000.
    5. The obligations of the Commission under this agreement shall 
apply only with respect to nuclear incidents occurring during the term 
of this agreement.
    6. The obligations of the Commission under this and all other 
agreements and contracts to which the Commission is a party shall not, 
with respect to any nuclear incident, in the aggregate exceed whichever 
of the following is the lowest; (a) $500,000,000; (b) $560,000,000 less 
the amount of financial protection required under this agreement; or (c) 
with respect to a common occurrence, $560,000,000 less the sum of the 
amounts of financial protection established under this agreement and all 
other applicable agreements.
    7. The obligations of the Commission under this agreement, except to 
the licensee for damage to property of the licensee, shall not be 
affected by any failure on the part of the licensee to fulfill its 
obligations under this agreement. Bankruptcy or insolvency of the 
licensee or any other person indemnified, or of the estate of the 
licensee or any other person indemnified shall not relieve the 
Commission of any of its obligations hereunder.

                               Article IV

    1. When the Commission determines that the United States will 
probably be required to make indemnity payments under the provisions of 
this agreement, the Commission shall have the right to collaborate with 
the licensee and other persons indemnified in the settlement and defense 
of any claim (provided that no government indemnity that would otherwise 
be available to pay public liability claims is used for these purposes) 
and shall have the right (a) to require the prior approval of the 
Commission for the settlement or payment of any claim or action asserted 
against the licensee or other persons indemnified for public liability 
or damage to property of persons legally liable for the nuclear incident 
which claim or action the licensee or the Commission may be required to 
indemnify under this agreement; and (b) to appear through the Attorney 
General of the United States on behalf of the licensee or other person 
indemnified, take charge of such action and settle or defend any such 
action. If the settlement or defense of any such action or claim is 
undertaken by the Commission, the licensee shall furnish all reasonable 
assistance in effecting a settlement or asserting defense.
    2. Neither this agreement nor any interest therein nor claim 
thereunder may be assigned or transferred without the approval of the 
Commission.

                                Article V

    The parties agree that they will enter into appropriate amendments 
of this agreement to the extent that such amendments are required 
pursuant to the Atomic Energy Act of 1954, as amended, or licenses, 
regulations or orders of the Commission.

                               Article VI

    The licensee agrees to pay the Commission such fees as are 
established by the Commission pursuant to regulations or orders of the 
Commission.

                               Article VII

    The term of this agreement shall commence as of the date and time 
specified in Item 5 of the Attachment and shall terminate at the time of 
expiration of that license specified in Item 3 of the Attachment, which 
is the last to expire; provided that, except as may otherwise be 
provided in applicable regulations or orders of the Commission, the term 
of this agreement shall not terminate until all the radioactive material 
has been removed from the location and transportation of the radioactive 
material from the location has ended as defined in paragraph 4(b), 
Article I. Termination of the term of

[[Page 815]]

this agreement shall not affect any obligation of the licensee or the 
Commission under this agreement with respect to any nuclear incident 
occurring during the term of this agreement.

               United States Nuclear Regulatory Commission

                               attachment

    Indemnity Agreement No. ________
    Item 1--Licensee _____________
    Item 2--Amount of financial protection--
    Item 3--License number or numbers___
    Item 4--Location _____________
    Item 5--The indemnity agreement designated above, of which this 
Attachment is a part, is effective as of 12:01 a.m., on the
_______ day of ________ 19__.
    Dated at Bethesda, MD, the ______ day of _____ 19__.
For the U.S. Nuclear Regulatory Commission.
 For____________________________________________________________________
 By_____________________________________________________________________

[42 FR 53, Jan. 3, 1977, as amended at 42 FR 20142, Apr. 18, 1977; 42 FR 
23501, May 9, 1977; 44 FR 20633, Apr. 6, 1979; 44 FR 24045, Apr. 24, 
1979; 45 FR 37410, June 3, 1980; 49 FR 11152, Mar. 26, 1984; 54 FR 
24161, June 6, 1989]



Sec. 140.109  Appendix I.

             Nuclear Energy Liability Insurance Association

                          master policy no. __

                   Nuclear Energy Liability Insurance

                    (Secondary Financial Protection)

    Named Insured: Each person or organization designated in Item 1 of a 
certificate.
    Policy Period: Beginning on the first day of August, 1977, and 
continuing to the effective date and time of the cancellation or other 
termination of this policy, eastern standard time.
    Limits of Liability: The amount of retrospective premium actually 
received by the companies plus the amount of the companies' contingent 
liability, if any, pursuant to Conditions 2, 3, and 4.
Date of Issue___________________________________________________________
Authorized Representative_______________________________________________
    In consideration of the payment of the annual premium, in reliance 
upon the statements in the certificates and subject to the limits of 
liability, conditions and other terms of this Master Policy, the 
undersigned members of Nuclear Energy Liability Insurance Association 
(hereinafter called the companies), each for itself, severally and not 
jointly, and in the respective proportions herein set forth, and the 
insureds named in the certificates, agree as follows:

                           Insuring Agreements

                  i. nuclear energy liability insurance

                    (Secondary Financial Protection)

    To pay on behalf of or to the insured or to the insured's workers' 
compensation carrier all sums payable as excess losses to which this 
Master Policy applies.

                             ii. definitions

    Bodily injury means bodily injury, sickness or disease, including 
death resulting therefrom, sustained by any person.
    Certificate means a Certificate of Insurance, including Declarations 
and Bond for Payment of Retrospective Premiums, issued to be a part of 
this Master Policy.
    Common nuclear occurrence means any occurrence or series of 
occurrences causing bodily injury or property damage arising out of the 
radioactive, toxic, explosive, or other hazardous properties of nuclear 
material
    (a) Discharged or dispersed from a nuclear reactor described in Item 
3 of a certificate over a period of days, weeks, months, or longer, or
    (b) Discharged or dispersed from a nuclear reactor described in Item 
3 of a certificate over a period of days, weeks, months or longer and 
also arising out of such properties of nuclear material so discharged or 
dispersed from one or more other nuclear reactors described in Item 3 of 
other certificates, or
    (c) In the course of transportation for which protection is afforded 
(or would be afforded but for exhaustion of its limit of liability) 
under the primary financial protection described in Item 4 of a 
certificate and also arising out of such properties of nuclear material 
in the course of transportation for which protection is afforded (or 
would be afforded but for exhaustion of its limit of liability) under 
the primary financial protection described in Item 4 of one or more 
other certificates.
    Damages and claim expenses includes sums estimated by the companies 
to be payable under this policy and payments made by the companies under 
this Master Policy:
    (a) In settlement of claims and in satisfaction of judgments against 
the insureds for damages because of bodily injury or property damage;
    (b) For (1) costs taxed against an insured in any suit against the 
insured seeking damages payable under the terms of this Master Policy 
and interest on any judgment therein, (2) premiums on appeal bonds and 
bonds to release attachments in any such suit and (3) reasonable 
expenses, other than loss of earnings, incurred by the insured at the 
companies' request;
    (c) For expenses incurred in the investigation, negotiation, 
settlement and defense of any claim or suit including, but not limited

[[Page 816]]

to, the cost of such services by salaried employees of the companies, 
fees and expenses of independent adjusters, attorneys' fees and 
disbursements, expenses for expert testimony, inspection and appraisal 
of property, examination, X-ray or autopsy or medical expenses of any 
kind;
    (d) For expenses incurred by the companies in investigating a 
nuclear incident or in minimizing its effects;
    (e) For all other expenses of the companies in fulfilling their 
obligations under this Master Policy, provided that such expenses are 
reasonable and necessary.
    Excess losses means all damages and claim expenses
    (a) Because of bodily injury or property damage to which a 
certificate applies, and
    (b) Which are excess of all sums paid or payable as estimated by the 
companies under all applicable primary financial protection.
    Extraordinary nuclear occurrence has the meaning given it in the 
Atomic Energy Act of 1954, or in any law amendatory thereof.
    Insured means any person or organization identified in Item 1 or 2 
of a certificate.
    Nuclear incident means
    (a) An extraordinary nuclear occurrence, or
    (b) A common nuclear occurrence, or if neither of these,
    (c) An occurrence or series of occurrences, including continuous or 
repeated exposure to substantially the same general conditions, causing 
bodily injury or property damage arising out of the radioactive, toxic, 
explosive, or other hazardous properties of nuclear material.
    Nuclear material means source material, special nuclear material or 
byproduct material.
    Primary financial protection means the insurance policies or other 
contracts identified in Item 4 of a certificate and includes any 
amendment thereto which is consented to by the companies pursuant to 
Condition 6 of this Master Policy.
    Property damage means physical injury to or destruction or 
radioactive contamination of property, and loss of use of property so 
injured, destroyed or contaminated, and loss of use of property while 
evacuated or withdrawn from use because possibly so contaminated or 
because of imminent danger of such contamination.
    Source material, special nuclear material, and byproduct material 
have the meanings given them in the Atomic Energy Act of 1954, or in any 
law amendatory thereof.

                       iii. application of policy

    Insurance is provided by this Master Policy only through a 
certificate. No insurance is afforded with respect to bodily injury or 
property damage caused prior to August 1, 1977 by a nuclear incident.

                               Conditions

                            1. annual premium

    The named insureds designated in a certificate shall pay to the 
companies the annual premium for each calendar year or part thereof.
    Such annual premium shall be determined by the companies and stated 
in a written notice mailed to the first named insured shown in Item 1 of 
a certificate, and shall be due and payable as stated in such notice.

                        2. retrospective premium

    The named insureds designated in a certificate shall pay to the 
companies retrospective premium in the event of excess losses due to 
bodily injury or property damage caused during their certificate period 
by a nuclear incident arising out of or in connection with a nuclear 
reactor described in Item 3 of the certificate or in Item 3 of any other 
certificate. The amount of retrospective premium-due under each 
certificate shall be determined by multiplying such excess losses by the 
ratio of the maximum retrospective premium payable with respect to the 
nuclear incident under the certificate to the total of the maximum 
retrospective premiums payable with respect to the nuclear incident 
under all such certificates.
    If any portion of the bodily injury or property damage to which this 
Master Policy applies is caused during any portion of a certificate 
period by a nuclear incident, the retrospective premium the named 
insureds designated in such certificate are obligated to pay shall be 
determined as if all bodily injury or property damage to which this 
Master Policy applies caused by the nuclear incident had been caused 
during the certificate period of such certificate.
    The maximum retrospective premium that the named insureds designated 
in a certificate shall pay to the companies for all excess losses 
arising out of any one nuclear incident is the amount stated in Item 7 
of their certificate.
    In the event of two more nuclear incidents, the maximum amount of 
retrospective premium that shall be due from and payable by the named 
insureds in one calendar year shall not exceed twice the amount stated 
in Item 7 of their certificate. Any amount in excess thereof shall be 
paid in subsequent calendar years as billed by the companies.
    In addition, an allowance for applicable premium taxes shall be 
determined by the companies and paid to them by the named insureds at 
the time retrospective premiums are due and payable.
    After a nuclear incident resulting in excess losses, the companies 
shall mail to the first named insured designated in Item 1 of a 
certificate written notice of the retrospective premium and allowance 
for premium taxes

[[Page 817]]

then due under such certificate. Such notice shall also constitute 
notice to all other named insureds designated in such certificate. The 
named insureds shall pay directly to the Nuclear Energy Liability 
Insurance Association the retrospective premium and allowance for 
premium taxes stated in the notice. The notice shall specify a date no 
earlier than 60 days after mailing by which time payment is to be 
received by the Nuclear Energy Liability Insurance Association.
    The companies shall at least annually review their estimate of 
excess losses arising out of the nuclear incident and shall adjust the 
retrospective premium and allowance for premium taxes accordingly. If 
the amount due from the named insureds is increased, written notice 
shall be mailed to the first named insured in accordance with the 
foregoing paragraph; if deceased the companies shall return the excess 
to the first named insured.
    The obligation of the named insureds to pay retrospective premium 
and the allowance for premium taxes for excess losses arising out of a 
nuclear incident shall continue until the named insureds have paid the 
maximum retrospective premium stated in Item 7 of their certificate plus 
allowance for premium taxes.
    The companies shall send to the Nuclear Regulatory Commission 
summaries of their estimates of excess losses arising out of the nuclear 
incident and their computations of retrospective premium and the 
allowance for premium taxes due.
    All retrospective premium (but not the allowance for premium taxes) 
received by the companies is to be held by the companies separate from 
the companies' other assets and is to be used by the companies only for 
the purpose of paying excess losses. Any investment income received by 
the companies from such retrospective premium shall accrue to the 
benefit of the named insureds. This paragraph shall not apply to any 
retrospective premium received by the companies as reimbursement for any 
funds expended pursuant to Condition 4.
    No commission will be paid with respect to retrospective premium and 
allowance for premium taxes.

                          3. limit of liability

    Regardless of the number of
    (a) Persons or organizations who are insureds under this Master 
Policy, or
    (b) Claims made and suits brought against any and all insureds, or
    (c) Policies or contracts of primary financial protection or 
certificates which apply to the nuclear incident, or
    (d) Years this Master Policy and any certificate shall continue in 
force,

The total liability of the companies under this Master Policy for all 
excess losses arising out of any nuclear incident shall not exceed the 
amount of retrospective premium actually received by the companies 
pursuant to Condition 2 with respect to such nuclear incident plus the 
companies' contingent liability, if any, as determined by Condition 4. 
Reimbursement of the companies for funds expended pursuant to Condition 
4 shall not operate to increase the total liability of the companies.

                4. contingent liability of the companies

    The companies have a contingent liability under this Master Policy 
for payment of excess losses but only if, and to the extent that, the 
retrospective premium due under one or more certificates is not paid. In 
the event of any such failure to pay retrospective premiums, the 
companies' obligations under this Condition 4 are limited as follows:
    Regardless of the number of nuclear incidents which cause bodily 
injury or property damage to which this Master Policy applies, the 
number of years this Master Policy is in force, the number of 
certificates issued or in effect, or the number of annual premiums paid 
or payable.
    (a) The total contingent liability of the companies for all excess 
losses arising out of two or more nuclear incidents shall not exceed 
$46,500,000;
    (b) Subject to the above provision (a), the total contingent 
liability of the companies for all excess losses arising out of any one 
nuclear incident shall not exceed $23,250,000;
    (c) Subject to the above provisions (a) and (b), the maximum amount 
to be paid by the companies in any one calendar year because of 
contingent liability for excess losses shall not exceed $23,250,000.
    If a named insured designated in a certificate shall become 
insolvent or be adjudged bankrupt, the companies' obligation under this 
Condition 4 shall not apply to the failure of any named insured 
designated in such certificate to pay retrospective premium with respect 
to excess losses because of bodily injury or property damage caused 
after the date of such insolvency or bankruptcy.

       5. investigation, defense or settlement of claims or suits

    Subject to the provisions of any written agreement between the 
companies and the Nuclear Regulatory Commission, the companies shall 
defend any claim or suit alleging bodily injury or property damage 
caused by a nuclear incident and seeking damages which are payable under 
this Master Policy, and may make such investigation and settlement of 
any claim or suit as they deem expedient. In no event shall the 
companies be obligated to pay any claim or judgment or to defend any 
claim or suit after the companies have paid the amount of retrospective 
premium actually received for excess losses arising out

[[Page 818]]

of the nuclear incident plus the amount of their contingent liability, 
if any.

                     6. primary financial protection

    Regardless of the number of policies or contracts of primary 
financial protection applicable to a nuclear incident, the limit of 
liability of all such policies or contracts shall be deemed to be 
exhausted when the sums paid under all such policies or contracts are 
equal to the lesser of (1) the sum of the limits of liability available 
under all such primary financial protection or (2) one hundred forty 
million dollars.
    The named insured designated in a certificate shall maintain in full 
effect during the currency of such certificate the primary financial 
protection described therein, except for any reduction of the limit of 
liability of such primary financial protection solely as the result of 
sums paid thereunder. Failure of the named insureds to comply with the 
foregoing shall not invalidate this Master Policy, but in the event of 
such failure the companies shall be liable only to the extent that they 
would have been liable and the named insureds complied therewith.
    In the event that the limit of liability of the primary financial 
protection is reduced, such names insureds shall immediately inform the 
companies thereof and make all reasonable efforts to reinstate such 
limit.
    Upon the companies' request the named insureds shall provide the 
companies with a certified copy of any policy or other contract of 
primary financial protection. No amendment of the primary financial 
protection shall increase, extend or broaden the insurance provided by 
this Master Policy unless the companies agree to the amendment by an 
endorsement issued to form a part of this Master Policy.

  7. interest to be paid by named insured on retrospective premium and 
                 allowance for premium taxes in default

    If retrospective premium or allowance for premium taxes is not paid 
when due by the named insureds designated in Item 1 of a certificate, 
such named insureds shall be obligated to pay, in addition to the amount 
in default, interest thereon during the period of default. Such interest 
shall be computed at an annual rate equal to the sum of (a) three 
percent plus (b) a rate of interest equal to Moody's Average Public 
Utility Bond Yield described in the issue of Moody's Bond Survey current 
on the date that the retrospective premium and allowance for premium 
taxes were due. The annual rate of interest shall be adjusted monthly 
during the period of default to reflect any revisions of Moody's Average 
Public Utility Bond Yield described in the issue of Moody's Bond Survey 
current on the first business day of each such month.
    The interest so received shall be used to pay to the companies 
interest at the annual rate described above for any funds the companies 
have paid pursuant to Condition 4. Any balance remaining shall accrue to 
the benefit of named insureds not in default as if it were investment 
income on retrospective premium.

              8. notice of nuclear incident, claim or suit

    In the event of bodily injury or property damage to which this 
Master Policy applies or of a nuclear incident which may give rise to 
claims therefor, written notice containing particulars sufficient to 
identify the insured and also reasonably obtainable information with 
respect to the time, place and circumstances thereof, and the names and 
addresses of the injured and of available witnesses, shall be given by 
or for the insured to Nuclear Energy Liability Insurance Association or 
the companies as soon as practicable. If claim is made or suit is 
brought against the insured, the insured shall immediately forward to 
Nuclear Energy Liability Insurance Association or the companies every 
demand, notice, summons or other process received by or on behalf of the 
insured.

              9. assistance and cooperation of the insured

    The insured shall cooperate with the companies and, upon the 
companies' request, attend hearings and trials and assist in making 
settlements, in securing and giving evidence, in obtaining the 
attendance of witnesses and in the conduct of any legal proceedings in 
connection with the subject matter of this insurance. The insured shall 
not, except at the insured's own cost, make any payment, assume any 
obligation or incur any expense.

                      10. action against companies

    No action shall lie against the companies or any of them unless, as 
a condition precedent thereto, the insured shall have fully complied 
with all the terms of this Master Policy, nor until the amount of the 
insured's obligation to pay shall have been finally determined either by 
judgment against the insured after actual trial or by written agreement 
of the insured, the claimant and the companies.
    Any person or organization or the legal representative thereof who 
has secured such judgment or written agreement shall thereafter be 
entitled to recover under this Master Policy to the extent of the 
insurance afforded by this Master Policy. No person or organization 
shall have any right under this Master Policy to join the companies or 
any of them as parties to any action against the insured to determine 
the insured's liability, nor shall the companies or any of them be 
impleaded by the insured or the insured's legal representative. Except 
as provided in

[[Page 819]]

Condition 4, bankruptcy or insolvency of the insured or of the insured's 
estate shall not relieve the companies of any of their obligations 
hereunder.

                             11. subrogation

    In the event of any payment under this Master Policy, the companies 
may participate with the insured and any underlying insurer in the 
exercise of all the insured's rights of recovery against any person or 
organization liable therefor. Prior to knowledge of bodiliy injury or 
property damage to which this Master Policy applies or of a nuclear 
incident which may give rise to claims therefor, the insured may waive 
in writing any right of recovery against any person or organization. 
After such knowledge, the insured shall not waive or otherwise prejudice 
any such right of recovery but shall do everything necessary to secure 
such rights. Recoveries shall be applied first to reimburse any person 
or organization (including the insured) that may have paid any amount 
with respect to liability in excess of the limit of the companies' 
liability hereunder; then to reimburse the companies up to the amount 
paid hereunder; and lastly to reimburse anyone entitiled to claim the 
residue, if any. A different apportionment maybe made by agreement 
signed by all parties affected.
    Reasonable expenses incurred in the exercise of rights of recovery 
shall be apportioned in the ratio of the respective losses for which 
recovery is sought. The companies shall, after deducting all of their 
expenses in securing recovery, apply the net amount of recoveries made 
by the companies as a credit in determining the amount of excess losses.

                           12. other insurance

    This insurance shall be excess insurance over primary financial 
protection.
    This insurance is concurrent with insurance afforded by a Master 
Policy--Nuclear Energy Liability Insurance (Secondary Financial 
Protection) issued to the named insured by Mutual Atomic Energy 
Liability Underwriters, hereinafter called concurrent insurance. The 
companies shall not be liable under this Master Policy for a greater 
proportion of excess losses than the applicable limit of liability 
described in Condition 3 bears to the sum of (a) such limit plus (b) the 
applicable limit of liability of such concurrent insurance.
    If the insured has other valid and collectible insurance (other than 
primary financial protection or concurrent insurance) applicable to 
excess losses covered by this Master Policy, the insurance afforded by 
this Master Policy shall be primary insurance under such other 
insurance.

                               13. changes

    Notice to any agent or knowledge possessed by any agent or by any 
other person shall not effect a waiver or a change in any part of this 
Master Policy or estop the companies from asserting any right under the 
terms of this Master Policy; nor shall the terms of this Master Policy 
be waived or changed, except by endorsement executed by Nuclear Energy 
Liability Insurance Association on behalf of the companies and issued to 
form a part of this Master Policy.

                             14. assignment

    Assignment of interest by the named insured shall not bind the 
companies until their consent is endorsed hereon; if, however, the named 
insured shall die or be declared bankrupt or insolvent, this Master 
Policy shall cover such named insured's legal representative, receiver 
or trustee as an insured under this Master Policy, but only with respect 
to such legal representative's, receiver's or trustee's liability as 
such, and then only provided written notice of the legal 
representative's, receiver's or trustee's appointment as such is given 
to the companies within ten days after such appointment.

       15. custodian of the policy--nuclear regulatory commission

    The named insureds have designated the Nuclear Regulatory Commission 
as the custodian of this Master Policy and any endorsements thereto.

                            16. cancellation

    The first named insured designated in Item 1 of a certificate may 
cancel such certificate by mailing to the companies and the Nuclear 
Regulatory Commission written notice stating when, not less than thirty 
days thereafter, such cancellation shall be effective.
    The companies may cancel any certificate by mailing to the first 
named insured designated in Item 1 of such certificate written notice 
stating when, not less than ninety days thereafter, such cancellation 
shall be effective; provided that in the event of non-payment of any 
annual premium, retrospective premium or allowance for premium taxes due 
under a certificate, such certificate may be canceled by the companies 
by mailing to the first named insured designated therein written notice 
stating when, not less than thirty days thereafter, such cancellation 
shall be effective.
    The mailing of notice as aforesaid shall be sufficient proof of 
notice. The effective date and time of cancellation stated in the notice 
shall become the end of the certificate period. Delivery of such written 
notice, either by the first named insured designated in Item 1 of a 
certificate or by the companies, shall be equivalent to mailing.

[[Page 820]]

    A copy of the companies' cancellation notice shall be mailed to the 
Nuclear Regulatory Commission, but mailing such copy is not a condition 
of cancellation.
    If a certificate is canceled, the earned portion of the annual 
premium shall be computed pro-rata. Adjustment of the annual premium, if 
any, may be made either at the time cancellation is effective or as soon 
as practicable after cancellation becomes effective, but payment or 
tender of unearned premium is not a condition of cancellation.
    Cancellation or termination of any certificate shall not terminate 
the obligation of a named insured to pay retrospective premium and the 
allowance for premium taxes as provided in such named insured's 
certificate and Condition 2 of this Master Policy.
    This Master Policy shall terminate automatically on the effective 
date and time of cancellation or termination of the last certificate in 
effect.

                       17. company representation

    (a) Any notice, sworn statement or proof of loss which may be 
required by the provisions of this Master Policy may be given to any one 
of the companies, and such notice, statement or proof of loss so given 
shall be valid and binding as to all companies.
    (b) In any action or suit against the companies, service of process 
may be made on any one of them and such service shall be deemed valid 
and binding service on all companies.
    (c) Nuclear Energy Liability Insurance Association is the agent of 
the companies with respect to all matters pertaining to this insurance. 
All notices or other communications required by this Master Policy to be 
given to the companies may be given to such agent, at its office at The 
Exchange, Suite 245, 270 Farmington Avenue, Farmington, Connecticut--
06032 with the same force and effect as if given directly to the 
companies. Any requests, demands or agreements made by such agent shall 
be deemed to have been made directly by the companies.

                18. authorization of first named insured

    Except with respect to compliance with the obligations imposed on 
the insured by Conditions 8, 9, 10 and 11 of this Master Policy, the 
first named insured designated in Item 1 of a certificate is authorized 
to act for every other person and organization insured under such 
certificate in all matters pertaining to this insurance.

    19. changes in subscribing companies and in their proportionate 
                                liability

    The members of Nuclear Energy Liability Insurance Association 
subscribing this Master Policy, and the proportionate liability of each, 
may change from time to time.
    Each company subscribing this Master Policy upon its issuance shall 
be liable only for its stated proportion of any obligation assumed or 
expense incurred under this Master Policy because of bodily injury or 
property damage caused during the period from the effective date of this 
Master Policy to the close of December 31 next following. For each 
subsequent calendar year, beginning January 1 next following the 
effective date of this Master Policy, the subscribing companies and the 
proportionate liability of each such company shall be stated in an 
endorsement issued to form a part of this Master Policy, duly executed 
by the President of Nuclear Energy Liability Insurance Association on 
behalf of each such company, and mailed or delivered to the Nuclear 
Regulatory Commission.

                            20. declarations

    By acceptance of this Master Policy, the named insureds designated 
in a certificate agree that the statements in such certificate are their 
agreements and representations, that this Master Policy and such 
certificate are issued in reliance upon the truth of such 
representations and that this Master Policy and such certificate embody 
all agreements between such named insureds and the companies or any of 
their agents relating to this insurance.
    In witness whereof each of the subscribing companies has caused this 
Master Policy to be executed on its behalf by the Nuclear Energy 
Liability Insurance Association and duly countersigned on the first page 
by an authorized representative.
    For the Subscribing Companies of NUCLEAR ENERGY LIABILITY INSURANCE 
ASSOCIATION
By:

Burt C. Proom,
President.

             Nuclear Energy Liability Insurance Association

Certificate No._________________________________________________________
Forming Part of Master Policy No._______________________________________
________________________________________________________________________

     certificate of insurance declarations and bond for payment of 
                         retrospective premiums

                        Certificate of Insurance

    This is to certify that the persons and organizations designated in 
Item 1 of the Declarations are named insureds under the Master Policy--
Nuclear Energy Liability Insurance (Secondary Financial Protection), 
herein called the Master Policy, issued by Nuclear Energy Liability 
Insurance Association.
    Such insurance as is provided by the Master Policy applies, through 
this certificate, only:

[[Page 821]]

    (a) to the insureds identified in Items 1 and 2 of the Declarations,
    (b) for the certificate period stated in Item 6 of the Declarations,
    (c) to bodily injury or property damage
    (1) with respect to which the primary financial protection described 
in Item 4 of the Declarations would apply but for exhaustion of its 
limit of liability as described in Condition 6 of the Master Policy, and
    (2) which is caused during the certificate period stated in Item 6 
of the Declarations by a nuclear incident arising out of or in 
connection with the nuclear reactor described in Item 3 of the 
Declarations, and
    (3) which is discovered and for which written claim is made against 
the injured not later than ten years after the end of the certificate 
period stated in Item 6 of the Declarations. However, with respect to 
bodily injury or property damage caused by an extraordinary nuclear 
occurrence this subparagraph (3) shall not operate to bar coverage for 
bodily injury or property damage which is discovered and for which 
written claim is made against the insured not later than twenty years 
after the date of the extraordinary nuclear occurrence.

                              declarations

    Item 1. Named insureds and addresses:
    (a)
    (b)
    Item 2. Additional insureds:
    Any other person or organization who would be insured under the 
primary financial protection identified in Item 4 of the Declarations 
but for exhaustion of the limit of liability of such primary financial 
protection.
    Item 3. Description and location of nuclear reactor:
    Item 4. (a) Identification of primary financial protection 
applicable to the nuclear reactor and limit(s) of liability thereof:
Nuclear Energy Liability Insurance Association's Policy NF- $108,500,000
Mutual Atomic Energy Liability Underwriters' Policy MF- $31,500,000
    (b) The following endorsements, attached to the primary financial 
protection policies listed in Item 4(a) also apply to the insurance 
afforded by the Master Policy through this certificate as though they 
were attached hereto:
    (1) Waiver of Defense Endorsement (Extraordinary Nuclear Occurrence) 
and
    (2) Supplementary Endorsement--Waiver of Defenses--Reactor 
Construction at the Facility,
    (c) The limits of liability provided under the primary financial 
protection specified in Item 4(a) above are not shared with any other 
reactor except as follows:
    Item 5. Limits of Liability: The amount of retrospective premium 
actually received by the companies plus the amount of the companies' 
contingent liability, if any, pursuant to Conditions 2, 3, and 4 of the 
Master Policy.
    Item 6. Certificate Period: Beginning at 12:01 a.m. on ______ and 
continuing to the effective date and time of cancellation or termination 
of the Master Policy or this certificate, whichever first occurs, 
eastern standard time.
    Item 7. Maximum retrospective premium (exclusive of allowance for 
premium taxes) payable pursuant to Condition 2 of the Master Policy with 
respect to each nuclear incident: $3,875,000.
    Item 8. Premium payable pursuant to Condition 1 of the Master Policy 
for the period from ______ through December 31 following: $___.

               Bond for Payment of Retrospective Premiums

    Know All Men By These Presents, that the undersigned do hereby 
acknowledge that they are named insureds under the Master Policy 
described in the above Certificate of Insurance and Declarations. The 
named insureds do hereby convenant with and are held and are firmly 
bound to the members of Nuclear Energy Liability Insurance Association 
subscribing the Master Policy (hereinafter called the companies) to pay 
the companies all retrospective premiums and allowances for premium 
taxes which shall become due and payable in accordance with the Master 
Policy, as it may be changed from time to time, with interest on such 
premiums and allowances for taxes to be computed at the rate provided in 
the Master Policy from the date payment thereof is specified to be due 
the companies in written notice to the first named insured as provided 
in Condition 2 of the Master Policy until paid;
    And it is hereby expressly agreed that copies of written notices of 
retrospective premiums and allowances for premium taxes due and payable 
or other evidence of such amounts due and payable sworn to by a duly 
authorized representative of the companies shall be prima facie evidence 
of the fact and extent of the liability of the named insureds for such 
amounts;
    And it is further expressly agreed that the named insureds will 
indemnify the companies against any and all liability, losses and 
expenses of whatsoever kind or nature (including but not limited to 
interest, court cost, and counsel fees) which the companies may sustain 
or incur (1) by reason of the failure of the named insureds to comply 
with the convenants and provisions of this Bond and (2) in enforcing any 
of the convenants or provisions of this Bond, or any provisions of the 
Master Policy relating to such convenants or provisions;
    For the purpose of recording this agreement, a photocopy 
acknowledged before a Notary Public to be a true copy hereof shall be 
regarded as an original.
    The preceding Certificate of Insurance, Declarations and Bond form a 
part of the

[[Page 822]]

Master Policy. Cancellation or termination of the Master Policy or the 
Certificate of Insurance shall not affect the named insured's 
obligations under the policy or the Bond to pay the retrospective 
premiums and allowances for premium taxes, as provided in this 
Certificate and Condition 2 of the Master Policy.
    In witness whereof, the named insureds have caused the Declaration 
and the Bond for Payment of Retrospective Premiums to be signed and 
sealed by a duly authorized officer, to be effective ______ eastern 
standard time.
Attest or Witness
Named Insureds:
By______________________________________________________________________
(Seal)
(Signature of Officer)
________________________________________________________________________
(type or print Name & Title of Officer)
Date:___________________________________________________________________
    In witness whereof, the companies subscribing the Master Policy have 
caused the Certificate of Insurance and the Declarations to be signed on 
their behalf by the President of Nuclear Energy Liability Insurance 
Association to be effective _____ eastern standard time, and 
countersigned below by a duly authorized representative.
    For the Subscribing Companies of Nuclear Energy Liability Insurance 
Association.
By: President___________________________________________________________
Countersigned by________________________________________________________
(Authorized Representative)

[49 FR 11153, Mar. 26, 1984]



PART 150_EXEMPTIONS AND CONTINUED REGULATORY AUTHORITY IN AGREEMENT
STATES AND IN OFFSHORE WATERS UNDER SECTION 274--Table of Contents



                           General Provisions

Sec.
150.1 Purpose.
150.2 Scope.
150.3 Definitions.
150.4 Communications.
150.5 Interpretations.

      Continued Commission Regulatory Authority in Offshore Waters

150.7 Persons in offshore waters not exempt.
150.8 Information collection requirements: OMB approval.

                     Exemptions in Agreement States

150.10 Persons exempt.
150.11 Critical mass.

      Continued Commission Regulatory Authority in Agreement States

150.14 Commission regulatory authority for physical protection.
150.15 Persons not exempt.
150.15a Continued Commission authority pertaining to byproduct material.

           Continued Commission Authority in Agreement States

150.16 Submission to Commission of nuclear material transaction reports.
150.17 Submission to Commission of nuclear material status reports.
150.17a Compliance with requirements of US/IAEA Safeguards Agreement.
150.19 Submission to Commission of tritium reports.

                               Reciprocity

150.20 Recognition of Agreement State licenses.
150.21 Transportation of special nuclear material by aircraft.

                               Enforcement

150.30 Violations.
150.31 Requirements for Agreement State regulation of byproduct 
          material.
150.32 Funds for reclamation or maintenance of byproduct material.
150.33 Criminal penalties.

    Authority: Atomic Energy Act of 1954, secs. 11, 53, 81, 83, 84, 122, 
161, 181, 223, 234, 274 (42 U.S.C. 2014, 2201, 2231, 2273, 2282, 2021); 
Energy Reorganization Act of 1974, sec. 201 (42 U.S.C. 5841); Nuclear 
Waste Policy Act of 1982, secs. 135, 141 (42 U.S.C. 10155, 10161); 44 
U.S.C. 3504 note.
    Sections 150.3, 150.15, 150.15a, 150.31, 150.32 also issued under 
Atomic Energy Act secs. 11e(2), 81, 83, 84 (42 U.S.C. 2014e(2), 2111, 
2113, 2114).
    Section 150.14 also issued under Atomic Energy Act sec. 53 (42 
U.S.C. 2073).
    Section 150.15 also issued under Nuclear Waste Policy Act sec. 135 
(42 U.S.C. 10155, 10161).
    Section 150.17a also issued under Atomic Energy Act sec. 122 (42 
U.S.C. 2152).
    Section 150.30 also issued under Atomic Energy Act sec. 234 (42 
U.S.C. 2282).

    Source: 27 FR 1352, Feb. 14, 1962, unless otherwise noted.

                           General Provisions



Sec. 150.1  Purpose.

    The regulations in this part provide certain exemptions to persons 
in Agreement States from the licensing requirements contained in 
chapters 6,

[[Page 823]]

7, and 8 of the Act and from the regulations of the Commission imposing 
requirements upon persons who receive, possess, use or transfer 
byproduct material, source, or special nuclear material in quantities 
not sufficient to form a critical mass; and to define activities in 
Agreement States and in offshore waters over which the regulatory 
authority of the Commission continues. The provisions of the Act, and 
regulations of the Commission apply to all persons in Agreement States 
and in offshore waters engaging in activities over which the regulatory 
authority of the Commission continues.

[46 FR 44151, Sept. 3, 1981]



Sec. 150.2  Scope.

    The regulations in this part apply to all States that have entered 
into agreements with the Commission or the Atomic Energy Commission 
pursuant to subsection 274b of the Act. This part also gives notice to 
all persons who knowingly provide to any licensee, applicant for a 
license or certificate or quality assurance program approval, holder of 
a certificate or quality assurance program approval, contractor, or 
subcontractor, any components, equipment, materials, or other goods or 
services that relate to a licensee's, certificate holder's, quality 
assurance program approval holder's or applicant's activities subject to 
this part, that they may be individually subject to NRC enforcement 
action for violation of Sec. Sec. 30.10, 40.10, 61.9b, 70.10, and 71.8.

[63 FR 1901, Jan. 13, 1998, as amended at 80 FR 63419, Oct. 20, 2015]



Sec. 150.3  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954 (68 Stat. 919) including any 
amendments thereto;
    Agreement State means any State with which the Commission or the 
Atomic Energy Commission has entered into an effective agreement under 
subsection 274b of the Act. Nonagreement State means any other State.
    Byproduct material means--
    (1) Any radioactive material (except special nuclear material) 
yielded in, or made radioactive by, exposure to the radiation incident 
to the process of producing or using special nuclear material;
    (2) The tailings or wastes produced by the extraction or 
concentration of uranium or thorium from ore processed primarily for its 
source material content, including discrete surface wastes resulting 
from uranium solution extraction processes. Underground ore bodies 
depleted by these solution extraction operations do not constitute 
``byproduct material'' within this definition;
    (3)(i) Any discrete source of radium-226 that is produced, 
extracted, or converted after extraction, before, on, or after August 8, 
2005, for use for a commercial, medical, or research activity; or
    (ii) Any material that--
    (A) Has been made radioactive by use of a particle accelerator; and
    (B) Is produced, extracted, or converted after extraction, before, 
on, or after August 8, 2005, for use for a commercial, medical, or 
research activity; and
    (4) Any discrete source of naturally occurring radioactive material, 
other than source material, that--
    (i) The Commission, in consultation with the Administrator of the 
Environmental Protection Agency, the Secretary of Energy, the Secretary 
of Homeland Security, and the head of any other appropriate Federal 
agency, determines would pose a threat similar to the threat posed by a 
discrete source of radium-226 to the public health and safety or the 
common defense and security; and
    (ii) Before, on, or after August 8, 2005, is extracted or converted 
after extraction for use in a commercial, medical, or research activity.
    Commission means the Nuclear Regulatory Commission or its duly 
authorized representatives;
    Discrete source means a radionuclide that has been processed so that 
its concentration within a material has been purposely increased for use 
for commercial, medical, or research activities.
    Foreign obligations means the commitments entered into by the U.S. 
Government under Atomic Energy Act

[[Page 824]]

(AEA) section 123 agreements for cooperation in the peaceful uses of 
atomic energy. Imports and exports of material or equipment pursuant to 
such agreements are subject to these commitments, which in some cases 
involve an exchange of information on imports, exports, retransfers with 
foreign governments, peaceful end-use assurances, and other conditions 
placed on the transfer of the material or equipment. The U.S. Government 
informs the licensee of obligations attached to material.
    Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the Government.
    Offshore waters means that area of land and water, beyond Agreement 
States' Submerged Lands Act jurisdiction, on or above the U.S. Outer 
Continental Shelf.
    Person means: (1) Any individual, corporation, partnership, firm, 
association, trust, estate, public or private institution, group, 
agency, and State or any political subdivision of any political entity 
within a State, and any legal successor, representative, agent, or 
agency of the foregoing other than Government agencies;
    Production facility means:
    (1) Any equipment or device determined by rule of the Commission to 
be capable of the production of special nuclear material in such 
quantity as to be of significance to the common defense and security, or 
in such manner as to affect the health and safety of the public, 
including a uranium enrichment facility; or
    (2) Any important component part especially designed for such 
equipment or device as determined by the Commission.
    Reconciliation means the process of evaluating and comparing 
licensee reports required under this part to the projected material 
balances generated by the Nuclear Materials Management and Safeguards 
System. This process is considered complete when the licensee resolves 
any differences between the reported and projected balances, including 
those listed for foreign obligated materials.
    Source material means:
    (1) Uranium, thorium, or any other material which is determined by 
the Commission pursuant to the provisions of section 61 of the Act to be 
source material; or
    (2) Ores containing one or more of the foregoing materials, in such 
concentration as the Commission may by regulation determine from time to 
time;
    Special nuclear material means:
    (1) Plutonium, uranium 233, uranium enriched in the isotope 233 or 
in the isotope 235, and any other material which the Commission, 
pursuant to the provisions of section 51 of the Act, determines to be 
special nuclear material, but does not include source material; or
    (2) Any material artificially enriched by any of the foregoing but 
does not include source material;
    State means any State, the District of Columbia, Puerto Rico, and 
any territory or possession of the United States; and
    Utilization facility means:
    (1) Any equipment or device, except an atomic weapon, determined by 
rule of the Commission to be capable of making use of special nuclear 
material in such quantity as to be of significance to the common defense 
and security, or in such manner as to affect the health and safety of 
the public, or peculiarly adapted for making use of atomic energy in 
such quantity as to be of significance to the common defense and 
security, or in such manner as to affect the health and safety of the 
public; or
    (2) Any important component part especially designed for such 
equipment or device as determined by the Commission.
    Uranium enrichment facility means:
    (1) Any facility used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or

[[Page 825]]

    (2) Any equipment or device, or important component part especially 
designed for such equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.

[27 FR 1352, Feb. 14, 1962, as amended at 31 FR 15145, Dec. 2, 1966; 40 
FR 8794, Mar. 3, 1975; 44 FR 55327, Sept. 26, 1979; 45 FR 18906, Mar. 
24, 1980; 46 FR 44152, Sept. 3, 1981; 57 FR 18394, Apr. 30, 1992; 68 FR 
10365, Mar. 5, 2003; 72 FR 55934, Oct. 1, 2007; 73 FR 32464, June 9, 
2008]



Sec. 150.4  Communications.

    Except where otherwise specified in this part, all communications 
and reports concerning the regulations in this part should be sent by 
mail addressed: ATTN: Document Control Desk, Director, Office of Nuclear 
Material Safety and Safeguards, and sent either by mail to the U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand 
delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland; or, where practicable, by electronic submission, for example, 
via Electronic Information Exchange, or CD-ROM. Electronic submissions 
must be made in a manner that enables the NRC to receive, read, 
authenticate, distribute, and archive the submission, and process and 
retrieve it a single page at a time. Detailed guidance on making 
electronic submissions can be obtained by visiting the NRC's Web site at 
http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of Information Services, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. The 
guidance discusses, among other topics, the formats the NRC can accept, 
the use of electronic signatures, and the treatment of nonpublic 
information.

[73 FR 5727, Jan. 31, 2008, as amended at 74 FR 62686, Dec. 1, 2009; 79 
FR 75742, Dec. 19, 2014; 80 FR 74982, Dec. 1, 2015]



Sec. 150.5  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by an 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.

      Continued Commission Regulatory Authority in Offshore Waters



Sec. 150.7  Persons in offshore waters not exempt.

    Persons in offshore waters are not exempt from the Commission's 
licensing and regulatory requirements with respect to byproduct, source, 
and special nuclear materials.

[46 FR 44152, Sept. 3, 1981]



Sec. 150.8  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0032.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec. 150.16, 150.17, 150.17a, 150.19, 150.20, 
and 150.31.
    (c) This part contains information collection requirements in 
addition to those approved under the control number specified in 
paragraph (a) of this section. These information collection requirements 
and the control numbers under which they are approved are as follows:
    (1) In Sec. 150.16, DOE/NRC FORM 741 and its computer-readable 
format are approved under control number 3150-0003.
    (2) In Sec. 150.17, DOE/NRC Form 742 and its computer-readable 
format are approved under control number 3150-0004, and DOE/NRC Form 
742C and its computer-readable format are approved under control number 
3150-0058.
    (3) In Sec. 150.17a, Form N-71 and associated forms are approved 
under OMB control number 3150-0056 and DOC/NRC Forms AP-1 or AP-A and 
associated

[[Page 826]]

forms are approved under OMB control number 0694-0135.
    (4) In Sec. 150.20, NRC Form 241 is approved under control number 
3150-0013.

[49 FR 19629, May 9, 1984, as amended at 62 FR 52190, Oct. 6, 1997; 73 
FR 32464, June 9, 2008; 73 FR 78615, Dec. 23, 2008; 74 FR 1872, Jan. 14, 
2009]

                     Exemptions in Agreement States



Sec. 150.10  Persons exempt.

    Except as provided in Sec. Sec. 150.15, 150.16, 150.17, 150.17a, 
and 150.19, any person in an Agreement State who manufactures, produces, 
receives, possesses, uses, or transfers byproduct material, source 
material, or special nuclear material in quantities not sufficient to 
form a critical mass is exempt from the requirements for a license 
contained in Chapters 6, 7, and 8 of the Act, regulations of the 
Commission imposing licensing requirements upon persons who manufacture, 
produce, receive, possess, use, or transfer such materials, and from 
regulations of the Commission applicable to licensees. The exemptions in 
this section do not apply to agencies of the Federal government as 
defined in Sec. 150.3.

[37 FR 9208, May 6, 1972, as amended at 45 FR 50718, July 31, 1980; 75 
FR 73946, Nov. 30, 2010]



Sec. 150.11  Critical mass.

    (a) For the purposes of this part, special nuclear material in 
quantities not sufficient to form a critical mass means uranium enriched 
in the isotope U-235 in quantities not exceeding 350 grams of contained 
U-235; uranium-233 in quantities not exceeding 200 grams; plutonium in 
quantities not exceeding 200 grams; or any combination of them in 
accordance with the following formula: For each kind of special nuclear 
material, determine the ratio between the quantity of that special 
nuclear material and the quantity specified above for the same kind of 
special nuclear material. The sum of such ratios for all kinds of 
special nuclear materials in combination shall not exceed unity. For 
example, the following quantities in combination would not exceed the 
limitation and are within the formula, as follows:

(175 (grams contained U-235 / 350) + (50 grams U-233) / 200) + (50 grams 
Pu / 200) = 1

    (b) To determine whether the exemption granted in Sec. 150.10 
applies to the receipt, possession or use of special nuclear material at 
any particular plant or other authorized location of use, a person shall 
include in the quantity computed according to paragraph (a) of this 
section the total quantity of special nuclear material which he is 
authorized to receive, possess or use at the plant or other location of 
use at any one time.

[27 FR 1352, Feb. 14, 1962, as amended at 30 FR 12069, Sept. 22, 1965]

      Continued Commission Regulatory Authority in Agreement States



Sec. 150.14  Commission regulatory authority for physical protection.

    Persons in Agreement States possessing, using or transporting 
special nuclear material of low strategic significance in quantities 
greater than 15 grams of plutonium or uranium-233 or uranium-235 
(enriched to 20 percent or more in the U-235 isotope) or any combination 
greater than 15 grams when computed by the equation grams = grams 
uranium-235 + grams plutonium + grams uranium-233 shall meet the 
physical protection requirements of Sec. 73.67 of 10 CFR part 73.

[44 FR 43285, July 24, 1979, as amended at 44 FR 68199, Nov. 28, 1979]



Sec. 150.15  Persons not exempt.

    (a) Persons in agreement States are not exempt from the Commission's 
licensing and regulatory requirements with respect to the following 
activities:
    (1) The construction and operation of any production or utilization 
facility. As used in this subparagraph, operation of a facility 
includes, but is not limited to (i) the storage and handling of 
radioactive wastes at the facility site by the person licensed to 
operate the facility, and (ii) the discharge of radioactive effluents 
from the facility site.
    (2) The export from or import into the United States of byproduct, 
source, or special nuclear material, or of any production or utilization 
facility.

[[Page 827]]

    (3) The disposal into the ocean or sea of byproduct, source, or 
special nuclear waste materials, as defined in regulations or orders of 
the Commission. For purposes of this part, ocean or sea means any part 
of the territorial waters of the United States and any part of the 
international waters.
    (4) The transfer, storage or disposal of radioactive waste material 
resulting from the separation in a production facility of special 
nuclear material from irradiated nuclear reactor fuel. This subparagraph 
does not apply to the transfer, storage or disposal of contaminated 
equipment.
    (5) The disposal of such other byproduct, source, or special nuclear 
material as the Commission determines by regulation or order should, 
because of the hazards or potential hazards thereof, not be so disposed 
of without a license from the Commission.
    (6) The transfer of possession or control by the manufacturer, 
processor, or producer of any equipment, device, commodity, or other 
product containing source material or byproduct material whose 
subsequent possession, use, transfer, and disposal by all other persons 
are exempted from licensing and regulatory requirements of the 
Commission under Parts 30 and 40 of this chapter.
    (7) The storage of:
    (i) Spent fuel in an independent spent fuel storage installation 
(ISFSI) licensed under part 72 of this chapter,
    (ii) Spent fuel and high-level radioactive waste in a monitored 
retrievable storage installation (MRS) licensed under part 72 of this 
chapter, or
    (iii) Greater than Class C waste, as defined in part 72 of this 
chapter, in an ISFSI or an MRS licensed under part 72 of this chapter; 
the GTCC waste must originate in, or be used by, a facility licensed 
under part 50 of this chapter.
    (8) Greater than Class C waste, as defined in part 72 of this 
chapter, that originates in, or is used by, a facility licensed under 
part 50 of this chapter and is licensed under part 30 and/or part 70 of 
this chapter.
    (b) Notwithstanding any exemptions provided in this part, the 
Commission may from time to time by rule, regulation, or order, require 
that the manufacturer, processor, or producer of any equipment, device, 
commodity, or other product containing source, byproduct, or special 
nuclear material shall not transfer possession or control of such 
product except pursuant to a license or an exemption from licensing 
issued by the Commission.

[27 FR 1352, Feb. 14, 1962, as amended at 34 FR 7369, May 7, 1969; 53 FR 
31683, Aug. 19, 1988; 66 FR 51843, Oct. 11, 2001; 73 FR 63582, Oct. 24, 
2008]



Sec. 150.15a  Continued Commission authority pertaining to byproduct
material.

    (a) Prior to the termination of any Agreement State license for 
byproduct material as defined in Sec. 150.3(c)(2) of this part, or for 
any activity that results in the production of such material, the 
Commission shall have made a determination that all applicable standards 
and requirements pertaining to such material have been met.
    (b) After November 8, 1981, the Commission reserves the authority to 
establish minimum standards regarding reclamation, long term 
surveillance (i.e., continued site observation, monitoring and, where 
necessary, maintenance), and ownership of byproduct material as defined 
in Sec. 150.3(c)(2) of this part and of land used as a disposal site 
for such material. Such reserved authority includes:
    (1) Authority to establish such terms and conditions as the 
Commission determines necessary to assure that, prior to termination of 
any license for byproduct material as defined in Sec. 150.3(c)(2) of 
this part, or for any activity that results in the production of such 
material, the licensee shall comply with decontamination, 
decommissioning, and reclamation standards prescribed by the Commission; 
and with ownership requirements for such materials and its disposal 
site;
    (2) The authority to require that prior to termination of any 
license for byproduct material as defined in Sec. 150.3(c)(2) of this 
part, or for any activity that results in the production of such 
material, that title to such byproduct material and its disposal site be 
transferred to the United States or the State in which such material and 
land is located, at the option of the

[[Page 828]]

State (provided such option is exercised prior to termination of the 
license);
    (3) The authority to permit use of the surface or subsurface 
estates, or both, of the land transferred to the United States or a 
State pursuant to paragraph (b)(2) of this section in a manner 
consistent with the provisions of the Uranium Mill Tailings Radiation 
Control Act of 1978, provided that the Commission determines that such 
use would not endanger the public health, safety, welfare, or the 
environment;
    (4) The authority to require, in the case of a license for any 
activity that produces such byproduct material (which license was in 
effect on November 8, 1981) transfer of land and material pursuant to 
paragraph (b)(2), of this section, taking into consideration the status 
of such material and land and interests therein, and the ability of the 
licensee to transfer title and custody thereof to the United States or a 
State.
    (5) The authority to require the Secretary of the Department of 
Energy, other Federal agency, or State, whichever has custody of such 
property and materials, to undertake such monitoring, maintenance and 
emergency measures as are necessary to protect the public health and 
safety and other actions at the Commission deems necessary to comply 
with the standards promulgated pursuant to the Uranium Mill Tailings 
Radiation Control Act of 1978; and
    (6) The authority to enter into arrangements as may be appropriate 
to assure Federal long term surveillance (i.e., continued site 
observation, monitoring, and where necessary, maintenance) of such 
disposal sites on land held in trust by the United States for any Indian 
Tribe or land owned by an Indian Tribe and subject to a restriction 
against alienation imposed by the United States.

[45 FR 65536, Oct. 3, 1980, as amended at 80 FR 74982, Dec. 1, 2015]

           Continued Commission Authority in Agreement States



Sec. 150.16  Submission to Commission of nuclear material transaction
reports.

    (a)(1) Each person who transfers or receives special nuclear 
material in a quantity of one gram or more of contained uranium-235, 
uranium-233, or plutonium under an Agreement State license shall 
complete and submit in computer-readable format Nuclear Material 
Transaction Reports as specified in the instructions in NUREG/BR-0006 
and NMMSS Report D-24, ``Personal Computer Data Input for NRC 
Licensees.'' In addition, each person who adjusts the inventory in any 
manner, other than for transfers and receipts, shall submit in computer-
readable format Nuclear Material Transaction Reports as specified in the 
instructions in NUREG/BR-0006 and NMMSS Report D-24, ``Personal Computer 
Data Input for NRC Licensees.'' Each licensee who receives special 
nuclear material in a quantity of one gram or more of contained uranium-
235, uranium-233, or plutonium from a foreign source, or who ships 
special nuclear material in a quantity of one gram or more of contained 
uranium-235, uranium-233, or plutonium to a foreign source, shall submit 
the licensee portion of this information as specified in the 
instructions in this part. The applicable foreign facility portion of 
the form must be completed and submitted for imports. The foreign 
facility portion of the form must be completed for exports only if a 
significant shipper-receiver difference as described in Sec. Sec. 
74.31, 74.43, or 74.59 of this part, as applicable, is identified. Each 
person who transfers the material shall submit a Nuclear Material 
Transaction Report in computer-readable format as specified in the 
instructions no later than the close of business the next working day. 
Each person who receives special nuclear material shall submit a Nuclear 
Material Transaction Report in the computer-readable format as specified 
in the instructions within ten (10) days after the special nuclear 
material is received. Copies of these instructions may be obtained 
either by writing to

[[Page 829]]

the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety, 
Safeguards, and Environmental Review, Washington, DC 20555-0001, or by 
e-mail to [email protected]. These prescribed computer-readable 
formats replace the DOE/NRC Form 741 which have been previously 
submitted in paper form.
    (2) Except as specified in Sec. Sec. 150.17(d) and 150.17a, each 
person who, under an Agreement State specific license transfers, 
receives, or adjusts the inventory in any manner, of uranium or thorium 
source material with foreign obligations by one kilogram or more; 
imports or exports one kilogram or more of uranium or thorium source 
material; or uses one kilogram or more of any uranium or thorium source 
material in enrichment services, downblending uranium that has an 
initial enrichment of the U\235\ isotope of 10 percent or more, or in 
the fabrication of mixed-oxide fuels, shall complete and submit in 
computer-readable format Nuclear Material Transaction Reports as 
specified in the instructions in NUREG/BR-0006 and NMMSS Report D-24, 
``Personal Computer Data Input for NRC Licensees.'' Each person who, 
under an Agreement State specific license exports one kilogram or more 
of uranium or thorium source material shall complete in the format 
listed above the licensee's portion of the Nuclear Material Transaction 
Report unless there is indication of loss, theft, or diversion as 
discussed in Sec. 40.64(c)(1) of this chapter is identified, in which 
case both the licensee's and the foreign facility's information shall be 
reported. For imports, the shipper's portion of the form must also be 
completed. Copies of the instructions may be obtained either by writing 
to the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety 
and Safeguards, Washington, DC 20555-0001, or by e-mail to 
[email protected]. Each licensee who transfers the material shall 
submit a Nuclear Material Transaction Report in computer-readable format 
as specified in the instructions no later than the close of business the 
next working day. Each licensee who receives the material shall submit a 
Nuclear Material Transaction Report in computer-readable format in 
accordance with instructions within ten (10) days after the material is 
received. The Commission's copy of the report must be submitted to the 
address specified in the instructions. These prescribed computer-
readable forms replace the DOE/NRC Form 741 which have been previously 
submitted in paper form.
    (b)(1) Each person who, pursuant to an Agreement State License, 
possesses 1 gram or more of contained uranium-235, uranium-233, or 
plutonium shall report immediately to the Regional Administrator of the 
appropriate NRC Regional Office listed in appendix A of part 73 of this 
chapter, by telephone, any theft or other unlawful diversion of special 
nuclear material which the licensee is licensed to possess or any 
incident in which an attempt has been made, or is believed to have been 
made, to commit a theft or unlawful diversion of special nuclear 
material.
    (2) Within 15 days, the licensee shall follow the initial report 
with a written report that sets forth the details of the incident. The 
report must be sent by an appropriate method listed in Sec. 150.4 to 
the Director, Office of Nuclear Material Safety and Safeguards, with a 
copy to the appropriate NRC Regional Office, shown in appendix A to part 
73 of this chapter.
    (3) Subsequent to the submission of the written report required by 
this paragraph, each licensee shall promptly inform the Regional 
Administrator of the appropriate NRC Regional Office by means of a 
written report of any substantive additional information which becomes 
available to the licensee concerning an attempted or apparent theft or 
unlawful diversion of special nuclear material.

[39 FR 39559, Nov. 8, 1974, as amended at 41 FR 16447, Apr. 19, 1976; 52 
FR 31613, Aug. 21, 1987; 59 FR 35622, July 13, 1994; 68 FR 58825, Oct. 
10, 2003; 73 FR 5727, Jan. 31, 2008; 73 FR 32464, June 9, 2008; 79 FR 
75742, Dec. 19, 2014]



Sec. 150.17  Submission to Commission of nuclear material status
reports.

    (a) Except as specified in paragraph (d) of this section and Sec. 
150.17a, each person possessing, or who had possessed in the previous 
reporting period, at any one time and location, under an Agreement State 
license, special nuclear material in a quantity totaling

[[Page 830]]

one gram or more of contained uranium-235, uranium-233, or plutonium, 
shall complete and submit, in computer-readable format Material Balance 
Reports concerning special nuclear material that the licensee has 
received, produced, possessed, transferred, consumed, disposed of, or 
lost. This prescribed computer-readable report replaces the DOE/NRC Form 
742 which has been previously submitted in paper form. The Physical 
Inventory Listing Report must be submitted with each Material Balance 
Report. This prescribed computer-readable report replaces the DOE/NRC 
Form 742C which has been previously submitted in paper form. Each 
licensee shall prepare and submit the reports described in this 
paragraph as specified in the instructions in NUREG/BR-0007 and NMMSS 
Report D-24 ``Personal Computer Data Input for NRC Licensees.'' Copies 
of these instructions may be obtained from the U.S. Nuclear Regulatory 
Commission, Division of Fuel Cycle Safety, Safeguards, and Environmental 
Review, Washington, DC 20555-0001, or by e-mail to [email protected]. 
Each person subject to this requirement shall submit a report no later 
than March 31 of each year. The Commission may, when good cause is 
shown, permit a licensee to submit Material Balance Reports and Physical 
Inventory Listing Reports at other times. Each licensee required to 
report material balance, and inventory information, as described in this 
part, shall resolve any discrepancies identified during the report 
review and reconciliation process within 30 calendar days of 
notification of a discrepancy identified by NRC.
    (b) Except as specified in paragraph (d) of this section and Sec. 
150.17a, each person possessing, or who had possessed in the previous 
reporting period, at any one time and location, under an Agreement State 
license:
    (1) One kilogram or more of uranium or thorium source material with 
foreign obligations, shall document holdings as of September 30 of each 
year and submit to the Commission within 30 days. Alternatively, these 
reports may be submitted with the licensee's material status reports on 
special nuclear material filed under part 72 or 74 of this chapter. This 
statement must be submitted to the address specified in the reporting 
instructions in NUREG/BR-0007, and include the Reporting Identification 
Symbol (RIS) assigned by the Commission.
    (2) One kilogram or more of uranium or thorium source material in 
the operation of enrichment services, downblending uranium that has an 
initial enrichment of the U\235\ isotope of 10 percent or more, or in 
the fabrication of mixed-oxide fuels shall complete and submit, in 
computer-readable format, Material Balance and Physical Inventory 
Listing Reports concerning source material that the licensee has 
received, produced, possessed, transferred, consumed, disposed, or lost. 
Reports must be submitted for each Reporting Identification Symbol (RIS) 
account including all holding accounts. Each licensee shall prepare and 
submit these reports as specified in the instructions in NUREG/BR-0007 
and NMMSS Report D-24, ``Personal Computer Data Input for NRC 
Licensees.'' These reports must document holdings as of September 30 of 
each year and submitted to the Commission within 30 days. Alternatively, 
these reports may be submitted with the licensee's material status 
reports on special nuclear material filed under part 72 or 74 of this 
chapter. Copies of the reporting instructions may be obtained by writing 
to the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety 
and Safeguards, Washington, DC 20555-0001, or by e-mail to 
[email protected]. Each licensee required to report material balance, 
and inventory information, as described in this part, shall resolve any 
discrepancies identified during the report review and reconciliation 
process within 30 calendar days of the notification of a discrepancy 
identified by the NRC.
    (c)(1) Except as specified in paragraph (d) of this section, each 
licensee who is authorized to possess uranium or thorium pursuant to a 
specific license shall notify the NRC Headquarters Operations Center by 
telephone, at the numbers listed in appendix A to part 73 of this 
chapter, of any incident in which an attempt has been made or is 
believed to have been made

[[Page 831]]

to commit a theft or unlawful diversion of more than 6.8 kilograms (kg) 
[15 pounds] of such material at any one time or more than 68 kg [150 
pounds] of such material in any one calendar year.
    (2) The licensee shall notify the NRC as soon as possible, but 
within 4 hours, of discovery of any incident in which an attempt has 
been made or is believed to have been made to commit a theft or unlawful 
diversion of such material.
    (3) The initial notification shall be followed within a period of 
sixty (60) days by a written followup notification submitted in 
accordance with Sec. 150.4. A copy of the written followup notification 
shall also be sent to the appropriate NRC Regional Office as shown in 
appendix A to part 73 of this chapter and to Director, Division of 
Security Policy, Office of Nuclear Security and Incident Response, U.S. 
Nuclear Regulatory Commission.
    (4) Subsequent to the submission of the written followup 
notification required by this paragraph, the licensee shall promptly 
update the written followup notification, in accordance with this 
paragraph, with any substantive additional information, which becomes 
available to the licensee, concerning an attempted or apparent theft or 
unlawful diversion of source material.
    (d) The reports described in paragraphs (a), (b), and (c) of this 
section are not required for:
    (1) Processed ores containing less than five (5) percent of uranium 
or thorium, or any combination of uranium and thorium, by dry weight;
    (2) Thorium contained in magnesium-thorium and tungsten-thorium 
alloys, if the thorium content in the alloys does not exceed 4 percent 
by weight;
    (3) Chemical catalysts containing uranium depleted in the U-235 
isotope to 0.4 percent or less, if the uranium content of the catalyst 
does not exceed 15 percent by weight; or
    (4) Any source material contained in non-nuclear end use devices or 
components, including but not limited to permanently installed 
shielding, teletherapy, radiography, X-ray, accelerator devices, or 
munitions.

[35 FR 12196, July 30, 1970, as amended at 36 FR 10938, June 5, 1971; 41 
FR 16448, Apr. 19, 1976; 49 FR 24708, June 15, 1984; 51 FR 9767, Mar. 
21, 1986; 52 FR 31613, Aug. 21, 1987; 59 FR 35622, July 13, 1994; 60 FR 
24553, May 9, 1995; 68 FR 10365, Mar. 5, 2003; 68 FR 58825, Oct. 10, 
2003; 73 FR 32465, June 9, 2008; 74 FR 62686, Dec. 1, 2009; 75 FR 73946, 
Nov. 30, 2010; 79 FR 75742, Dec. 19, 2014]



Sec. 150.17a  Compliance with requirements of US/IAEA Safeguards 
Agreement.

    (a) For purposes of this section, the terms facility, location, and 
Eligible Facilities List have the meanings set forth in Sec. 75.4 of 
this chapter.
    (b) Each person who, under an Agreement State license, is authorized 
to possess byproduct, source, or special nuclear material is subject to 
the provisions of Part 75 of this chapter and shall comply with its 
applicable provisions. However, regarding these persons, the Commission 
will issue orders under section 274m of the Act instead of making 
license amendments; and, to the extent Part 75 of this chapter refers to 
license amendments and license conditions, these references shall be 
deemed, for purposes of this paragraph, to refer to orders under section 
274m of the Act.
    (c)(1) In response to a written request by the Commission, each 
applicant for an Agreement State license or certificate, and each 
recipient of an Agreement State license or certificate shall submit 
facility information, as described in Sec. 75.10 of this chapter, on 
Form N-71 and associated forms, and site information on DOC/NRC Form AP-
A and associated forms;
    (2) As required by the Additional Protocol, shall submit location 
information described in Sec. 75.11 of this chapter on DOC/NRC Form AP-
1 and associated forms; and
    (3) Shall permit verification thereof by the International Atomic 
Energy Agency (IAEA); and shall take other action as may be necessary to 
implement the US/IAEA Safeguards Agreement, as described in Part 75 of 
this chapter.
    (d) In response to a written request by the Commission, each 
applicant for

[[Page 832]]

an Agreement State license or certificate, and each recipient of an 
Agreement State license or certificate shall submit facility 
information, as described in Sec. 75.10 of this chapter, on Form N-71 
and associated forms, and site information on DOC/NRC Form AP-A and 
associated forms; shall submit location information described in Sec. 
75.11 of this chapter on DOC/NRC Form AP-1 or AP-A and associated forms; 
shall permit verification thereof by the International Atomic Energy 
Agency (IAEA); and shall take other action as may be necessary to 
implement the US/IAEA Safeguards Agreement, as described in part 75 of 
this chapter.

[73 FR 78615, Dec. 23, 2008]



Sec. 150.19  Submission to Commission of tritium reports.

    (a)-(b) [Reserved]
    (c) Except as specified in paragraph (d) of this section, each 
person who, pursuant to an Agreement State license, is authorized to 
possess tritium shall report promptly to the appropriate NRC Regional 
Office as shown in appendix D of part 20 of this chapter by telephone 
and telegraph, mailgram, or facsimile any incident in which an attempt 
has been made or is believed to have been made to commit a theft or 
unlawful diversion of more than 10 curies of such material at any one 
time or 100 curies of such material in any one calendar year. The 
initial report must be followed within a period of fifteen days by a 
written report that sets forth the details of the incident and its 
consequences. The report must be submitted to the Director, Office of 
Nuclear material Safety and Safeguards, using an appropriate method 
listed in Sec. 150.4, with a copy to the appropriate NRC Regional 
Office as shown in appendix A to part 73 of this chapter. Subsequent to 
the submission of the written report required by this paragraph, each 
person subject to the provisions of this paragraph shall promptly inform 
the appropriate NRC Regional Office by means of a written report of any 
substantive additional information, which becomes available to such 
person, concerning an attempted or apparent theft or unlawful diversion 
of tritium.
    (d) The reports described in this section are not required for 
tritium possessed pursuant to a general license issued pursuant to 
regulations of an Agreement State equivalent to part 31 of this chapter 
or for tritium in spent fuel.

[37 FR 9208, May 6, 1972, as amended at 41 FR 16448, Apr. 19, 1976; 46 
FR 55085, Nov. 6, 1981; 49 FR 24708, June 15, 1984; 52 FR 31613, Aug. 
21, 1987; 68 FR 58825, Oct. 10, 2003; 73 FR 5727, Jan. 31, 2008; 79 FR 
75742, Dec. 19, 2014]

                               Reciprocity



Sec. 150.20  Recognition of Agreement State licenses.

    (a)(1) Provided that the provisions of paragraph (b) of this section 
have been met, any person who holds a specific license from an Agreement 
State, where the licensee maintains an office for directing the licensed 
activity and retaining radiation safety records, is granted a general 
license to conduct the same activity in--
    (i) Non-Agreement States;
    (ii) Areas of Exclusive Federal jurisdiction within Agreement 
States; and
    (iii) Offshore waters.
    (2) The provisions of paragraph (a)(1) of this section do not apply 
if the specific Agreement State license limits the authorized activity 
to a specific installation or location.
    (b) Notwithstanding any provision to the contrary in any specific 
license issued by an Agreement State to a person engaging in activities 
in a non-Agreement State, in an area of exclusive Federal jurisdiction 
within an Agreement State, or in offshore waters under the general 
licenses provided in this section, the general licenses provided in this 
section are subject to all the provisions of the Act, now or hereafter 
in effect, and to all applicable rules, regulations, and orders of the 
Commission including the provisions of Sec. Sec. 30.7(a) through (f), 
30.9, 30.10, 30.34, 30.41, and 30.51 through 30.63 of this chapter; 
Sec. Sec. 40.7(a) through (f), 40.9, 40.10, 40.41, 40.51, 40.61 through 
40.63, 40.71, and 40.81 of this chapter; Sec. Sec. 70.7(a) through (f), 
70.9, 70.10, 70.32, 70.42, 70.52, 70.55, 70.56, 70.60 through 70.62 of 
this chapter; Sec. Sec. 74.11, 74.15, and 74.19 of this chapter; and to 
the provisions of 10 CFR parts 19, 20 and 71 and subparts C

[[Page 833]]

through H of part 34, Sec. Sec. 39.15 and 39.31 through 39.77 of this 
chapter. In addition, any person engaging in activities in non-Agreement 
States, in areas of exclusive Federal jurisdiction within Agreement 
States, or in offshore waters under the general licenses provided in 
this section:
    (1) Shall, at least 3 days before engaging in each activity for the 
first time in a calendar year, file a submittal containing an NRC Form 
241, ``Report of Proposed Activities in Non-Agreement States,'' a copy 
of its Agreement State specific license, and the appropriate fee as 
prescribed in Sec. 170.31 of this chapter with the Regional 
Administrator of the U.S. Nuclear Regulatory Commission Regional Office 
listed on the NRC Form 241 and in appendix D to part 20 of this chapter 
for the Region in which the Agreement State that issued the license is 
located. If a submittal cannot be filed 3 days before engaging in 
activities under reciprocity, because of an emergency or other reason, 
the Regional Administrator may waive the 3-day time requirement provided 
the licensee:
    (i) Informs the Region by telephone, facsimile, an NRC Form 241, or 
a letter of initial activities or revisions to the information submitted 
on the initial NRC Form 241;
    (ii) Receives oral or written authorization for the activity from 
the region; and
    (iii) Within 3 days after the notification, files an NRC Form 241, a 
copy of the Agreement State license, and the fee payment.
    (2) Shall file an amended NRC Form 241 or letter with the Regional 
Administrator to request approval for changes in work locations, 
radioactive material, or work activities different from the information 
contained on the initial NRC Form 241.
    (3) Shall not, in any non-Agreement State, in an area of exclusive 
Federal jurisdiction within an Agreement State, or in offshore waters, 
transfer or dispose of radioactive material possessed or used under the 
general licenses provided in this section, except by transfer to a 
person who is specifically licensed by the Commission to receive this 
material.
    (4) Shall not, under the general license concerning activities in 
non-Agreement States or in areas of exclusive Federal jurisdiction 
within Agreement States, possess or use radioactive materials, or engage 
in the activities authorized in paragraph (a) of this section, for more 
than 180 days in any calendar year, except that the general license in 
paragraph (a) of this section concerning activities in offshore waters 
authorizes that person to possess or use radioactive materials, or 
engage in the activities authorized, for an unlimited period of time.
    (5) Shall comply with all terms and conditions of the specific 
license issued by an Agreement State except such terms or conditions as 
are contrary to the requirements of this section.

[35 FR 7725, May 20, 1970]

    Editorial Note: For Federal Register citations affecting Sec. 
150.20, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 150.21  Transportation of special nuclear material by aircraft.

    Except as specifically approved by the Commission no shipment of 
special nuclear material in excess of 20 grams or 20 curies whichever is 
less of plutonium or uranium-233 shall be made by a licensee of an 
Agreement State in passenger aircraft.

[38 FR 3039, Feb. 1, 1973]

                               Enforcement



Sec. 150.30  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or
    (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;

[[Page 834]]

    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section;
    (iv) Any term, condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

[57 FR 55081, Nov. 24, 1992]



Sec. 150.31  Requirements for Agreement State regulation of byproduct
material.

    (a) Prior to November 8, 1981, in the licensing and regulation of 
byproduct material, as defined in Sec. 150.3(c)(2) of this part, or of 
any activity which results in the production of such byproduct material, 
an Agreement State shall require compliance with the requirements in 
appendix A of 10 CFR part 40 of this chapter to the maximum extent 
practicable.
    (b) After November 8, 1981, in the licensing and regulation of 
byproduct material, as defined in Sec. 150.3(c)(2) of this part, or of 
any activity which results in the production of such byproduct material, 
an Agreement State shall require:
    (1) Compliance with requirements in appendix A of 10 CFR part 40 of 
this chapter established by the Commission pertaining to ownership of 
such byproduct material and disposal sites for such material; and
    (2) Compliance with standards which shall be adopted by the 
Agreement State for the protection of the public health, safety, and the 
environment from hazards associated with such material which are 
equivalent, to the extent practicable, or more stringent than, standards 
in appendix A of 10 CFR part 40 of this chapter adopted and enforced by 
the Commission for the same purposes, including requirements and 
standards subsequently promulgated by the Commission and the 
Administrator of the Environmental Protection Agency pursuant to the 
Uranium Mill Tailing Radiation Control Act of 1978; and
    (3) Compliance with procedures which:
    (i) In the case of licenses, under State law include:
    (A) An opportunity, after public notice, for written comments and a 
public hearing, with a transcript;
    (B) An opportunity for cross examination; and
    (C) A written determination by the appropriate State official which 
is based upon findings included in such determination and upon the 
evidence presented during the public comment period and which is subject 
to judicial review;
    (ii) In the case of rulemaking, provide an opportunity for public 
participation through written comments or a public hearing and provide 
for judicial review of the rule;
    (iii) Require for each licensing action which has a significant 
impact on the human environment a written analysis by the appropriate 
State agency (which shall be available to the public before the 
commencement of any such proceedings) of the impact of such licensing 
action, including any activities conducted pursuant thereto, on the 
environment. Such analysis shall include:
    (A) An assessment of the radiological and nonradiological impacts to 
the public health of the activities to be conducted pursuant to such 
licenses;
    (B) An assessment of any impact on any waterway and groundwater 
resulting from such activities;
    (C) Consideration of alternatives, including alternative sites and 
engineering methods, to the activities to be conducted pursuant to such 
license; and
    (D) Consideration of the long term impacts, including 
decommissioning, decontamination, and reclamation impacts associated 
with activities to be conducted pursuant to such license, including the 
management of any byproduct material, as defined in Sec. 150.3(c)(2) of 
this part; and
    (iv) Prohibit commencement of construction with respect to such 
material prior to complying with the provisions of paragraph (b)(3)(iii) 
of this section. As used in this paragraph:
    (A) The term commencement of construction means taking any action 
defined as ``construction'' or any other

[[Page 835]]

activity at the site of a facility subject to the regulations in this 
part that has a reasonable nexus to radiological health and safety.
    (B) The term construction means the installation of foundations, or 
in-place assembly, erection, fabrication, or testing for any structure, 
system, or component of a facility or activity subject to the 
regulations in this part that have a reasonable nexus to radiological 
safety or security. The term ``construction'' does not include:
    (1) Changes for temporary use of the land for public recreational 
purposes;
    (2) Site exploration, including necessary borings to determine 
foundation conditions or other preconstruction monitoring to establish 
background information related to the suitability of the site, the 
environmental impacts of construction or operation, or the protection of 
environmental values;
    (3) Preparation of the site for construction of the facility, 
including clearing of the site, grading, installation of drainage, 
erosion and other environmental mitigation measures, and construction of 
temporary roads and borrow areas;
    (4) Erection of fences and other access control measures that are 
not related to the safe use of or security of radiological materials 
subject to this part;
    (5) Excavation;
    (6) Erection of support buildings (e.g., construction equipment 
storage sheds, warehouse and shop facilities, utilities, concrete mixing 
plants, docking and unloading facilities, and office buildings) for use 
in connection with the construction of the facility;
    (7) Building of service facilities (e.g., paved roads, parking lots, 
railroad spurs, exterior utility and lighting systems, potable water 
systems, sanitary sewerage treatment facilities, and transmission 
lines);
    (8) Procurement or fabrication of components or portions of the 
proposed facility occurring at other than the final, in-place location 
at the facility; or
    (9) Taking any other action which has no reasonable nexus to 
radiological health and safety.
    (c) No Agreement State shall be required under paragraph (b) to 
conduct proceedings concerning any license or regulation which would 
duplicate proceedings conducted by the Commission.
    (d) In adopting requirements pursuant to paragraph (b)(2) of this 
section, the State may adopt alternatives (including, where appropriate, 
site-specific alternatives) to the requirements adopted and enforced by 
the Commission for the same purpose if, after notice and opportunity for 
public hearing, the Commission determines that the alternatives will 
achieve a level of stabilization and containment of the sites concerned, 
and a level of protection for public health, safety and the environment 
from radiological and nonradiological hazards associated with the sites, 
which is equivalent to, to the extent practicable, or more stringent 
than the level which would be achieved by standards and requirements 
adopted and enforced by the Commission for the same purpose and any 
final standards promulgated by the Administrator of the Environmental 
Protection Agency in accordance with section 275. Alternative State 
requirements may take into account local or regional conditions, 
including geology, topography, hydrology and meteorology.

[45 FR 65537, Oct. 3, 1980; 50 FR 41866, Oct. 16, 1985, as amended at 76 
FR 56966, Sept. 15, 2011]



Sec. 150.32  Funds for reclamation or maintenance of byproduct
material.

    (a) The total amount of funds an Agreement State collects, pursuant 
to a license for byproduct material as defined in Sec. 150.3(c)(2) of 
this part or for any activity that results in the production of such 
material, for reclamation or long term maintenance and monitoring of 
such material, shall after November 8, 1981, be transferred to the 
United States if title and custody of such material and its disposal 
site is transferred to the United States upon termination of such 
license. Such funds include, but are not limited to, sums collected for 
long term surveillance (i.e., continued site observation, monitoring 
and, where necessary, maintenance). Such funds do not however, include 
monies held as surety where no

[[Page 836]]

default has occurred and the reclamation or other bonded activity has 
been performed.
    (b) If an Agreement State requires such payments for reclamation or 
long term surveillance (i.e., continued site observation, monitoring 
and, where necessary, maintenance), the payments must, after November 8, 
1981, be sufficient to ensure compliance with those standards 
established by the Commission pertaining to bonds, sureties, and 
financial arrangements to ensure adequate reclamation and long term 
management of such byproduct material and its disposal site.

[45 FR 65537, Oct. 3, 1980; 48 FR 40882, Sept. 12, 1983]



Sec. 150.33  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 150 are issued under one or more of sections 
161b, 161i, or 161o, except for sections listed in paragraph (b) of this 
section.
    (b) The regulations in part 150 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec. 150.1, 150.2, 150.3, 150.4, 150.5, 150.7, 150.8, 150.10, 
150.11, 150.15, 150.15a, 150.30, 150.31, 150.32, and 150.33.

[57 FR 55081, Nov. 24, 1992]



PART 160_TRESPASSING ON COMMISSION PROPERTY--Table of Contents



Sec.
160.1 Purpose.
160.2 Scope.
160.3 Trespass.
160.4 Unauthorized introduction of weapons or dangerous materials.
160.5 Violations and penalties.
160.6 Posting.
160.7 Effective date of prohibition on designated locations.
160.8 Applicability of other laws.

    Authority: Atomic Energy Act of 1954, secs. 161, 223, 229, 234 (42 
U.S.C. 2201, 2273, 2278a, 2282); Energy Reorganization Act of 1974, sec. 
201 (42 U.S.C. 5841).

    Source: 28 FR 8400, Aug. 16, 1963, unless otherwise noted.



Sec. 160.1  Purpose.

    The regulations in this part are issued for the protection and 
security of facilities, installations and real property subject to the 
proprietory jurisdiction or administration, or in the custody of, the 
Nuclear Regulatory Commission.

[28 FR 8400, Aug. 16, 1963, as amended at 40 FR 8794, Mar. 3, 1975]



Sec. 160.2  Scope.

    The regulations in this part apply to all facilities, installations, 
and real property subject to the jurisdiction or administration of the 
Nuclear Regulatory Commission or in its custody which have been posted 
with a notice of the prohibitions and penalties set forth in this part.

[40 FR 8794, Mar. 3, 1975]



Sec. 160.3  Trespass.

    Unauthorized entry upon any facility, installation or real property 
subject to this part is prohibited.



Sec. 160.4  Unauthorized introduction of weapons or dangerous
materials.

    Unauthorized carrying, transporting, or otherwise introducing or 
causing to be introduced any dangerous weapon, explosive, or other 
dangerous instrument or material likely to produce substantial injury or 
damage to persons or property, into or upon any facility, installation 
or real property subject to this part, is prohibited.



Sec. 160.5  Violations and penalties.

    (a) Whoever willfully violates either Sec. Sec. 160.3 or 160.4 
shall, upon conviction, be punishable by a fine of not more than $1,000.
    (b) Whoever willfully violates either Sec. Sec. 160.3 or 160.4 with 
respect to any facility, installation or real property enclosed by a 
fence, wall, floor, roof, or other structural barrier shall be guilty of 
a misdemeanor and, upon conviction, shall be punished by a fine of not 
to exceed $5,000 or imprisonment for not more than one year, or both.



Sec. 160.6  Posting.

    Notices stating the pertinent prohibitions of Sec. Sec. 160.3 and 
160.4 and penalties of Sec. 160.5 will be conspicuously posted

[[Page 837]]

at all entrances of each designated facility, installation or parcel of 
real property and at such intervals along the perimeter as will provide 
reasonable assurance of notice to persons about to enter.



Sec. 160.7  Effective date of prohibition on designated locations.

    The prohibitions in Sec. Sec. 160.3 and 160.4 shall take effect as 
to any facility, installation or real property on publication in the 
Federal Register of the notice designating the facility, installation or 
real property and posting in accordance with Sec. 160.6.



Sec. 160.8  Applicability of other laws.

    Nothing in this part shall be construed to affect the applicability 
of the provisions of State or other Federal laws.



PART 170_FEES FOR FACILITIES, MATERIALS, IMPORT AND EXPORT LICENSES,
AND OTHER REGULATORY SERVICES UNDER THE ATOMIC ENERGY ACT OF 1954, 
AS AMENDED--Table of Contents



                           General Provisions

Sec.
170.1 Purpose.
170.2 Scope.
170.3 Definitions.
170.4 Interpretations.
170.5 Communications.
170.8 Information collection requirements: OMB approval.
170.11 Exemptions.
170.12 Payment of fees.
170.20 Average cost per professional staff-hour.

                            Schedule of Fees

170.21 Schedule of fees for production and utilization facilities, 
          review of standard referenced design approvals, special 
          projects, inspections and import and export licenses.
170.31 Schedule of fees for materials licenses and other regulatory 
          services, including inspections, and import and export 
          licenses.
170.32 Schedule of fees for health and safety, and safeguards 
          inspections for materials licenses.

                               Enforcement

170.41 Failure by applicant or licensee to pay prescribed fees.
170.51 Right to review and appeal of prescribed fees.

    Authority: Atomic Energy Act of 1954, secs. 11, 161(w) (42 U.S.C. 
2014, 2201(w)); Energy Reorganization Act of 1974, sec. 201 (42 U.S.C. 
5841); 42 U.S.C. 2214; 31 U.S.C. 901, 902, 9701; 44 U.S.C. 3504 note.

    Source: 33 FR 10924, Aug. 1, 1968; 33 FR 11587, Aug. 15, 1968, 
unless otherwise noted.

                           General Provisions



Sec. 170.1  Purpose.

    The regulations in this part set out fees charged for licensing 
services, inspection services, and special projects rendered by the 
Nuclear Regulatory Commission as authorized under title V of the 
Independent Offices Appropriation Act of 1952 (31 U.S.C. 9701(a)).

[81 FR 41186, June 24, 2016]



Sec. 170.2  Scope.

    Except for persons who apply for or hold the permits, licenses, or 
approvals exempted in Sec. 170.11, the regulations in this part apply 
to a person who is:
    (a) An applicant for or holder of a specific byproduct material 
license issued pursuant to parts 30 and 32 through 36 and 39 of this 
chapter;
    (b) An applicant for or holder of a specific source material license 
issued pursuant to part 40 of this chapter;
    (c) An applicant for or holder of a specific special nuclear 
material license issued pursuant to part 70 of this chapter;
    (d) An applicant for or holder of specific approval of spent fuel 
casks and shipping containers issued pursuant to part 71 of this 
chapter;
    (e) An applicant for or holder of a specific license to possess 
power reactor spent fuel and other radioactive materials associated with 
spent fuel storage in an independent spent fuel storage installation 
issued pursuant to part 72 of this chapter;
    (f) An applicant for or holder of a specific approval of sealed 
sources and devices containing byproduct material, source material, or 
special nuclear material;
    (g) An applicant for or holder of a production or utilization 
facility construction permit or operating license issued under 10 CFR 
part 50, or an early

[[Page 838]]

site permit, standard design certification, standard design approval, 
manufacturing license, or combined license issued under 10 CFR part 52;
    (h) Required to have examinations and tests performed to qualify or 
requalify individuals as part 55 reactor operators;
    (i) Required to have routine and non-routine safety and safeguards 
inspections of activities licensed pursuant to the requirements of this 
chapter;
    (j) [Reserved]
    (k) Applying for or already has applied for review, under appendix Q 
to 10 CFR part 50 of a facility site before the submission of an 
application for a construction permit;
    (l) Applying for or already has applied for review of a standardized 
spent fuel facility design; or
    (m) Applying for or has applied for since March 23, 1978, review of 
an item under the category of special projects in this chapter that the 
Commission completes or makes whether or not in conjunction with a 
license application on file or that may be filed.
    (n) An applicant for or holder of a license, approval, 
determination, or other authorization issued by the Commission pursuant 
to 10 CFR part 61.
    (o) Requesting preapplication/licensing review assistance by 
consulting with the NRC and/or by filing preliminary analyses, 
documents, or reports.
    (p) An applicant for or a holder of a specific import or export 
license issued pursuant to 10 CFR part 110.
    (q) An Agreement State licensee who files for or is holder of a 
general license under the reciprocity provisions of 10 CFR 150.20.
    (r) An applicant for or a holder of a certificate of compliance 
issued under 10 CFR Part 76.
    (s) A holder of a general license granted by 10 CFR Part 31 who is 
required to register a device(s).
    (t) An owner or operator of an unlicensed site in decommissioning 
being conducted under NRC oversight.
    (u) Submitting a Touhy request, pursuant to 10 CFR 9.200 through 
9.204, as defined in Sec. 170.3.

[49 FR 21301, May 21, 1984, as amended at 52 FR 8242, Mar. 17, 1987; 54 
FR 15399, Apr. 18, 1989; 56 FR 31499, July 10, 1991; 58 FR 7737, Feb. 9, 
1993; 64 FR 31469, June 10, 1999; 66 FR 32469, June 14, 2001; 70 FR 
30543, May 26, 2005; 72 FR 49565, Aug. 28, 2007; 81 FR 41186, June 24, 
2016]



Sec. 170.3  Definitions.

    As used in this part:
    Act means the Atomic Energy Act of 1954 (68 Stat. 919) including any 
amendments thereto;
    Agreement State means any State with which the Commission or the 
Atomic Energy Commission has entered into an effective agreement under 
subsection 274b of the Act. ``Nonagreement State'' means any other 
State.
    Application means any request filed with the Commission for a 
permit, license, approval, exemption, certificate, other permission, or 
for any other service.
    Balance of plant consists of the remaining systems, components, and 
structures that comprise a complete nuclear power plant and are not 
included in the nuclear steam supply system.
    Byproduct material means--
    (1) Any radioactive material (except special nuclear material) 
yielded in, or made radioactive by, exposure to the radiation incident 
to the process of producing or using special nuclear material;
    (2)(i) Any discrete source of radium-226 that is produced, 
extracted, or converted after extraction, before, on, or after August 8, 
2005, for use for a commercial, medical, or research activity; or
    (ii) Any material that--
    (A) Has been made radioactive by use of a particle accelerator; and
    (B) Is produced, extracted, or converted after extraction, before, 
on, or after August 8, 2005, for use for a commercial, medical, or 
research activity; and
    (3) Any discrete source of naturally occurring radioactive material, 
other than source material, that--

[[Page 839]]

    (i) The Commission, in consultation with the Administrator of the 
Environmental Protection Agency, the Secretary of Energy, the Secretary 
of Homeland Security, and the head of any other appropriate Federal 
agency, determines would pose a threat similar to the threat posed by a 
discrete source of radium-226 to the public health and safety or the 
common defense and security; and
    (ii) Before, on, or after August 8, 2005, is extracted or converted 
after extraction for use in a commercial, medical, or research activity.
    Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the Government.
    Greater Than Class C Waste or GTCC Waste means low-level radioactive 
waste that exceeds the concentration limits of radionuclides established 
for Class C waste in 10 CFR 61.55.
    High Enriched Uranium means uranium enriched to 20 percent or 
greater in the isotope uranium-235.
    Human use means the internal or external administration of 
byproduct, source, or special nuclear material, or the radiation 
therefrom, to human beings.
    Inspections means:
    (1) Routine inspections designed to evaluate the licensee's 
activities within the context of the licensee having primary 
responsibility for protection of the public and environment;
    (2) Non-routine inspections in response or reaction to an incident, 
allegation, follow up to inspection deficiencies or inspections to 
determine implementation of safety issues. A non-routine or reactive 
inspection has the same purpose as the routine inspection;
    (3) Reviews and assessments of licensee performance;
    (4) Evaluations, such as those performed by Diagnostic Evaluation 
Teams; or
    (5) Incident investigations.
    Low Enriched Uranium means uranium enriched below 20 percent in the 
isotope uranium-235.
    Manufacturing license means a license pursuant to Appendix M of part 
52 of this chapter to manufacture a nuclear power reactor(s) to be 
operated at sites not identified in the license application.
    Materials license means a license, certificate, approval, 
registration, or other form of permission issued or granted by the NRC 
under the regulations in 10 CFR Parts 30, 31 through 36, 39, 40, 61, 70, 
72, and 76.
    Nonprofit educational institution means a public or nonprofit 
educational institution whose primary function is education, whose 
programs are accredited by a nationally recognized accrediting agency or 
association, who is legally authorized to provide a program of organized 
instruction or study, who provides an educational program for which it 
awards academic degrees, and whose educational programs are available to 
the public.
    Nuclear reactor means an apparatus, other than an atomic weapon, 
designed or used to sustain nuclear fission in a self-supporting chain 
reaction.
    Nuclear Steam Supply System consists of the reactor core, reactor 
coolant system, and related auxiliary systems including the emergency 
core cooling system; decay heat removal system; and chemical volume and 
control system.
    Other production or utilization facility means a facility other than 
a nuclear reactor licensed by the Commission under the authority of 
section 103 or 104 of the Atomic Energy Act of 1954, as amended (the 
Act), and pursuant to the provisions of part 50 of this chapter.
    Overhead and general and administrative costs means:
    (1) The Government benefits for each employee such as leave and 
holidays, retirement and disability benefits, health and life insurance 
costs, and social security costs;
    (2) Travel costs;
    (3) Overhead [e.g., supervision and support staff that directly 
support the NRC's Nuclear Reactor Safety Program and Nuclear Materials 
Safety and

[[Page 840]]

Waste Program; administrative support costs (e.g., rental of space, 
equipment, telecommunications, and supplies)]; and
    (4) Indirect costs that would include, but not be limited to, NRC 
central policy direction, legal, and executive management services for 
the Commission, and special and independent reviews, investigations, and 
enforcement, and appraisal of NRC programs and operations. Some of the 
organizations included, in whole or in part, are the Commissioners, 
Secretary, Executive Director for Operations, General Counsel, 
Congressional and Public Affairs (except for international safety and 
safeguards programs), Inspector General, Investigations, Enforcement, 
Small Business and Civil Rights, the Technical Training Center, Advisory 
Committee on Reactor Safeguards, and the Atomic Safety and Licensing 
Board Panel. The Commission views these budgeted costs as support for 
all its regulatory services provided to applicants, licensees, and 
certificate holders, and these costs must be recovered under Public Law 
101-508.
    Part 55 Reviews as used in this part means those services provided 
by the Commission to administer requalification and replacement 
examinations and tests for reactor operators licensed pursuant to 10 CFR 
part 55 of the Commission's regulations and employed by part 50 
licensees. These services also include related items such as the 
preparation, review, and grading of the examinations and tests.
    Person as used in this part has the same meaning as found in parts 
30, 40, 50, and 70 of title 10 of the Code of Federal Regulations.
    Power reactor means a nuclear reactor designed to produce electrical 
or heat energy licensed by the Commission under the authority of section 
103 or subsection 104b of the Act and pursuant to the provisions of 
Sec. 50.21(b) or Sec. 50.22 of this chapter.
    Production facility means:
    (1) Any nuclear reactor designed or used primarily for the formation 
of plutonium or uranium-233; or
    (2) Any facility designed or used for the separation of the isotopes 
of plutonium, except laboratory scale facilities designed or used for 
experimental or analytical purposes only; or
    (3) Any facility designed or used for the processing of irradiated 
materials containing special nuclear material except:
    (i) Laboratory scale facilities designed or used for experimental or 
analytical purposes;
    (ii) Facilities in which the only special nuclear materials 
contained in the irradiated material to be processed are uranium 
enriched in the isotope U\235\ and plutonium produced by the 
irradiation, if the material processed contains not more than 
10-6 grams of plutonium per gram of U\235\ and has fission 
product activity not in excess of 0.25 millicurie of fission products 
per gram of U\235\; and
    (iii) Facilities in which processing is conducted pursuant to a 
license issued under parts 30 and 70 of this chapter, or equivalent 
regulations of an Agreement State, for the receipt, possession, use, and 
transfer of irradiated special nuclear material, which authorizes the 
processing of the irradiated material on a batch basis for the 
separation of selected fission products and limits the process batch to 
not more than 100 grams of uranium enriched in the isotope 235 and not 
more than 15 grams of any other special nuclear material.
    Reference systems concept means a concept that involves the review 
of an entire facility design or major fraction of a facility design 
outside of the context of a license application. The standard design 
would be referenced in subsequent license applications.
    Research reactor means a nuclear reactor licensed by the Commission 
under the authority of subsection 104c of the Act and pursuant to the 
provisions of Sec. 50.21(c) of this chapter for operation at a thermal 
power level of 10 megawatts or less, and which is not a testing facility 
as defined in this section.
    The phrase review is completed as used in this part means that the 
review has been brought to an end, whether by reason of issuance of a 
permit, license, approval, certificate, exemption, or other form of 
permission, or whether the application is denied, withdrawn, suspended, 
or action on the application is postponed by the applicant.

[[Page 841]]

    Sealed source means any byproduct material that is encased in a 
capsule designed to prevent leakage or escape of the byproduct material.
    Small modular reactor (SMR) for the purposes of calculating fees, 
means the class of light-water power reactors having a licensed thermal 
power rating less than or equal to 1,000 MWt per module. This rating is 
based on the thermal power equivalent of a light-water SMR with an 
electrical power generating capacity of 300 MWe or less per module.
    Small modular reactor site (SMR site) is the geographically bounded 
location of one or more SMRs and a basis on which SMR fees are 
calculated.
    Source material means:
    (1) Uranium or thorium, or any combination thereof, in any physical 
or chemical form; or
    (2) Ores which contain by weight one-twentieth of one percent 
(0.05%) or more of
    (i) Uranium,
    (ii) Thorium, or
    (iii) Any combination thereof. Source material does not include 
special nuclear material.
    Special nuclear material means:
    (1) Plutonium, uranium-233, uranium enriched in the isotope 233 or 
in the isotope 235, and any other material which the Commission, 
pursuant to the provisions of section 51 of the Act, determines to be 
special nuclear material but does not include source material; or
    (2) Any material artificially enriched by any of the foregoing, but 
does not include source material.
    Special projects means specific services provided by the Commission 
for which fees are not otherwise specified in this chapter. This 
includes, but is not limited to, contested hearings on licensing actions 
directly related to U.S. Government national security initiatives (as 
determined by the NRC), topical report reviews, early site reviews, 
waste solidification activities, activities related to the tracking and 
monitoring of shipment of classified matter, services provided to 
certify licensee, vendor, or other private industry personnel as 
instructors for 10 CFR part 55 reactor operators, reviews of financial 
assurance submittals that do not require a license amendment, reviews of 
responses to Confirmatory Action Letters, reviews of uranium recovery 
licensees' land-use survey reports, and reviews of 10 CFR 50.71 final 
safety analysis reports. Special projects does not include activities 
otherwise exempt from fees under this part. It also does not include 
those contested hearings for which a fee exemption is granted in Sec. 
170.11(a)(2), including those related to individual plant security 
modifications.
    Testing facility means a nuclear reactor licensed by the Commission 
under the authority of subsection 104c of the Act and pursuant to the 
provisions of Sec. 50.21(c) of this chapter for operation at:
    (1) A thermal power level in excess of 10 megawatts; or
    (2) A thermal power level in excess of 1 megawatt, if the reactor is 
to contain:
    (i) A circulating loop through the core in which the applicant 
proposes to conduct fuel experiments; or
    (ii) A liquid fuel loading; or
    (iii) An experimental facility in the core in excess of 16 square 
inches in cross-section.
    Touhy request means a request for NRC records or NRC testimony that 
is made pursuant to the NRC's regulations at 10 CFR 9.200 through 9.204.
    Uranium enrichment facility means:
    (1) Any facility used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, except laboratory scale facilities 
designed or used for experimental or analytical purposes only; or
    (2) Any equipment or device, or important component part especially 
designed for this equipment or device, capable of separating the 
isotopes of uranium or enriching uranium in the isotope 235.
    Utilization facility means:
    (1) Any nuclear reactor other than one designed or used primarily 
for the formation of plutonium or U-233; or
    (2) An accelerator-driven subcritical operating assembly used for 
the irradiation of materials containing special nuclear material and 
described in the application assigned docket number 50-608.

[33 FR 10924, Aug. 1, 1968]

[[Page 842]]


    Editorial Note: For Federal Register citations affecting Sec. 
170.3, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 170.4  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by an 
officer or employee of the Commission other than a written 
interpretation by the General Counsel will be recognized to be binding 
upon the Commission.



Sec. 170.5  Communications.

    All communications concerning the regulations in this part should be 
addressed to the NRC's Chief Financial Officer, either by mail to the 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand 
delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland; or, where practicable, by electronic submission, for example, 
via Electronic Information Exchange, or CD-ROM. Electronic submissions 
must be made in a manner that enables the NRC to receive, read, 
authenticate, distribute, and archive the submission, and process and 
retrieve it a single page at a time. Detailed guidance on making 
electronic submissions can be obtained by visiting the NRC's Web site at 
http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[68 FR 58825, Oct. 10, 2003, as amended at 74 FR 62686, Dec. 1, 2009; 80 
FR 74982, Dec. 1, 2015]



Sec. 170.8  Information collection requirements: OMB approval

    This part contains no information collection requirements and 
therefore is not subject to the requirements of the Paperwork Reduction 
Act (44 U.S.C. 3501 et seq.).

[62 FR 52191, Oct. 6, 1997]



Sec. 170.11  Exemptions.

    (a) No application fees, license fees, renewal fees, inspection 
fees, or special project fees shall be required for:
    (1) A special project that is a request/report submitted to the 
NRC--
    (i) In response to a Generic Letter or NRC Bulletin that does not 
result in an amendment to the license, does not result in the review of 
an alternate method or reanalysis to meet the requirements of the 
Generic Letter, or does not involve an unreviewed safety issue;
    (ii) When the NRC, at the time the request/report is submitted, 
plans to use the information in response to an NRC request from the 
Office Director level or above to resolve an identified safety, 
safeguards, or environmental issue, or to assist the NRC in generic 
regulatory improvements or efforts (e.g., rules, regulatory guides, 
regulations, policy statements, generic letters, or bulletins).
    (2) A contested hearing conducted by the NRC on a specific 
application or the authorizations and conditions of a specific NRC 
license, certificate, or other authorization, including those involving 
individual plant security modifications. This exemption does not apply 
to a contested hearing on a licensing action that the NRC determines 
directly involves a U.S. Government national security-related 
initiative, including those specifically associated with Presidentially-
directed national security programs.
    (3) [Reserved]
    (4) A construction permit or license applied for by, or issued to, a 
non-profit educational institution for a production or utilization 
facility, other than a power reactor, or for the possession and use of 
byproduct material, source material, or special nuclear material. This 
exemption does not apply to those byproduct, source or special nuclear 
material licenses which authorize:
    (i) Human use;
    (ii) Remunerated services to other persons;
    (iii) Distribution of byproduct material, source material, or 
special nuclear material or products containing byproduct material, 
source material or special nuclear material; or
    (iv) Activities performed under a Government agency contract.

[[Page 843]]

    (5)-(8) [Reserved]
    (9) Federally-owned and State-owned research reactors used primarily 
for educational training and academic research purposes. For purposes of 
this exemption, the term research reactor means a nuclear reactor that--
    (i) Is licensed by the Nuclear Regulatory Commission under section 
104c. of the Atomic Energy Act of 1954 (42 U.S.C. 2134(c)) at a thermal 
power level of 10 megawatts or less; and
    (ii) If so licensed at a thermal power level of more than 1 
megawatt, does not contain--
    (A) A circulating loop through the core in which the licensee 
conducts fuel experiments;
    (B) A liquid fuel loading; or
    (C) An experimental facility in the core in excess of 16 square 
inches in cross-section.
    (10) Activities of the Commission undertaken, pursuant to part 75 of 
this chapter, solely for the purpose of implementation of the US/IAEA 
Safeguards Agreement.
    (11) [Reserved]
    (12) A performance assessment or evaluation for which the licensee 
volunteers at the NRC's request and which is selected by the NRC.
    (13) All fee exemption requests must be submitted in writing to the 
Chief Financial Officer in accordance with Sec. 170.5, and the Chief 
Financial Officer will grant or deny such requests in writing.
    (b) The Commission may, upon application by an interested person, or 
upon its own initiative, grant such exemptions from the requirements of 
this part as it determines are authorized by law and are otherwise in 
the public interest. Applications for exemption under this paragraph may 
include activities such as, but not limited to, the use of licensed 
materials for educational or noncommercial public displays or scientific 
collections.

[33 FR 10924, Aug. 1, 1968]

    Editorial Note: For Federal Register citations affecting Sec. 
170.11, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 170.12  Payment of fees.

    (a) Application and registration fees. Each application or 
registration for which a fee is prescribed must be accompanied by a 
remittance for the full amount of the fee. The NRC will not issue a new 
license or an amendment increasing the scope of an existing license to a 
higher fee category before receiving the prescribed application fee. The 
application or registration fee(s) is charged whether the Commission 
approves the application or not. The application or registration fee(s) 
is also charged if the applicant withdraws the application or 
registration.
    (b) Licensing fees. (1) Licensing fees will be assessed to recover 
full costs for--
    (i) The review of applications for new licenses and approvals;
    (ii) The review of applications for amendments to and renewal of 
existing licenses or approvals;
    (iii) Preapplication consultations and reviews; and
    (iv) The full cost for project managers assigned to a specific plant 
or facility, excluding leave time and time spent on generic activities 
(such as rulemaking).
    (2) Full cost fees will be determined based on the professional 
staff time and appropriate contractual support services expended. The 
full cost fees for professional staff time will be determined at the 
professional hourly rates in effect the time the service was provided. 
The full cost fees are payable upon notification by the Commission.
    (3) The NRC intends to bill each applicant or licensee at quarterly 
intervals for all accumulated costs for each application the applicant 
or licensee has on file for NRC review, until the review is completed.
    (4) The NRC intends to bill each applicant or licensee for costs 
related to project manager time on a quarterly basis. Each bill will 
identify the costs related to project manager time.
    (c) Inspection fees. (1) Inspection fees will be assessed to recover 
full cost for each resident inspector (including the senior resident 
inspector), assigned to a specific plant or facility. The fees assessed 
will be based on the number of hours that each inspector assigned to the 
plant or facility is in an official

[[Page 844]]

duty status (i.e., all time in a non-leave status), excluding time spent 
by a resident inspector in support of activities at another site. The 
hours will be billed at the appropriate hourly rate established in 10 
CFR 170.20. Resident inspectors' time related to a specific inspection 
will be included in the fee assessed for the specific inspection in 
accordance with paragraph (c)(2) of this section.
    (2) Inspection fees will be assessed to recover the full cost for 
each specific inspection, including plant- or licensee-specific 
performance reviews and assessments, evaluations, and incident 
investigations. For inspections that result in the issuance of an 
inspection report, fees will be assessed for costs incurred up to 
approximately 30 days after the inspection report is issued. The costs 
for these inspections include preparation time, time on site, 
documentation time, and follow-up activities and any associated 
contractual service costs, but exclude the time involved in the 
processing and issuance of a notice of violation or civil penalty.
    (3) The NRC intends to bill for resident inspectors' time and for 
specific inspections subject to full cost recovery on a quarterly basis. 
The fees are payable upon notification by the Commission.
    (d) Special project fees. (1) All special projects performed by the 
Commission, unless otherwise exempt from fees or for which fees are 
otherwise specified in this part, will be assessed fees to recover the 
full cost of the service provided. Special projects means specific 
services provided by the Commission, including but not limited to--
    (i) Topical reports;
    (ii) Financial assurance submittals that do not require a license 
amendment;
    (iii) Responses to Confirmatory Action Letters;
    (iv) Uranium recovery licensees' land-use survey reports;
    (v) 10 CFR 50.71 final safety analysis reports;
    (vi) Contested hearings on licensing actions directly involving U.S 
Government national security initiatives, as determined by the NRC; and
    (vii) Responses to Touhy requests that require the NRC staff to 
expend more than 50 hours of official time. Fees for Touhy requests will 
be billed at the appropriate hourly rate established in Sec. 170.20.
    (2) The NRC intends to bill each applicant or licensee at quarterly 
intervals until the special project is completed. Each bill will 
identify the special project, including any documents submitted for 
review or the specific contested hearing, and the related costs. The 
fees are payable upon notification by the Commission.
    (e) Part 55 review fees. Fees for Part 55 review services are based 
on NRC time spent in administering the examinations and tests and any 
related contractual costs. The fees assessed will also include related 
activities such as preparing, reviewing, and grading of the examinations 
and tests. The NRC intends to bill the costs at quarterly intervals to 
the licensee employing the operators.
    (f) Method of payment. All license fee payments are to be made 
payable to the U.S. Nuclear Regulatory Commission. The payments are to 
be made in U.S. funds by electronic funds transfer such as ACH 
(Automated Clearing House) using E.D.I. (Electronic Data Interchange), 
check, draft, money order, or credit card. Payment of invoices of $5,000 
or more should be paid via ACH through NRC's Lockbox Bank at the address 
indicated on the invoice. Credit card payments should be made up to the 
limit established by the credit card bank at the address indicated on 
the invoice. Specific written instructions for making electronic 
payments and credit card payments may be obtained by contacting the 
License Fee and Accounts Receivable Branch at 301-415-7554. In 
accordance with Department of the Treasury requirements, refunds will 
only be made upon receipt of information on the payee's financial 
institution and bank accounts.
    (g) Collection of underpayment of fees. The NRC is entitled to 
collect any underpayment of fees as a result of an error by the NRC.

[64 FR 31469, June 10, 1999, as amended at 65 FR 11204, Mar. 2, 2000; 65 
FR 36959, June 12, 2000; 66 FR 32469, June 14, 2001; 67 FR 64037, Oct. 
17, 2002; 72 FR 31420, June 6, 2007; 79 FR 37144, June 30, 2014; 81 FR 
41186, June 24, 2016]

[[Page 845]]



Sec. 170.20  Average cost per professional staff-hour.

    Fees for permits, licenses, amendments, renewals, special projects, 
10 CFR part 55 re-qualification and replacement examinations and tests, 
other required reviews, approvals, and inspections under Sec. Sec. 
170.21 and 170.31 will be calculated using the professional staff-hour 
rate of $263 per hour.

[82 FR 30699, June 30, 2017]

                            Schedule of Fees



Sec. 170.21  Schedule of fees for production and utilization 
facilities, review of standard referenced design approvals, special
projects, inspections and import and export licenses.

    Applicants for construction permits, manufacturing licenses, 
operating licenses, import and export licenses, approvals of facility 
standard reference designs, re-qualification and replacement 
examinations for reactor operators, and special projects and holders of 
construction permits, licenses, and other approvals shall pay fees for 
the following categories of services:

                        Schedule of Facility Fees
                     [See footnotes at end of table]
------------------------------------------------------------------------
      Facility categories and type of fees              Fees \1 2\
------------------------------------------------------------------------
A. Nuclear Power Reactors:
    Application for Construction Permit........  Full Cost.
    Early Site Permit, Construction Permit,      Full Cost.
     Combined License, Operating License.
    Amendment, Renewal, Dismantling-             Full Cost.
     Decommissioning and Termination, Other
     Approvals.
    Inspections \3\............................  Full Cost.
B. Standard Reference Design Review:
    Preliminary Design Approvals, Final Design   Full Cost.
     Approvals, Certification.
    Amendment, Renewal, Other Approvals........  Full Cost.
C. Test Facility/Research Reactor/Critical
 Facility:
    Application for Construction Permit........  Full Cost.
    Construction Permit, Operating License.....  Full Cost.
    Amendment, Renewal, Dismantling-             Full Cost.
     Decommissioning and Termination, Other
     Approvals.
    Inspections \3\............................  Full Cost.
D. Manufacturing License:
    Application for Construction...............  Full Cost.
    Preliminary Design Approval, Final Design    Full Cost.
     Approval.
    Amendment Renewal, Other Approvals.........  Full Cost.
    Inspections \3\............................  Full Cost.
E. [Reserved]
F. [Reserved]
G. Other Production or Utilization Facility:
    Application for Construction Permit........  Full Cost.
    Construction Permit, Operating License.....  Full Cost.
    Amendment, Renewal, Other Approvals........  Full Cost.
    Inspections \3\............................  Full Cost.
H. Production or Utilization Facility
 Permanently Closed Down:
    Inspections \3\............................  Full Cost.
I. Part 55 Reviews:
    Requalification and Replacement              Full Cost.
     Examinations for Reactors Operators.
J. Special Projects:
    Approvals and preapplication/licensing       Full Cost.
     activities.
    Inspections \3\............................  Full Cost.
    Contested hearings on licensing actions      Full Cost.
     directly related to U.S. Government
     national security initiatives.
    Touhy requests \5\.........................  Full Cost.
K. Import and export licenses:
Licenses for the import and export only of
 production or utilization facilities or the
 export only of components for production or
 utilization facilities issued under 10 CFR
 part 110.
    1. Application for import or export of
     production or utilization facilities \4\
     (including reactors and other facilities)
     and exports of components requiring
     Commission and Executive Branch review,
     for example, actions under 10 CFR
     110.40(b)..
        Application--new license, or amendment;  $18,400
         or license exemption request.
    2. Application for export of reactor and
     other components requiring Executive
     Branch review, for example, those actions
     under 10 CFR 110.41(a)..
        Application--new license, or amendment;  9,200
         or license exemption request.
    3. Application for export of components
     requiring the assistance of the Executive
     Branch to obtain foreign government
     assurances..
        Application--new license, or amendment;  4,500
         or license exemption request.

[[Page 846]]

 
    4. Application for export of facility
     components and equipment not requiring
     Commission or Executive Branch review, or
     obtaining foreign government assurances..
        Application--new license, or amendment;  4,500
         or license exemption request.
    5. Minor amendment of any active export or
     import license, for example, to extend the
     expiration date, change domestic
     information, or make other revisions which
     do not involve any substantive changes to
     license terms or conditions or to the type
     of facility or component authorized for
     export and, therefore, do not require in-
     depth analysis or review or consultation
     with the Executive Branch, U.S. host
     state, or foreign government authorities..
        Minor amendment to license.............  2,600
------------------------------------------------------------------------
\1\ Fees will not be charged for orders related to civil penalties or
  other civil sanctions issued by the Commission under Sec. 2.202 of
  this chapter or for amendments resulting specifically from the
  requirements of these orders. For orders unrelated to civil penalties
  or other civil sanctions, fees will be charged for any resulting
  licensee-specific activities not otherwise exempted from fees under
  this chapter. Fees will be charged for approvals issued under a
  specific exemption provision of the Commission's regulations under
  Title 10 of the Code of Federal Regulations (e.g., 10 CFR 50.12, 10
  CFR 73.5) and any other sections in effect now or in the future,
  regardless of whether the approval is in the form of a license
  amendment, letter of approval, safety evaluation report, or other
  form.
\2\ Full cost fees will be determined based on the professional staff
  time and appropriate contractual support services expended. For
  applications currently on file and for which fees are determined based
  on the full cost expended for the review, the professional staff hours
  expended for the review of the application up to the effective date of
  the final rule will be determined at the professional rates in effect
  when the service was provided.
\3\ Inspections covered by this schedule are both routine and non-
  routine safety and safeguards inspections performed by NRC for the
  purpose of review or follow-up of a licensed program. Inspections are
  performed through the full term of the license to ensure that the
  authorized activities are being conducted in accordance with the
  Atomic Energy Act of 1954, as amended, other legislation, Commission
  regulations or orders, and the terms and conditions of the license.
  Non-routine inspections that result from third-party allegations will
  not be subject to fees.
\4\ Imports only of major components for end-use at NRC-licensed
  reactors are authorized under NRC general import license in 10 CFR
  110.27.
\5\ Full cost fees will be assessed once NRC work on a Touhy request
  exceeds 50 hours, in accordance with Sec. 170.12(d).


[53 FR 52648, Dec. 29, 1988]

    Editorial Note: For Federal Register citations affecting Sec. 
170.21, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 170.31  Schedule of fees for materials licenses and other 
regulatory services, including inspections, and import and export
licenses.

    Applicants for materials licenses, import and export licenses, and 
other regulatory services, and holders of materials licenses or import 
and export licenses shall pay fees for the following categories of 
services. For those fee categories identified to be subject to full cost 
fees, full cost fees will be assessed for all licensing and inspection 
activities, unless otherwise indicated.

                       Schedule of Materials Fees
                     [See footnotes at end of table]
------------------------------------------------------------------------
  Category of materials licenses and type of
                   fees \1\                            Fee \2\ \3\
------------------------------------------------------------------------
1. Special nuclear material:
    A. (1) Licenses for possession and use of
     U-235 or plutonium for fuel fabrication
     activities.
        (a) Strategic Special Nuclear Material  Full Cost.
         (High Enriched Uranium) [Program
         Code(s): 21213].
        (b) Low Enriched Uranium in             Full Cost.
         Dispersible Form Used for Fabrication
         of Power Reactor Fuel [Program
         Code(s): 21210].
    (2) All other special nuclear materials
     licenses not included in Category 1.A.(1)
     which are licensed for fuel cycle
     activities.
        (a) Facilities with limited operations  Full Cost.
         [Program Code(s): 21240, 21310,
         21320].
        (b) Gas centrifuge enrichment           Full Cost.
         demonstration facilities [Program
         Code(s): 21205].
        (c) Others, including hot cell          Full Cost.
         facilities [Program Code(s): 21130,
         21133].
    B. Licenses for receipt and storage of      Full Cost.
     spent fuel and reactor-related Greater
     than Class C (GTCC) waste at an
     independent spent fuel storage
     installation (ISFSI) [Program Code(s):
     23200].
    C. Licenses for possession and use of       $1,200.
     special nuclear material of less than a
     critical mass as defined in Sec. 70.4
     in sealed sources contained in devices
     used in industrial measuring systems,
     including x-ray fluorescence
     analyzers.\4\ Application [Program
     Code(s): 22140].

[[Page 847]]

 
    D. All other special nuclear material       $2,400.
     licenses, except licenses authorizing
     special nuclear material in sealed or
     unsealed form in combination that would
     constitute a critical mass, as defined in
     Sec. 70.4 of this chapter, for which
     the licensee shall pay the same fees as
     those under Category 1.A.\4\ Application
     [Program Code(s): 22110, 22111, 22120,
     22131, 22136, 22150, 22151, 22161, 22170,
     23100, 23300, 23310].
    E. Licenses or certificates for             Full Cost.
     construction and operation of a uranium
     enrichment facility [Program Code(s):
     21200].
    F. Licenses for possession and use of       Full Cost.
     special nuclear material greater than
     critical mass, as defined in Sec. 70.4
     of this chapter, for development and
     testing of commercial products, and other
     non-fuel-cycle activities.\4\ [Program
     Code(s): 22155].
2. Source material:
    A. (1) Licenses for possession and use of   Full Cost.
     source material for refining uranium mill
     concentrates to uranium hexafluoride or
     for deconverting uranium hexafluoride in
     the production of uranium oxides for
     disposal. [Program Code(s): 11400]
    (2) Licenses for possession and use of
     source material in recovery operations
     such as milling, in-situ recovery, heap-
     leaching, ore buying stations, ion-
     exchange facilities, and in processing of
     ores containing source material for
     extraction of metals other than uranium
     or thorium, including licenses
     authorizing the possession of byproduct
     waste material (tailings) from source
     material recovery operations, as well as
     licenses authorizing the possession and
     maintenance of a facility in a standby
     mode.
        (a) Conventional and Heap Leach         Full Cost.
         facilities [Program Code(s): 11100].
        (b) Basic In Situ Recovery facilities   Full Cost.
         [Program Code(s): 11500].
        (c) Expanded In Situ Recovery           Full Cost.
         facilities [Program Code(s): 11510].
        (d) In Situ Recovery Resin facilities   Full Cost.
         [Program Code(s): 11550].
        (e) Resin Toll Milling facilities       Full Cost.
         [Program Code(s): 11555].
        (f) Other facilities [Program Code(s):  Full Cost.
         11700].
    (3) Licenses that authorize the receipt of  Full Cost.
     byproduct material, as defined in Section
     11e.(2) of the Atomic Energy Act, from
     other persons for possession and
     disposal, except those licenses subject
     to the fees in Category 2.A.(2) or
     Category 2.A.(4) [Program Code(s): 11600,
     12000].
    (4) Licenses that authorize the receipt of  Full Cost.
     byproduct material, as defined in Section
     11e.(2) of the Atomic Energy Act, from
     other persons for possession and disposal
     incidental to the disposal of the uranium
     waste tailings generated by the
     licensee's milling operations, except
     those licenses subject to the fees in
     Category 2.A.(2) [Program Code(s): 12010].
    (5) Licenses that authorize the possession  Full Cost.
     of source material related to removal of
     contaminants (source material) from
     drinking water [Program Code(s): 11820].
    B. Licenses which authorize the             $1,200.
     possession, use, and/or installation of
     source material for shielding.6 7 8
     Application [Program Code(s): 11210].
    C. Licenses to distribute items containing  $2,100.
     source material to persons exempt from
     the licensing requirements of part 40 of
     this chapter. Application [Program
     Code(s): 11240].
    D. Licenses to distribute source material   $2,600.
     to persons generally licensed under part
     40 of this chapter. Application [Program
     Codes(s): 11230, 11231].
    E. Licenses for possession and use of       $2,500.
     source material for processing or
     manufacturing of products or materials
     containing source material for commercial
     distribution. Application [Program
     Code(s): 11710].
    F. All other source material licenses.      $2,500.
     Application [Program Code(s): 11200,
     11220, 11221, 11300, 11800, 11810].
3. Byproduct material:
    A. Licenses of broad scope for the          $12,300.
     possession and use of byproduct material
     issued under parts 30 and 33 of this
     chapter for processing or manufacturing
     of items containing byproduct material
     for commercial distribution. Application
     [Program Code(s): 03211, 03212, 03213].
    B. Other licenses for possession and use    $3,400.
     of byproduct material issued under part
     30 of this chapter for processing or
     manufacturing of items containing
     byproduct material for commercial
     distribution. Application [Program
     Code(s): 03214, 03215, 22135, 22162].
    C. Licenses issued under Sec. Sec. $4,900.
     32.72 and/or 32.74 of this chapter that
     authorize the processing or manufacturing
     and distribution or redistribution of
     radiopharmaceuticals, generators, reagent
     kits, and/or sources and devices
     containing byproduct material. This
     category does not apply to licenses
     issued to nonprofit educational
     institutions whose processing or
     manufacturing is exempt under Sec.
     170.11(a)(4). Application [Program
     Code(s): 02500, 02511, 02513].
    D. [Reserved].............................  N/A.
    E. Licenses for possession and use of       $3,000.
     byproduct material in sealed sources for
     irradiation of materials in which the
     source is not removed from its shield
     (self-shielded units). Application
     [Program Code(s): 03510, 03520].
    F. Licenses for possession and use of less  $6,200.
     than or equal to 10,000 curies of
     byproduct material in sealed sources for
     irradiation of materials in which the
     source is exposed for irradiation
     purposes. This category also includes
     underwater irradiators for irradiation of
     materials where the source is not exposed
     for irradiation purposes. Application
     [Program Code(s): 03511].
    G. Licenses for possession and use of       $58,700.
     greater than 10,000 curies of byproduct
     material in sealed sources for
     irradiation of materials in which the
     source is exposed for irradiation
     purposes. This category also includes
     underwater irradiators for irradiation of
     materials where the source is not exposed
     for irradiation purposes. Application
     [Program Code(s): 03521].

[[Page 848]]

 
    H. Licenses issued under subpart A of part  $6,300.
     32 of this chapter to distribute items
     containing byproduct material that
     require device review to persons exempt
     from the licensing requirements of part
     30 of this chapter. The category does not
     include specific licenses authorizing
     redistribution of items that have been
     authorized for distribution to persons
     exempt from the licensing requirements of
     part 30 of this chapter. Application
     [Program Code(s): 03254, 03255, 03257].
    I. Licenses issued under subpart A of part  $9,400.
     32 of this chapter to distribute items
     containing byproduct material or
     quantities of byproduct material that do
     not require device evaluation to persons
     exempt from the licensing requirements of
     part 30 of this chapter. This category
     does not include specific licenses
     authorizing redistribution of items that
     have been authorized for distribution to
     persons exempt from the licensing
     requirements of part 30 of this chapter.
     Application [Program Code(s): 03250,
     03251, 03252, 03253, 03256].
    J. Licenses issued under subpart B of part  $1,900.
     32 of this chapter to distribute items
     containing byproduct material that
     require sealed source and/or device
     review to persons generally licensed
     under part 31 of this chapter. This
     category does not include specific
     licenses authorizing redistribution of
     items that have been authorized for
     distribution to persons generally
     licensed under part 31 of this chapter.
     Application [Program Code(s): 03240,
     03241, 03243].
    K. Licenses issued under Subpart B of part  $1,100.
     32 of this chapter to distribute items
     containing byproduct material or
     quantities of byproduct material that do
     not require sealed source and/or device
     review to persons generally licensed
     under part 31 of this chapter. This
     category does not include specific
     licenses authorizing redistribution of
     items that have been authorized for
     distribution to persons generally
     licensed under part 31 of this chapter.
     Application [Program Code(s): 03242,
     03244].
    L. Licenses of broad scope for possession
     and use of byproduct material issued
     under parts 30 and 33 of this chapter for
     research and development that do not
     authorize commercial distribution. Number
     of locations of use: 1-5.
        (1) Licenses of broad scope for
         possession and use of byproduct
         material issued under parts 30 and 33
         of this chapter for research and
         development that do not authorize
         commercial distribution. Number of
         locations of use: 6-19.
        (2) Licenses of broad scope for         $5,200.
         possession and use of byproduct
         material issued under parts 30 and 33
         of this chapter for research and
         development that do not authorize
         commercial distribution. Number of
         locations of use: 20 or more.
         Application [Program Code(s): 01100,
         01110, 01120, 03610, 03611, 03612,
         03613, 04610, 04611, 04612, 04613,
         04614, 04615, 04616, 04617, 04618,
         04619, 04620, 04621, 04622, 04623]
    M. Other licenses for possession and use    $6,700.
     of byproduct material issued under part
     30 of this chapter for research and
     development that do not authorize
     commercial distribution. Application
     [Program Code(s): 03620].
    N. Licenses that authorize services for
     other licensees, except:
        (1) Licenses that authorize only
         calibration and/or leak testing
         services are subject to the fees
         specified in fee Category 3.P.; and.
        (2) Licenses that authorize waste       $6,900.
         disposal services are subject to the
         fees specified in fee Categories
         4.A., 4.B., and 4.C. Application
         [Program Code(s): 03219, 03225,
         03226].
    O. Licenses for possession and use of       $3,000.
     byproduct material issued under part 34
     of this chapter for industrial
     radiography operations. Application
     [Program Code(s): 03310, 03320].
    P. All other specific byproduct material    $3,300.
     licenses, except those in Categories 4.A.
     through 9.D.\9\ Application [Program
     Code(s): 02400, 02410, 03120, 03121,
     03122, 03123, 03124, 03130, 03140, 03220,
     03221, 03222, 03800, 03810, 22130].
    Q. Registration of a device(s) generally    $500.
     licensed under part 31 of this chapter.
     Registration.
    R. Possession of items or products
     containing radium-226 identified in 10
     CFR 31.12 which exceed the number of
     items or limits specified in that
     section.\5\
        1. Possession of quantities exceeding   $2,400.
         the number of items or limits in 10
         CFR 31.12(a)(4) or (5) but less than
         or equal to 10 times the number of
         items or limits specified.
         Application [Program Code(s): 02700].
        2. Possession of quantities exceeding   $2,400.
         10 times the number of items or
         limits specified in 10 CFR
         31.12(a)(4) or (5). Application
         [Program Code(s): 02710].
    S. Licenses for production of accelerator-  $13,400.
     produced radionuclides. Application
     [Program Code(s): 03210].
4. Waste disposal and processing:
    A. Licenses specifically authorizing the    Full Cost.
     receipt of waste byproduct material,
     source material, or special nuclear
     material from other persons for the
     purpose of contingency storage or
     commercial land disposal by the licensee;
     or licenses authorizing contingency
     storage of low-level radioactive waste at
     the site of nuclear power reactors; or
     licenses for receipt of waste from other
     persons for incineration or other
     treatment, packaging of resulting waste
     and residues, and transfer of packages to
     another person authorized to receive or
     dispose of waste material. Application
     [Program Code(s): 03231, 03233, 03236,
     06100, 06101].
    B. Licenses specifically authorizing the    $6,500.
     receipt of waste byproduct material,
     source material, or special nuclear
     material from other persons for the
     purpose of packaging or repackaging the
     material. The licensee will dispose of
     the material by transfer to another
     person authorized to receive or dispose
     of the material. Application [Program
     Code(s): 03234].

[[Page 849]]

 
    C. Licenses specifically authorizing the    $4,700.
     receipt of prepackaged waste byproduct
     material, source material, or special
     nuclear material from other persons. The
     licensee will dispose of the material by
     transfer to another person authorized to
     receive or dispose of the material.
     Application [Program Code(s): 03232].
5. Well logging:
    A. Licenses for possession and use of       $4,300.
     byproduct material, source material, and/
     or special nuclear material for well
     logging, well surveys, and tracer studies
     other than field flooding tracer studies.
     Application [Program Code(s): 03110,
     03111, 03112].
    B. Licenses for possession and use of       Full Cost.
     byproduct material for field flooding
     tracer studies. Licensing [Program
     Code(s): 03113].
6. Nuclear laundries:
    A. Licenses for commercial collection and   $21,000.
     laundry of items contaminated with
     byproduct material, source material, or
     special nuclear material. Application
     [Program Code(s): 03218].
7. Medical licenses:
    A. Licenses issued under parts 30, 35, 40,  $10,500.
     and 70 of this chapter for human use of
     byproduct material, source material, or
     special nuclear material in sealed
     sources contained in gamma stereotactic
     radiosurgery units, teletherapy devices,
     or similar beam therapy devices.
     Application [Program Code(s): 02300,
     02310].
    B. Licenses of broad scope issued to        $8,200.
     medical institutions or two or more
     physicians under parts 30, 33, 35, 40,
     and 70 of this chapter authorizing
     research and development, including human
     use of byproduct material, except
     licenses for byproduct material, source
     material, or special nuclear material in
     sealed sources contained in teletherapy
     devices. This category also includes the
     possession and use of source material for
     shielding when authorized on the same
     license.\10\ Application [Program
     Code(s): 02110].
    C. Other licenses issued under parts 30,    $5,200.
     35, 40, and 70 of this chapter for human
     use of byproduct material, source
     material, and/or special nuclear
     material, except licenses for byproduct
     material, source material, or special
     nuclear material in sealed sources
     contained in teletherapy devices.
     Application [Program Code(s): 02120,
     02121, 02200, 02201, 02210, 02220, 02230,
     02231, 02240, 22160].
8. Civil defense:
    A. Licenses for possession and use of       $2,400.
     byproduct material, source material, or
     special nuclear material for civil
     defense activities. Application [Program
     Code(s): 03710].
9. Device, product, or sealed source safety
 evaluation:
    A. Safety evaluation of devices or          $5,100.
     products containing byproduct material,
     source material, or special nuclear
     material, except reactor fuel devices,
     for commercial distribution. Application--
     each device.
    B. Safety evaluation of devices or          $8,500.
     products containing byproduct material,
     source material, or special nuclear
     material manufactured in accordance with
     the unique specifications of, and for use
     by, a single applicant, except reactor
     fuel devices. Application--each device.
    C. Safety evaluation of sealed sources      $5,000.
     containing byproduct material, source
     material, or special nuclear material,
     except reactor fuel, for commercial
     distribution. Application--each source.
    D. Safety evaluation of sealed sources      $1,000.
     containing byproduct material, source
     material, or special nuclear material,
     manufactured in accordance with the
     unique specifications of, and for use by,
     a single applicant, except reactor fuel.
     Application--each source.
10. Transportation of radioactive material:
    A. Evaluation of casks, packages, and
     shipping containers.
        1. Spent Fuel, High-Level Waste, and    Full Cost.
         plutonium air packages.
        2. Other Casks........................  Full Cost.
    B. Quality assurance program approvals
     issued under part 71 of this chapter.
        1. Users and Fabricators.
            Application.......................  $4,000.
            Inspections.......................  Full Cost.
        2. Users.
            Application.......................  $4,000.
            Inspections.......................  Full Cost.
    C. Evaluation of security plans, route      Full Cost.
     approvals, route surveys, and
     transportation security devices
     (including immobilization devices).
11. Review of standardized spent fuel           Full Cost.
 facilities.
12. Special projects:Including approvals, pre-  Full Cost.
 application/licensing activities, and
 inspections. Application [Program Code:
 25110]
13. A. Spent fuel storage cask Certificate of   Full Cost.
 Compliance..
B. Inspections related to storage of spent      Full Cost.
 fuel under Sec. 72.210 of this chapter.
14. A. Byproduct, source, or special nuclear    Full Cost.
 material licenses and other approvals
 authorizing decommissioning, decontamination,
 reclamation, or site restoration activities
 under parts 30, 40, 70, 72, and 76 of this
 chapter, including MMLs. Application [Program
 Code(s): 03900, 11900, 21135, 21215, 21325,
 22200].
B. Site-specific decommissioning activities     Full Cost.
 associated with unlicensed sites, including
 MMLs, regardless of whether or not the sites
 have been previously licensed.
15. Import and Export licenses: Licenses
 issued under part 110 of this chapter for the
 import and export only of special nuclear
 material, source material, tritium and other
 byproduct material, and the export only of
 heavy water, or nuclear grade graphite (fee
 categories 15.A. through 15.E.).

[[Page 850]]

 
    A. Application for export or import of      $18,400.
     nuclear materials, including radioactive
     waste requiring Commission and Executive
     Branch review, for example, those actions
     under 10 CFR 110.40(b). Application--new
     license, or amendment; or license
     exemption request.
    B. Application for export or import of      $9,200.
     nuclear material, including radioactive
     waste, requiring Executive Branch review,
     but not Commission review. This category
     includes applications for the export and
     import of radioactive waste and requires
     NRC to consult with domestic host state
     authorities (i.e., Low-Level Radioactive
     Waste Compact Commission, the U.S.
     Environmental Protection Agency, etc.).
     Application--new license, or amendment;
     or license exemption request.
    C. Application for export of nuclear        $4,500.
     material, for example, routine reloads of
     low enriched uranium reactor fuel and/or
     natural uranium source material requiring
     the assistance of the Executive Branch to
     obtain foreign government assurances.
     Application--new license, or amendment;
     or license exemption request.
    D. Application for export or import of      $4,500.
     nuclear material not requiring Commission
     or Executive Branch review, or obtaining
     foreign government assurances.
     Application--new license, or amendment;
     or license exemption request.
    E. Minor amendment of any active export or  $2,600.
     import license, for example, to extend
     the expiration date, change domestic
     information, or make other revisions
     which do not involve any substantive
     changes to license terms and conditions
     or to the type/quantity/chemical
     composition of the material authorized
     for export and, therefore, do not require
     in-depth analysis, review, or
     consultations with other Executive
     Branch, U.S. host state, or foreign
     government authorities. Minor amendment.
Licenses issued under part 110 of this chapter
 for the import and export only of Category 1
 and Category 2 quantities of radioactive
 material listed in appendix P to part 110 of
 this chapter (fee categories 15.F. through
 15.R.).
Category 1 (Appendix P, 10 CFR Part 110)
 Exports:
    F. Application for export of appendix P     $14,500.
     Category 1 materials requiring Commission
     review (e.g. exceptional circumstance
     review under 10 CFR 110.42(e)(4)) and to
     obtain government-to-government consent
     for this process. (For additional consent
     see 15.I.). Application--new license, or
     amendment; or license exemption request.
    G. Application for export of appendix P     $7,900.
     Category 1 materials requiring Executive
     Branch review and to obtain government-to-
     government consent for this process. For
     additional consents see 15.I.
     Application--new license, or amendment;
     or license exemption request.
    H. Application for export of appendix P     $3,900.
     Category 1 materials and to obtain one
     government-to-government consent for this
     process. For additional consents see
     15.I. Application--new license, or
     amendment; or license exemption request.
    I. Requests for each additional government- $300.
     to-government consent in support of an
     export license application or active
     export license. Application--new license,
     or amendment; or license exemption
     request.
Category 2 (Appendix P, 10 CFR Part 110)
 Exports:
    J. Application for export of appendix P     $14,500.
     Category 2 materials requiring Commission
     review (e.g. exceptional circumstance
     review under 10 CFR 110.42(e)(4)).
     Application--new license, or amendment;
     or license exemption request.
    K. Applications for export of appendix P    $7,900.
     Category 2 materials requiring Executive
     Branch review. Application--new license,
     or amendment; or license exemption
     request.
    L. Application for the export of Category   $3,200.
     2 materials. Application--new license, or
     amendment; or license exemption request.
    M. [Reserved].............................  N/A.
    N. [Reserved].............................  N/A.
    O. [Reserved].............................  N/A.
    P. [Reserved].............................  N/A.
    Q. [Reserved].............................  N/A.
Minor Amendments (Category 1 and 2, Appendix
 P, 10 CFR Part 110, Export):
    R. Minor amendment of any active export     $1,300.
     license, for example, to extend the
     expiration date, change domestic
     information, or make other revisions
     which do not involve any substantive
     changes to license terms and conditions
     or to the type/quantity/chemical
     composition of the material authorized
     for export and, therefore, do not require
     in-depth analysis, review, or
     consultations with other Executive
     Branch, U.S. host state, or foreign
     authorities. Minor amendment.
16. Reciprocity:Agreement State licensees who   $1,800.
 conduct activities under the reciprocity
 provisions of 10 CFR 150.20. Application.
17. Master materials licenses of broad scope    Full Cost.
 issued to Government agencies:Application
 [Program Code(s): 03614].
18. Department of Energy.
    A. Certificates of Compliance. Evaluation   Full Cost.
     of casks, packages, and shipping
     containers (including spent fuel, high-
     level waste, and other casks, and
     plutonium air packages).

[[Page 851]]

 
    B. Uranium Mill Tailings Radiation Control  Full Cost.
     Act (UMTRCA) activities.
------------------------------------------------------------------------
\1\ Types of fees--Separate charges, as shown in the schedule, will be
  assessed for pre-application consultations and reviews; applications
  for new licenses, approvals, or license terminations; possession-only
  licenses; issuances of new licenses and approvals; certain amendments
  and renewals to existing licenses and approvals; safety evaluations of
  sealed sources and devices; generally licensed device registrations;
  and certain inspections. The following guidelines apply to these
  charges:
(a) Application and registration fees. Applications for new materials
  licenses and export and import licenses; applications to reinstate
  expired, terminated, or inactive licenses, except those subject to
  fees assessed at full costs; applications filed by Agreement State
  licensees to register under the general license provisions of 10 CFR
  150.20; and applications for amendments to materials licenses that
  would place the license in a higher fee category or add a new fee
  category must be accompanied by the prescribed application fee for
  each category.
(1) Applications for licenses covering more than one fee category of
  special nuclear material or source material must be accompanied by the
  prescribed application fee for the highest fee category.
(2) Applications for new licenses that cover both byproduct material and
  special nuclear material in sealed sources for use in gauging devices
  will pay the appropriate application fee for fee category 1.C. only.
(b) Licensing fees. Fees for reviews of applications for new licenses,
  renewals, and amendments to existing licenses, pre-application
  consultations and other documents submitted to the NRC for review, and
  project manager time for fee categories subject to full cost fees are
  due upon notification by the Commission in accordance with Sec.
  170.12(b).
(c) Amendment fees. Applications for amendments to export and import
  licenses must be accompanied by the prescribed amendment fee for each
  license affected. An application for an amendment to an export or
  import license or approval classified in more than one fee category
  must be accompanied by the prescribed amendment fee for the category
  affected by the amendment, unless the amendment is applicable to two
  or more fee categories, in which case the amendment fee for the
  highest fee category would apply.
(d) Inspection fees. Inspections resulting from investigations conducted
  by the Office of Investigations and nonroutine inspections that result
  from third-party allegations are not subject to fees. Inspection fees
  are due upon notification by the Commission in accordance with Sec.
  170.12(c).
(e) Generally licensed device registrations under 10 CFR 31.5.
  Submittals of registration information must be accompanied by the
  prescribed fee.
\2\ Fees will not be charged for orders related to civil penalties or
  other civil sanctions issued by the Commission under 10 CFR 2.202 or
  for amendments resulting specifically from the requirements of these
  orders. For orders unrelated to civil penalties or other civil
  sanctions, fees will be charged for any resulting licensee-specific
  activities not otherwise exempted from fees under this chapter. Fees
  will be charged for approvals issued under a specific exemption
  provision of the Commission's regulations under title 10 of the Code
  of Federal Regulations (e.g., 10 CFR 30.11, 40.14, 70.14, 73.5, and
  any other sections in effect now or in the future), regardless of
  whether the approval is in the form of a license amendment, letter of
  approval, safety evaluation report, or other form. In addition to the
  fee shown, an applicant may be assessed an additional fee for sealed
  source and device evaluations as shown in fee categories 9.A. through
  9.D.
\3\ Full cost fees will be determined based on the professional staff
  time multiplied by the appropriate professional hourly rate
  established in Sec. 170.20 in effect when the service is provided,
  and the appropriate contractual support services expended.
\4\ Licensees paying fees under categories 1.A., 1.B., and 1.E. are not
  subject to fees under categories 1.C., 1.D. and 1.F. for sealed
  sources authorized in the same license, except for an application that
  deals only with the sealed sources authorized by the license.
\5\ Persons who possess radium sources that are used for operational
  purposes in another fee category are not also subject to the fees in
  this category. (This exception does not apply if the radium sources
  are possessed for storage only.)
\6\ Licensees subject to fees under fee categories 1.A., 1.B., 1.E., or
  2.A. must pay the largest applicable fee and are not subject to
  additional fees listed in this table.
\7\ Licensees paying fees under 3.C. are not subject to fees under 2.B.
  for possession and shielding authorized on the same license.
\8\ Licensees paying fees under 7.C. are not subject to fees under 2.B.
  for possession and shielding authorized on the same license.
\9\ Licensees paying fees under 3.N. are not subject to paying fees
  under 3.P. for calibration or leak testing services authorized on the
  same license.
\10\ Licensees paying fees under 7.B. are not subject to paying fees
  under 7.C. for broad scope license licenses issued under parts 30, 35,
  40, and 70 of this chapter for human use of byproduct material, source
  material, and/or special nuclear material, except licenses for
  byproduct material, source material, or special nuclear material in
  sealed sources contained in teletherapy devices authorized on the same
  license.


[71 FR 30747, July 31, 2006, as amended at 75 FR 34235, June 16, 2010; 
76 FR 36797, June 22, 2011; 76 FR 72087, Nov. 22, 2011; 77 FR 35827, 
June 13, 2012; 78 FR 32341, May 29, 2013; 78 FR 39428, July 1, 2013; 78 
FR 54959, Sept. 9, 2013; 79 FR 37145, June 30, 2014; 79 FR 51471, Aug. 
29, 2014; 80 FR 37455, June 30, 2015; 81 FR 41186, June 24, 2016; 82 FR 
30699, June 30, 2017]



Sec. 170.32  Schedule of fees for health and safety, and safeguards 
inspections for materials licenses.

    Materials licensees shall pay inspection fees as set forth in Sec. 
170.31.

[53 FR 52652, Dec. 29, 1988]

                               Enforcement



Sec. 170.41  Failure by applicant or licensee to pay prescribed fees.

    If the Commission determines that an applicant or a licensee has 
failed to pay a prescribed fee required in this part, the Commission 
will not process any application and may suspend or revoke any license 
or approval issued to

[[Page 852]]

the applicant or licensee. The Commission may issue an order with 
respect to licensed activities that the Commission determines to be 
appropriate or necessary to carry out the provisions of this part, parts 
30, 31, 32 through 35, 40, 50, 61, 70, 71, 72, 73, and 76 of this 
chapter, and of the act.

[66 FR 32474, June 14, 2001]



Sec. 170.51  Right to review and appeal of prescribed fees.

    All debtors' requests for review of the fees assessed and appeal or 
disagreement with the prescribed fee (staff hours and contractual) must 
be submitted in accordance with the provisions of 10 CFR 15.31, 
``Disputed Debts,'' of this title.

[49 FR 21309, May 21, 1984; 49 FR 24113, June 12, 1984]



 PART 171_ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES
 AND MATERIALS LICENSES, INCLUDING HOLDERS OF CERTIFICATES OF 
 COMPLIANCE, REGISTRATIONS, AND QUALITY ASSURANCE PROGRAM APPROVALS
 AND GOVERNMENT AGENCIES LICENSED BY THE NRC--Table of Contents



Sec.
171.1 Purpose.
171.3 Scope.
171.5 Definitions.
171.7 Interpretations.
171.8 Information collection requirements: OMB approval.
171.9 Communications.
171.11 Exemptions.
171.13 Notice.
171.15 Annual fees: Reactor licenses and independent spent fuel storage 
          licenses.
171.16 Annual fees: Materials licensees, holders of certificates of 
          compliance, holders of sealed source and device registrations, 
          holders of quality assurance program approvals, and government 
          agencies licensed by the NRC.
171.17 Proration.
171.19 Payment.
171.21 [Reserved]
171.23 Enforcement.
171.25 Collection, interest, penalties, and administrative costs.


    Authority: Atomic Energy Act of 1954, secs. 11, 161(w), 223, 234 (42 
U.S.C. 2014, 2201(w), 2273, 2282); Energy Reorganization Act of 1974, 
sec. 201 (42 U.S.C. 5841); 42 U.S.C. 2214; 44 U.S.C. 3504 note.

    Source: 51 FR 33230, Sept. 18, 1986, unless otherwise noted.



Sec. 171.1  Purpose.

    The regulations in this part set out the annual fees charged to 
persons who hold licenses, Certificates of Compliance, sealed source and 
device registrations, and quality assurance program approvals issued by 
the United States Nuclear Regulatory Commission, including licenses, 
registrations, approvals, and certificates issued to a Government 
agency.

[56 FR 31504, July 10, 1991]



Sec. 171.3  Scope.

    The regulations in this part apply to any person holding an 
operating license for a power reactor, test reactor or research reactor 
issued under part 50 of this chapter and to any person holding a 
combined license issued under part 52 of this chapter that authorizes 
operation of a power reactor. The regulations in this part also apply to 
any person holding a materials license as defined in this part, a 
Certificate of Compliance, a sealed source or device registration, a 
quality assurance program approval, and to a Government agency as 
defined in this part. Notwithstanding the other provisions in this 
section, the regulations in this part do not apply to uranium enrichment 
facilities until after the Commission verifies through inspection that 
the facility has been constructed in accordance with the requirements of 
the license, as required in 10 CFR parts 40 and 70.

[72 FR 31426, June 6, 2007]



Sec. 171.5  Definitions.

    Budget means the funds appropriated by Congress for the NRC for each 
fiscal year, and if that appropriation is not passed on or before 
September 1 for that fiscal year, the funds most recently appropriated 
by Congress for the most recent fiscal year.

[[Page 853]]

    Budget authority means the authority, in the form of appropriations, 
provided by law and becoming available during the year, to enter into 
obligations that will result in immediate or future outlays involving 
Federal government funds. The appropriation is an authorization by an 
Act of Congress that permits the NRC to incur obligations and to make 
payments out of the Treasury for specified purposes. Fees assessed 
pursuant to Public Law 101-508 are based on NRC budget authority.
    Bundled unit means the cumulative licensed thermal power rating of a 
number of SMR reactors on the same site that, for 10 CFR part 171 
purposes only, is considered a single fee unit. The maximum capacity of 
a bundled unit is 4,500 MWt. A single SMR reactor can be part of two 
bundled units if it completes the capacity of one unit and begins the 
capacity of an additional unit. For a given site, the use of the bundled 
unit concept is independent of the number of SMR plants, the number of 
SMR licenses issued, or the sequencing of the SMR licenses that have 
been issued. The first bundled unit on a site is assessed a minimum fee 
for capacity less than or equal to 250 MWt, plus a variable fee for 
capacity greater than 250 MWt and less than or equal to 2,000 MWt. 
Bundled units with capacities greater than 2,000 MWt and less than or 
equal to 4,500 MWt are assessed a maximum fee that is equivalent to the 
annual fee paid by the current reactor fleet. The maximum fee replaces 
the minimum and variable fee for the first bundled unit. Each additional 
increment of 4,500 MWt of SMR capacity on the same site constitutes an 
additional bundled unit. No minimum fee is assessed to additional 
bundled units. For any additional bundled unit, a variable fee applies 
to capacities less than or equal to 2,000 MWt and the maximum fee 
applies to capacities greater than 2,000 MWt and less than or equal to 
4,500 MWT. For additional bundled units, the maximum fee replaces the 
variable fee.
    Byproduct material means--
    (1) Any radioactive material (except special nuclear material) 
yielded in, or made radioactive by, exposure to the radiation incident 
to the process of producing or using special nuclear material;
    (2)(i) Any discrete source of radium-226 that is produced, 
extracted, or converted after extraction, before, on, or after August 8, 
2005, for use for a commercial, medical, or research activity; or
    (ii) Any material that--
    (A) Has been made radioactive by use of a particle accelerator; and
    (B) Is produced, extracted, or converted after extraction, before, 
on, or after August 8, 2005, for use for a commercial, medical, or 
research activity; and
    (3) Any discrete source of naturally occurring radioactive material, 
other than source material, that--
    (i) The Commission, in consultation with the Administrator of the 
Environmental Protection Agency, the Secretary of Energy, the Secretary 
of Homeland Security, and the head of any other appropriate Federal 
agency, determines would pose a threat similar to the threat posed by a 
discrete source of radium-226 to the public health and safety or the 
common defense and security; and
    (ii) Before, on, or after August 8, 2005, is extracted or converted 
after extraction for use in a commercial, medical, or research activity.
    Certificate holder means a person who holds a certificate of 
compliance, or other package approval issued by the Commission.
    Commission means the U.S. Nuclear Regulatory Commission or its duly 
authorized representatives.
    Federal fiscal year means a year that begins on October 1 of each 
calendar year and ends on September 30 of the following calendar year. 
Federal fiscal years are identified by the year in which they end (e.g., 
fiscal year 1987 begins in 1986 and ends in 1987).
    Government agency means any executive department, commission, 
independent establishment, corporation, wholly or partly owned by the 
United States of America which is an instrumentality of the United 
States, or any board, bureau, division, service, office, officer, 
authority, administration, or other establishment in the executive 
branch of the government.

[[Page 854]]

    Greater Than Class C Waste or GTCC Waste means low-level radioactive 
waste that exceeds the concentration limits of radionuclides established 
for Class C waste in 10 CFR 61.55.
    High enriched uranium fuel means uranium enriched to 20 percent or 
greater in the isotope uranium-235.
    Low enriched uranium fuel means uranium enriched below 20 percent in 
the isotope uranium-235.
    Materials license means a license, certificate, approval, 
registration or other form of permission issued or granted by the NRC 
under the regulations in 10 CFR parts 30, 31 through 36, 39, 40, 61, 70, 
71, 72, and 76.
    Maximum fee is the highest fee paid by a single bundled unit. It is 
applied to all bundled units on an SMR site with a licensed thermal 
power rating greater than 2,000 MWt and less than or equal to 4,500 MWt 
and is equal to the flat annual fee paid by existing fleet power 
reactors.
    Minimum fee means one annual fee component paid by the first bundled 
unit on a site with a cumulative licensed thermal power rating of 2,000 
MWt or less. For the first bundled unit on a site with a licensed 
thermal power rating of 250 MWt or less, it is the only annual fee that 
a licensee pays.
    Nonprofit educational institution means a public or nonprofit 
educational institution whose primary function is education, whose 
programs are accredited by a nationally recognized accrediting agency or 
association, who is legally authorized to provide a program of organized 
instruction or study, who provides an educational program for which it 
awards academic degrees, and whose educational programs are available to 
the public.
    Nuclear reactor means an apparatus, other than an atomic weapon, 
used to sustain fission in a self-supporting chain reaction.
    Operating license means having a license issued pursuant to Sec. 
50.57 of this chapter. It does not include licenses that only authorize 
possession of special nuclear material after the Commission has received 
a request from the licensee to amend its licensee to permanently 
withdraw its authority to operate or the Commission has permanently 
revoked such authority.
    Overhead and general and administrative costs means:
    (1) The Government benefits for each employee such as leave and 
holidays, retirement and disability benefits, health and life insurance 
costs, and social security costs;
    (2) Travel costs;
    (3) Direct overhead [e.g., supervision and support staff that 
directly support the NRC safety mission areas; administrative support 
costs (e.g., rental of space, equipment, telecommunications and 
supplies)]; and
    (4) Indirect costs that would include, but not be limited to, NRC 
central policy direction, legal and executive management services for 
the Commission and special and independent reviews, investigations, and 
enforcement and appraisal of NRC programs and operations. Some of the 
organizations included, in whole or in part, are the Commissioners, 
Secretary, Executive Director for Operations, General Counsel, 
Congressional and Public Affairs (except for international safety and 
safeguards programs), Inspector General, Investigations, Enforcement, 
Small and Disadvantaged Business Utilization and Civil Rights, the 
Technical Training Center, Advisory Committees on Nuclear Waste and 
Reactor Safeguards, and the Atomic Safety and Licensing Board Panel. The 
Commission views these budgeted costs as support for all its regulatory 
services provided to applicants, licensees, and certificate holders, and 
these costs must be recovered under Public Law 101-508.
    Person means:
    (1) Any individual, corporation, partnership, firm, association, 
trust, estate, public or private institution, group, Government agency 
other than the Commission; any state or any political subdivision of, or 
any political entity within, a state; any foreign Government or nation 
or any political subdivision of any such government or nation; or other 
entity; and
    (2) Any legal successor, representative, agent, or agency of the 
foregoing.
    Power reactor means a nuclear reactor designed to produce electrical 
or heat energy and licensed by the Commission under the authority of 
section 103 or subsection 104b of the Atomic Energy Act of 1954, as 
amended, and pursuant

[[Page 855]]

to the provisions of Sec. 50.21(b) or Sec. 50.22 of this chapter.
    Quality assurance program approval is the document issued by the NRC 
to approve the quality assurance program submitted to the NRC as meeting 
the requirements of Sec. 71.101 of this chapter. Activities covered by 
the quality assurance program may be divided into two major groups: 
those activities including design, fabrication and use of packaging and 
those activities for use only of packaging.
    Registration holder as used in this part means any manufacturer or 
initial distributor of a sealed source or device containing a sealed 
source that holds a certificate of registration issued by the NRC or a 
holder of a registration for a sealed source or device manufactured in 
accordance with the unique specifications of, and for use by, a single 
applicant.
    Research reactor means a nuclear reactor licensed by the Commission 
under the authority of subsection 104c of the Act and pursuant to the 
provisions of Sec. 50.21(c) of this chapter for operation at a thermal 
power level of 10 megawatts or less, and which is not a testing facility 
as defined in this section.
    Small modular reactor (SMR) for the purposes of calculating fees, 
means the class of light-water power reactors having a licensed thermal 
power rating less than or equal to 1,000 MWt per module. This rating is 
based on the thermal power equivalent of a light-water SMR with an 
electrical power generating capacity of 300 MWe or less per module.
    Small modular reactor site (SMR site) is the geographically bounded 
location of one or more SMRs and a basis on which SMR fees are 
calculated.
    Source material means:
    (1) Uranium or thorium, or any combination thereof, in any physical 
or chemical form; or
    (2) Ores which contain by weight one-twentieth of one percent 
(0.05%) or more of
    (i) Uranium,
    (ii) Thorium, or
    (iii) Any combination thereof.
    Source material does not include special nuclear material.
    Special nuclear material means:
    (1) Plutonium, uranium-233, uranium enriched in the isotope 233 or 
in the isotope 235, and any other material which the Commission, 
pursuant to the provisions of section 51 of the Atomic Energy Act of 
1954, as amended, determines to be special nuclear material, but does 
not include source material; or
    (2) Any material artificially enriched by any of the foregoing, but 
does not include source material.
    Testing facility means a nuclear reactor licensed by the Commission 
under the authority of subsection 104c of the Act and pursuant to the 
provisions of Sec. 50.21(c) of this chapter for operation at:
    (1) A thermal power level in excess of 10 megawatts; or
    (2) A thermal power level in excess of 1 megawatt, if the reactor is 
to contain:
    (i) A circulating loop through the core in which the applicant 
proposes to conduct fuel experiments; or
    (ii) A liquid fuel loading; or
    (iii) An experimental facility in the core in excess of 16 square 
inches in cross-section.
    Variable fee means the annual fee component paid by the first 
bundled unit on a site with a licensed thermal power rating greater than 
250 MWt and less than or equal to 2,000 MWt; or the annual fee component 
paid by additional bundled units on a site that have a licensed thermal 
power rating of less than or equal to 2,000 MWt. The variable fee is the 
product of the bundled unit thermal power capacity (in the applicable 
range) and the variable rate.
    Variable rate means a per-MWt fee factor applied to all bundled 
units on site with a licensed thermal power rating less than or equal to 
2,000 MWt. For the first bundled unit on a site with a licensed thermal 
power rating greater than 250 MWt and less than or equal to 2,000 MWt, 
the variable rate is based on the difference between the maximum fee and 
the minimum fee, divided by 1,750 MWt (the variable fee licensed thermal 
rating range). For additional bundled units with a licensed thermal 
power rating less than or equal to 2,000

[[Page 856]]

MWt, the variable rate is based on the maximum fee divided by 2,000 MWt.

[51 FR 33230, Sept. 18, 1986, as amended at 53 FR 52652, Dec. 29, 1988; 
56 FR 31505, July 10, 1991; 57 FR 32714, July 23, 1992; 58 FR 38695, 
July 20, 1993; 65 FR 36964, June 12, 2000; 66 FR 32474, June 14, 2001; 
67 FR 42634, June 24, 2002; 71 FR 30752, May 30, 2006; 72 FR 35936, Oct. 
1, 2007; 81 FR 32627, May 24, 2016; 81 FR 45964, July 15, 2016]



Sec. 171.7  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the regulations in this part by an officer or employee 
of the Commission, other than a written interpretation by the General 
Counsel, will be recognized as binding on the Commission.



Sec. 171.8  Information collection requirements: OMB approval

    This part contains no information collection requirements and 
therefore is not subject to the requirements of the Paperwork Reduction 
Act (44 U.S.C. 3501 et seq.).

[62 FR 52191, Oct. 6, 1997]



Sec. 171.9  Communications.

    All communications concerning the regulations in this part should be 
addressed to the NRC's Chief Financial Officer, either by mail to the 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand 
delivery to the NRC's offices at 11555 Rockville Pike, Rockville, 
Maryland; or, where practicable, by electronic submission, for example, 
via Electronic Information Exchange, or CD-ROM. Electronic submissions 
must be made in a manner that enables the NRC to receive, read, 
authenticate, distribute, and archive the submission, and process and 
retrieve it a single page at a time. Detailed guidance on making 
electronic submissions can be obtained by visiting the NRC's Web site at 
http://www.nrc.gov/site-help/e-submittals.html; by e-mail to 
[email protected]; or by writing the Office of the Chief Information 
Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
The guidance discusses, among other topics, the formats the NRC can 
accept, the use of electronic signatures, and the treatment of nonpublic 
information.

[68 FR 58826, Oct. 10, 2003, as amended at 74 FR 62687, Dec. 1, 2009; 80 
FR 74982, Dec. 1, 2015]



Sec. 171.11  Exemptions.

    (a) All requests for exemptions must be filed with the NRC within 90 
days from the effective date of the final rule establishing the annual 
fees for which the exemption is sought in order to be considered. Absent 
extraordinary circumstances, any exemption requests filed beyond that 
date will not be considered. The filing of an exemption request does not 
extend the date on which the bill is payable. Only timely payment in 
full ensures avoidance of interest and penalty charges. If a partial or 
full exemption is granted, any overpayment will be refunded. Requests 
for clarification of or questions relating to an annual fee bill must 
also be filed within 90 days from the date of the initial invoice to be 
considered.
    (b) An annual fee is not required for:
    (1) A construction permit or license applied for by, or issued to, a 
nonprofit educational institution for a production or utilization 
facility, other than a power reactor, or for the possession and use of 
byproduct material, source material, or special nuclear material. This 
exemption does not apply to those byproduct, source, or special nuclear 
material licenses which authorize:
    (i) Human use;
    (ii) Remunerated services to other persons;
    (iii) Distribution of byproduct material, source material, or 
special nuclear material or products containing byproduct material, 
source material, or special nuclear material; or
    (iv) Activities performed under a Government contract.
    (2) Federally-owned and State-owned research reactors used primarily 
for educational training and academic research purposes. For purposes of 
this exemption, the term research reactor means a nuclear reactor that--
    (i) Is licensed by the Nuclear Regulatory Commission under section 
104c. of the Atomic Energy Act of 1954 (42 U.S.C. 2134(c)) for operation 
at a thermal power level of 10 megawatts or less; and

[[Page 857]]

    (ii) If so licensed for operation at a thermal power level of more 
than 1 megawatt, does not contain--
    (A) A circulating loop through the core in which the licensee 
conducts fuel experiments;
    (B) A liquid fuel loading; or
    (C) An experimental facility in the core in excess of 16 square 
inches in cross-section.
    (c) The Commission may, upon application by an interested person or 
on its own initiative, grant an exemption from the requirements of this 
part that it determines is authorized by law or otherwise in the public 
interest.
    (d) An exemption for reactors licensed to operate may be granted by 
the Commission taking into consideration each of the following factors:
    (1) Age of the reactor;
    (2) Number of customers in rate base;
    (3) Net increase in KWh cost for each customer directly related to 
the annual fee assessed under this part; and
    (4) Any other relevant matter which the licensee believes justifies 
the reduction of the annual fee.
    (e) The Commission may grant a materials licensee an exemption from 
the annual fee if it determines that the annual fee is not based on a 
fair and equitable allocation of the NRC costs. The following factors 
must be fulfilled as determined by the Commission for an exemption to be 
granted:
    (1) There are data specifically indicating that the assessment of 
the annual fee will result in a significantly disproportionate 
allocation of costs to the licensee, or class of licensees; or
    (2) There is clear and convincing evidence that the budgeted generic 
costs attributable to the class of licensees are neither directly or 
indirectly related to the specific class of licensee nor explicitly 
allocated to the licensee by Commission policy decisions; or
    (3) Any other relevant matter that the licensee believes shows that 
the annual fee was not based on a fair and equitable allocation of NRC 
costs.

[56 FR 31505, July 10, 1991, as amended at 57 FR 32714, July 23, 1992; 
58 FR 38695, July 20, 1993; 59 FR 12543, Mar. 17, 1994; 59 FR 36924, 
July 20, 1994; 67 FR 42634, June 24, 2002; 70 FR 30548, May 29, 2005; 79 
FR 37150, June 30, 2014]



Sec. 171.13  Notice.

    The annual fees applicable to any NRC licensee subject to this part 
and calculated in accordance with Sec. Sec. 171.15 and 171.16, will be 
published as a notice in the Federal Register as soon as possible but no 
later than the third quarter of the fiscal year. The annual fees will 
become due and payable to the NRC as indicated in Sec. 171.19. 
Quarterly payments of the annual fee of $100,000 or more will continue 
during the fiscal year and be based on the applicable annual fees as 
shown in Sec. Sec. 171.15 and 171.16 until a notice concerning the 
revised amount of the fees for the fiscal year is published by the NRC. 
If the NRC is unable to publish a final fee rule that becomes effective 
during the current fiscal year, fees would be assessed based on the 
rates in effect for the previous fiscal year.

[64 FR 31475, June 10, 1999]



Sec. 171.15  Annual fees: Reactor licenses and independent spent fuel 
storage licenses.

    (a) Each person holding an operating license for a power, test, or 
research reactor; each person holding a combined license under part 52 
of this chapter after the Commission has made the finding under 10 CFR 
52.103(g); each person holding a part 50 or part 52 power reactor 
license that is in decommissioning or possession only status, except 
those that have no spent fuel onsite; and each person holding a part 72 
license who does not hold a part 50 or part 52 license and provides 
notification in accordance with 10 CFR 72.80(g), shall pay the annual 
fee for each license held during the Federal fiscal year in which the 
fee is due. This paragraph does not apply to test or research reactors 
exempted under Sec. 171.11(a).
    (b)(1) The FY 2017 annual fee for each operating power reactor which 
must be collected by September 30, 2017, is $4,496,000.
    (2) The FY 2017 annual fees are comprised of a base annual fee for 
power reactors licensed to operate, a base spent fuel storage/reactor 
decommissioning annual fee, and associated additional charges (fee-
relief adjustment). The activities comprising the spent storage/

[[Page 858]]

reactor decommissioning base annual fee are shown in paragraphs 
(c)(2)(i) and (ii) of this section. The activities comprising the FY 
2017 fee-relief adjustment are shown in paragraph (d)(1) of this 
section. The activities comprising the FY 2017 base annual fee for 
operating power reactors are as follows:
    (i) Power reactor safety and safeguards regulation except licensing 
and inspection activities recovered under part 170 of this chapter and 
generic reactor decommissioning activities.
    (ii) Research activities directly related to the regulation of power 
reactors, except those activities specifically related to reactor 
decommissioning.
    (iii) Generic activities required largely for NRC to regulate power 
reactors (e.g., updating part 50 or 52 of this chapter, operating the 
Incident Response Center, new reactor regulatory infrastructure). The 
base annual fee for operating power reactors does not include generic 
activities specifically related to reactor decommissioning.
    (c)(1) The FY 2017 annual fee for each power reactor holding a 10 
CFR part 50 license that is in a decommissioning or possession-only 
status and has spent fuel onsite, and for each independent spent fuel 
storage 10 CFR part 72 licensee who does not hold a 10 CFR part 50 
license, is $188,000.
    (2) The FY 2017 annual fee is comprised of a base spent fuel 
storage/reactor decommissioning annual fee (which is also included in 
the operating power reactor annual fee shown in paragraph (b) of this 
section) and a fee-relief adjustment. The activities comprising the FY 
2017 fee-relief adjustment are shown in paragraph (d)(1) of this 
section. The activities comprising the FY 2017 spent fuel storage/
reactor decommissioning re-baselined annual fee are:
    (i) Generic and other research activities directly related to 
reactor decommissioning and spent fuel storage; and
    (ii) Other safety, environmental, and safeguards activities related 
to reactor decommissioning and spent fuel storage, except costs for 
licensing and inspection activities that are recovered under part 170 of 
this chapter.
    (d)(1) The fee-relief adjustment allocated to annual fees includes a 
surcharge for the activities listed in paragraph (d)(1)(i) of this 
section, plus the amount remaining after total budgeted resources for 
the activities included in paragraphs (d)(1)(ii) and (iii) of this 
section are reduced by the appropriations the NRC receives for these 
types of activities. If the NRC's appropriations for these types of 
activities are greater than the budgeted resources for the activities 
included in paragraphs (d)(1)(ii) and (iii) of this section for a given 
fiscal year, annual fees will be reduced. The activities comprising the 
FY 2017 fee-relief adjustment are as follows:
    (i) Low-level waste disposal generic activities;
    (ii) Activities not attributable to an existing NRC licensee or 
class of licenses (e.g., international cooperative safety program and 
international safeguards activities, support for the Agreement State 
program); and
    (iii) Activities not currently subject to 10 CFR part 170 licensing 
and inspection fees based on existing law or Commission policy (e.g., 
reviews and inspections conducted of nonprofit educational institutions, 
costs that would not be collected from small entities based on 
Commission policy in accordance with the Regulatory Flexibility Act, 5 
U.S.C. 601 et seq., regulatory support for Agreement States, generic 
decommissioning/reclamation activities for fee classes other than power 
reactors and spent fuel storage/reactor decommissioning, the in-situ 
leach rulemaking, activities for unregistered general licensees).
    (2) The total FY 2017 fee-relief adjustment allocated to the 
operating power reactor class of licenses is an $11,074,000 fee-relief 
surcharge, not including the amount allocated to the spent fuel storage/
reactor decommissioning class. The FY 2017 operating power reactor fee-
relief adjustment to be assessed to each operating power reactor is 
approximately a $111,863 fee-relief surcharge. This amount is calculated 
by dividing the total operating power reactor fee-relief surplus 
adjustment, $11,074,000, by the number of operating power reactors (99).
    (3) The FY 2017 fee-relief adjustment allocated to the spent fuel 
storage/reactor decommissioning class of licenses

[[Page 859]]

is a $467,500 fee-relief assessment. The FY 2017 spent fuel storage/
reactor decommissioning fee-relief adjustment to be assessed to each 
operating power reactor, each power reactor in decommissioning or 
possession-only status that has spent fuel onsite, and to each 
independent spent fuel storage 10 CFR part 72 licensee who does not hold 
a 10 CFR part 50 license, is a $3,832 fee-relief assessment. This amount 
is calculated by dividing the total fee-relief adjustment costs 
allocated to this class by the total number of power reactor licenses, 
except those that permanently ceased operations and have no fuel onsite, 
and 10 CFR part 72 licensees who do not hold a 10 CFR part 50 license.
    (e)(1) Each person holding an operating license for an SMR issued 
under 10 CFR part 50 or a combined license issued under 10 CFR part 52 
after the Commission has made the finding under 10 CFR 52.103(g), shall 
pay the annual fee for all licenses held for an SMR site. The annual fee 
will be determined using the cumulative licensed thermal power rating of 
all SMR units and the bundled unit concept, during the fiscal year in 
which the fee is due. For a given site, the use of the bundled unit 
concept is independent of the number of SMR plants, the number of SMR 
licenses issued, or the sequencing of the SMR licenses that have been 
issued.
    (2) The annual fees for a small modular reactor(s) located on a 
single site to be collected by September 30 of each year, are as 
follows:

----------------------------------------------------------------------------------------------------------------
  Bundled unit thermal power rating          Minimum fee              Variable fee             Maximum fee
----------------------------------------------------------------------------------------------------------------
First Bundled Unit
    0 MWt <=250 MWt.................  TBD                       N/A                      N/A
    250 MWt <=2,000 MWt..  TBD                       TBD                      N/A
    2,000 MWt <=4,500 MWt  N/A                       N/A                      TBD
Additional Bundled Units
    0 MWt <=2,000 MWt...............  N/A                       TBD                      N/A
    2,000 MWt <=4,500 MWt  N/A                       N/A                      TBD
----------------------------------------------------------------------------------------------------------------

    (3) The annual fee for an SMR collected under paragraph (e) of this 
section is in lieu of any fee otherwise required under paragraph (b) of 
this section. The annual fee under paragraph (e) of this section covers 
the same activities listed for power reactor base annual fee and spent 
fuel storage/reactor decommissioning reactor fee.
    (f) The FY 2017 annual fees for licensees authorized to operate a 
research or test (non-power) reactor licensed under 10 CFR part 50, 
unless the reactor is exempted from fees under Sec. 171.11(a), are as 
follows:

------------------------------------------------------------------------
 
------------------------------------------------------------------------
Research reactor........................................         $81,400
Test reactor............................................          81,400
------------------------------------------------------------------------


[72 FR 31426, June 6, 2007, as amended at 72 FR 49566, Aug. 28, 2007; 73 
FR 32407, June 6, 2008; 74 FR 27665, June 10, 2009; 75 FR 34240, June 
16, 2010; 76 FR 36802, June 22, 2011; 77 FR 35831, June 15, 2012; 78 FR 
39487, July 1, 2013; 79 FR 37150, June 30, 2014; 80 FR 37460, June 30, 
2015; 81 FR 32628, May 24, 2016; 81 FR 45964, July 15, 2016; 81 FR 
41192, June 24, 2016; 82 FR 30704, June 30, 2017]



Sec. 171.16  Annual fees: Materials licensees, holders of certificates 
of compliance, holders of sealed source and device registrations, 
holders of quality assurance program approvals, and government 
agencies licensed by the NRC.

    (a)(1) The provisions of this section apply to person(s) who are 
authorized to conduct activities under--
    (i) 10 CFR part 30 for byproduct material;
    (ii) 10 CFR part 40 for source material;
    (iii) 10 CFR part 70 for special nuclear material;
    (iv) 10 CFR part 71 for packaging and transportation of radioactive 
material; and
    (v) 10 CFR part 76 for uranium enrichment.
    (2) Notwithstanding the other provisions in this section, the 
regulations in this part do not apply to uranium enrichment facilities 
until after the Commission verifies through inspection that the facility 
has been constructed in accordance with the requirements of

[[Page 860]]

the license, as required in 10 CFR parts 40 and 70.
    (3) In accordance with Sec. 171.17, each person identified in 
paragraph (a)(1) of this section shall pay the applicable annual fee for 
each license the person holds during the FY. Annual fees will be 
prorated for new licenses issued and for licenses for which termination 
is requested and activities permanently ceased during the FY as provided 
in Sec. 171.17. If a single license authorizes more than one activity 
(e.g., human use and irradiator activities), annual fees will be 
assessed for each fee category applicable to the license. If a person 
holds more than one license, the total annual fee assessed will be the 
cumulative total of the annual fees applicable to each license held.
    (b) The annual fee is comprised of a base annual fee and an 
allocation for fee-relief adjustment. The activities comprising the fee-
relief adjustment are shown in paragraph (e) of this section. The base 
annual fee is the sum of budgeted costs for the following activities:
    (1) Generic and other research activities directly related to the 
regulation of materials licenses as defined in this part; and
    (2) Other safety, environmental, and safeguards activities for 
materials licenses, except costs for licensing and inspection activities 
that are recovered under Part 170 of this chapter.
    (c) A licensee who is required to pay an annual fee under this 
section, in addition to 10 CFR part 72 licenses, may qualify as a small 
entity. If a licensee qualifies as a small entity and provides the 
Commission with the proper certification along with its annual fee 
payment, the licensee may pay reduced annual fees as shown in the 
following table. Failure to file a small entity certification in a 
timely manner could result in the receipt of a delinquent invoice 
requesting the outstanding balance due and/or denial of any refund that 
might otherwise be due. The small entity fees are as follows:

------------------------------------------------------------------------
                                                          Maximum annual
                                                              fee per
                                                             licensed
                                                             category
------------------------------------------------------------------------
Small Businesses Not Engaged in Manufacturing (Average
 gross receipts over last 3 completed fiscal years):
    $485,000 to $7 million..............................          $4,100
    Less than $485,000..................................             850
Small Not-For-Profit Organizations (Annual Gross
 Receipts):
    $485,000 to $7 million..............................           4,100
    Less than $485,000..................................             850
Manufacturing Entities that Have An Average of 500
 Employees or Fewer:
    35 to 500 employees.................................           4,100
Fewer than 35 employees.................................             850
Small Governmental Jurisdictions (Including publicly
 supported educational institutions) (Population):
    20,000 to 49,999....................................           4,100
    Fewer than 20,000...................................             850
Educational Institutions that are not State or Publicly
 Supported, and have 500 Employees or Fewer
    35 to 500 employees.................................           4,100
    Fewer than 35 employees.............................             850
------------------------------------------------------------------------

    (d) The FY 2017 annual fees are comprised of a base annual fee and 
an allocation for fee-relief adjustment. The activities comprising the 
FY 2017 fee-relief adjustment are shown for convenience in paragraph (e) 
of this section. The FY 2017 annual fees for materials licensees and 
holders of certificates, registrations, or approvals subject to fees 
under this section are shown in the following table:

   Schedule of Materials Annual Fees and Fees for Government Agencies
                             Licensed by NRC
                     [See footnotes at end of table]
------------------------------------------------------------------------
                                                           Annual fees 1
             Category of materials licenses                     2 3
------------------------------------------------------------------------
1. Special nuclear material:
    A. (1) Licenses for possession and use of U-235 or
     plutonium for fuel fabrication activities

[[Page 861]]

 
        (a) Strategic Special Nuclear Material (High          $7,255,000
         Enriched Uranium) [Program Code(s): 21213].....
        (b) Low Enriched Uranium in Dispersible Form           2,629,000
         Used for Fabrication of Power Reactor Fuel
         [Program Code(s): 21210].......................
    (2) All other special nuclear materials licenses not
     included in Category 1.A.(1) which are licensed for
     fuel cycle activities
        (a) Facilities with limited operations [Program               $0
         Code(s): 21240, 21310, 21320]..................
        (b) Gas centrifuge enrichment demonstration            1,366,000
         facilities [Program Code(s): 21205]............
        (c) Others, including hot cell facilities                710,000
         [Program Code(s): 21130, 21133]................
    B. Licenses for receipt and storage of spent fuel           \11\ N/A
     and reactor-related Greater than Class C (GTCC)
     waste at an independent spent fuel storage
     installation (ISFSI) [Program Code(s): 23200]......
    C. Licenses for possession and use of special                  3,000
     nuclear material of less than a critical mass, as
     defined in Sec. 70.4 of this chapter, in sealed
     sources contained in devices used in industrial
     measuring systems, including x-ray fluorescence
     analyzers.\15\ [Program Code(s): 22140]............
    D. All other special nuclear material licenses,                8,600
     except licenses authorizing special nuclear
     material in sealed or unsealed form in combination
     that would constitute a critical mass, as defined
     in Sec. 70.4 of this chapter, for which the
     licensee shall pay the same fees as those under
     Category 1.A.\15\ [Program Code(s): 22110, 22111,
     22120, 22131, 22136, 22150, 22151, 22161, 22170,
     23100, 23300, 23310]...............................
    E. Licenses or certificates for the operation of a         3,470,000
     uranium enrichment facility [Program Code(s):
     21200].............................................
    F. Licenses for possession and use of special                  6,400
     nuclear material greater than critical mass, as
     defined in Sec. 70.4 of this chapter, for
     development and testing of commercial products, and
     other non-fuel-cycle activities.\15\ [Program Code:
     22155].............................................
2. Source material:
    A. (1) Licenses for possession and use of source           1,498,000
     material for refining uranium mill concentrates to
     uranium hexafluoride or for deconverting uranium
     hexafluoride in the production of uranium oxides
     for disposal. [Program Code: 11400]................
    (2) Licenses for possession and use of source
     material in recovery operations such as milling, in-
     situ recovery, heap-leaching, ore buying stations,
     ion-exchange facilities and in-processing of ores
     containing source material for extraction of metals
     other than uranium or thorium, including licenses
     authorizing the possession of byproduct waste
     material (tailings) from source material recovery
     operations, as well as licenses authorizing the
     possession and maintenance of a facility in a
     standby mode
        (a) Conventional and Heap Leach facilities                38,900
         [Program Code(s): 11100].......................
        (b) Basic In Situ Recovery facilities [Program            49,200
         Code(s): 11500]................................
        (c) Expanded In Situ Recovery facilities                  55,700
         [Program Code(s): 11510].......................
        (d) In Situ Recovery Resin facilities [Program           \5\ N/A
         Code(s): 11550]................................
        (e) Resin Toll Milling facilities [Program               \5\ N/A
         Code(s): 11555]................................
    (3) Licenses that authorize the receipt of byproduct         \5\ N/A
     material, as defined in Section 11e.(2) of the
     Atomic Energy Act, from other persons for
     possession and disposal, except those licenses
     subject to the fees in Category 2.A.(2) or Category
     2.A.(4) [Program Code(s): 11600, 12000]............
    (4) Licenses that authorize the receipt of byproduct          22,000
     material, as defined in Section 11e.(2) of the
     Atomic Energy Act, from other persons for
     possession and disposal incidental to the disposal
     of the uranium waste tailings generated by the
     licensee's milling operations, except those
     licenses subject to the fees in Category 2.A.(2)
     [Program Code(s): 12010]...........................
    (5) Licenses that authorize the possession of source           6,500
     material related to removal of contaminants (source
     material) from drinking water [Program Code(s):
     11820].............................................
    B. Licenses that authorize possession, use, and/or             3,300
     installation of source material for shielding.16 17
     18 [Program Code: 11210]...........................
    C. Licenses to distribute items containing source              5,500
     material to persons exempt from the licensing
     requirements of part 40 of this chapter. [Program
     Code: 11240].......................................
    D. Licenses to distribute source material to persons           6,400
     generally licensed under part 40 of this chapter
     [Program Code(s): 11230 and 11231].................
    E. Licenses for possession and use of source                   8,000
     material for processing or manufacturing of
     products or materials containing source material
     for commercial distribution. [Program Code: 11710].
    F. All other source material licenses. [Program                9,400
     Code(s): 11200, 11220, 11221, 11300, 11800, 11810].
3. Byproduct material:
    A. Licenses of broad scope for possession and use of          30,500
     byproduct material issued under parts 30 and 33 of
     this chapter for processing or manufacturing of
     items containing byproduct material for commercial
     distribution [Program Code(s): 03211, 03212, 03213]
    B. Other licenses for possession and use of                   11,600
     byproduct material issued under part 30 of this
     chapter for processing or manufacturing of items
     containing byproduct material for commercial
     distribution [Program Code(s): 03214, 03215, 22135,
     22162].............................................
    C. Licenses issued under Sec. Sec. 32.72 and/or            12,900
     32.74 of this chapter authorizing the processing or
     manufacturing and distribution or redistribution of
     radiopharmaceuticals, generators, reagent kits, and/
     or sources and devices containing byproduct
     material. This category also includes the
     possession and use of source material for shielding
     authorized under part 40 of this chapter when
     included on the same license. This category does
     not apply to licenses issued to nonprofit
     educational institutions whose processing or
     manufacturing is exempt under Sec. 171.11(a)(1).
     [Program Code(s): 02500, 02511, 02513].............

[[Page 862]]

 
    D. [Reserved].......................................         \5\ N/A
    E. Licenses for possession and use of byproduct               10,800
     material in sealed sources for irradiation of
     materials in which the source is not removed from
     its shield (self-shielded units) [Program Code(s):
     03510, 03520]......................................
    F. Licenses for possession and use of less than or            11,800
     equal to 10,000 curies of byproduct material in
     sealed sources for irradiation of materials in
     which the source is exposed for irradiation
     purposes. This category also includes underwater
     irradiators for irradiation of materials in which
     the source is not exposed for irradiation purposes
     [Program Code(s): 03511]...........................
    G. Licenses for possession and use of greater than            95,700
     10,000 curies of byproduct material in sealed
     sources for irradiation of materials in which the
     source is exposed for irradiation purposes. This
     category also includes underwater irradiators for
     irradiation of materials in which the source is not
     exposed for irradiation purposes [Program Code(s):
     03521].............................................
    H. Licenses issued under subpart A of part 32 of              11,800
     this chapter to distribute items containing
     byproduct material that require device review to
     persons exempt from the licensing requirements of
     part 30 of this chapter, except specific licenses
     authorizing redistribution of items that have been
     authorized for distribution to persons exempt from
     the licensing requirements of part 30 of this
     chapter [Program Code(s): 03254, 03255, 03257].....
    I. Licenses issued under subpart A of part 32 of              16,300
     this chapter to distribute items containing
     byproduct material or quantities of byproduct
     material that do not require device evaluation to
     persons exempt from the licensing requirements of
     part 30 of this chapter, except for specific
     licenses authorizing redistribution of items that
     have been authorized for distribution to persons
     exempt from the licensing requirements of part 30
     of this chapter [Program Code(s): 03250, 03251,
     03252, 03253, 03256]...............................
    J. Licenses issued under subpart B of part 32 of               4,600
     this chapter to distribute items containing
     byproduct material that require sealed source and/
     or device review to persons generally licensed
     under part 31 of this chapter, except specific
     licenses authorizing redistribution of items that
     have been authorized for distribution to persons
     generally licensed under part 31 of this chapter
     [Program Code(s): 03240, 03241, 03243].............
    K. Licenses issued under subpart B of part 32 of               3,300
     this chapter to distribute items containing
     byproduct material or quantities of byproduct
     material that do not require sealed source and/or
     device review to persons generally licensed under
     part 31 of this chapter, except specific licenses
     authorizing redistribution of items that have been
     authorized for distribution to persons generally
     licensed under part 31 of this chapter [Program
     Code(s): 03242, 03244].............................
    L. Licenses of broad scope for possession and use of          16,300
     byproduct material issued under parts 30 and 33 of
     this chapter for research and development that do
     not authorize commercial distribution. Number of
     locations of use: 1-5. [Program Code(s): 01100,
     01110, 01120, 03610, 03611, 03612, 03613]..........
    (1) Licenses of broad scope for possession and use            25,900
     of product material issued under parts 30 and 33 of
     this chapter for research and development that do
     not authorize commercial distribution. Number of
     locations of use: 6-19. [Program Code(s): 04610,
     04612, 04614, 04616, 04618, 04620, 04622]..........
    (2) Licenses of broad scope for possession and use            32,700
     of byproduct material issued under parts 30 and 33
     of this chapter for research and development that
     do not authorize commercial distribution. Number of
     locations of use: 20 or more. [Program Code(s):
     04611, 04613, 04615, 04617, 04619, 04621, 04623]...
    M. Other licenses for possession and use of                   14,800
     byproduct material issued under part 30 of this
     chapter for research and development that do not
     authorize commercial distribution [Program Code(s):
     03620].............................................
    N. Licenses that authorize services for other                 22,100
     licensees, except: (1) Licenses that authorize only
     calibration and/or leak testing services are
     subject to the fees specified in fee Category 3.P.;
     and (2) Licenses that authorize waste disposal
     services are subject to the fees specified in fee
     categories 4.A., 4.B., and 4.C. [Program Code(s):
     03219, 03225, 03226]...............................
    O. Licenses for possession and use of byproduct               27,000
     material issued under part 34 of this chapter for
     industrial radiography operations. This category
     also includes the possession and use of source
     material for shielding authorized under part 40 of
     this chapter when authorized on the same license
     [Program Code(s): 03310, 03320]....................
    P. All other specific byproduct material licenses,             9,300
     except those in Categories 4.A. through 9.D.\19\
     [Program Code(s): 02400, 02410, 03120, 03121,
     03122, 03123, 03124, 03140, 03130, 03220, 03221,
     03222, 03800, 03810, 22130]........................
    Q. Registration of devices generally licensed under         \13\ N/A
     part 31 of this chapter............................
    R. Possession of items or products containing radium-
     226 identified in 10 CFR 31.12 which exceed the
     number of items or limits specified in that
     section: \14\
    1. Possession of quantities exceeding the number of            7,600
     items or limits in 10 CFR 31.12(a)(4) or (5) but
     less than or equal to 10 times the number of items
     or limits specified [Program Code(s): 02700].......
    2. Possession of quantities exceeding 10 times the             8,000
     number of items or limits specified in 10 CFR
     31.12(a)(4) or (5) [Program Code(s): 02710]........
    S. Licenses for production of accelerator-produced            32,100
     radionuclides [Program Code(s): 03210].............
4. Waste disposal and processing:

[[Page 863]]

 
    A. Licenses specifically authorizing the receipt of          \5\ N/A
     waste byproduct material, source material, or
     special nuclear material from other persons for the
     purpose of contingency storage or commercial land
     disposal by the licensee; or licenses authorizing
     contingency storage of low-level radioactive waste
     at the site of nuclear power reactors; or licenses
     for receipt of waste from other persons for
     incineration or other treatment, packaging of
     resulting waste and residues, and transfer of
     packages to another person authorized to receive or
     dispose of waste material [Program Code(s): 03231,
     03233, 03236, 06100, 06101]........................
    B. Licenses specifically authorizing the receipt of           20,800
     waste byproduct material, source material, or
     special nuclear material from other persons for the
     purpose of packaging or repackaging the material.
     The licensee will dispose of the material by
     transfer to another person authorized to receive or
     dispose of the material [Program Code(s): 03234]...
    C. Licenses specifically authorizing the receipt of           13,900
     prepackaged waste byproduct material, source
     material, or special nuclear material from other
     persons. The licensee will dispose of the material
     by transfer to another person authorized to receive
     or dispose of the material [Program Code(s): 03232]
5. Well logging:
    A. Licenses for possession and use of byproduct               16,000
     material, source material, and/or special nuclear
     material for well logging, well surveys, and tracer
     studies other than field flooding tracer studies
     [Program Code(s): 03110, 03111, 03112].............
    B. Licenses for possession and use of byproduct              \5\ N/A
     material for field flooding tracer studies.
     [Program Code(s): 03113]...........................
6. Nuclear laundries:
    A. Licenses for commercial collection and laundry of          38,500
     items contaminated with byproduct material, source
     material, or special nuclear material [Program
     Code(s): 03218]....................................
7. Medical licenses:
    A. Licenses issued under parts 30, 35, 40, and 70 of          23,800
     this chapter for human use of byproduct material,
     source material, or special nuclear material in
     sealed sources contained in gamma stereotactic
     radiosurgery units, teletherapy devices, or similar
     beam therapy devices. This category also includes
     the possession and use of source material for
     shielding when authorized on the same license.
     [Program Code(s): 02300, 02310]....................
    B. Licenses of broad scope issued to medical                  33,800
     institutions or two or more physicians under parts
     30, 33, 35, 40, and 70 of this chapter authorizing
     research and development, including human use of
     byproduct material, except licenses for byproduct
     material, source material, or special nuclear
     material in sealed sources contained in teletherapy
     devices. This category also includes the possession
     and use of source material for shielding when
     authorized on the same license.\9\ [Program
     Code(s): 02110]....................................
    C. Other licenses issued under parts 30, 35, 40, and          14,700
     70 of this chapter for human use of byproduct
     material, source material, and/or special nuclear
     material, except licenses for byproduct material,
     source material, or special nuclear material in
     sealed sources contained in teletherapy devices.
     This category also includes the possession and use
     of source material for shielding when authorized on
     the same license.9 20 [Program Code(s): 02120,
     02121, 02200, 02201, 02210, 02220, 02230, 02231,
     02240, 22160]......................................
8. Civil defense:
    A. Licenses for possession and use of byproduct                7,600
     material, source material, or special nuclear
     material for civil defense activities [Program
     Code(s): 03710]....................................
9. Device, product, or sealed source safety evaluation:
    A. Registrations issued for the safety evaluation of           7,600
     devices or products containing byproduct material,
     source material, or special nuclear material,
     except reactor fuel devices, for commercial
     distribution.......................................
    B. Registrations issued for the safety evaluation of          12,600
     devices or products containing byproduct material,
     source material, or special nuclear material
     manufactured in accordance with the unique
     specifications of, and for use by, a single
     applicant, except reactor fuel devices.............
    C. Registrations issued for the safety evaluation of           7,400
     sealed sources containing byproduct material,
     source material, or special nuclear material,
     except reactor fuel, for commercial distribution...
    D. Registrations issued for the safety evaluation of           1,500
     sealed sources containing byproduct material,
     source material, or special nuclear material,
     manufactured in accordance with the unique
     specifications of, and for use by, a single
     applicant, except reactor fuel.....................
10. Transportation of radioactive material:
    A. Certificates of Compliance or other package
     approvals issued for design of casks, packages, and
     shipping containers
    1. Spent Fuel, High-Level Waste, and plutonium air           \6\ N/A
     packages...........................................
    2. Other Casks......................................         \6\ N/A
    B. Quality assurance program approvals issued under
     part 71 of this chapter
    1. Users and Fabricators............................         \6\ N/A
    2. Users............................................         \6\ N/A
    C. Evaluation of security plans, route approvals,            \6\ N/A
     route surveys, and transportation security devices
     (including immobilization devices).................
11. Standardized spent fuel facilities..................         \6\ N/A
12. Special Projects [Program Code(s): 25110]...........         \6\ N/A
13. A. Spent fuel storage cask Certificate of Compliance         \6\ N/A

[[Page 864]]

 
    B. General licenses for storage of spent fuel under         \12\ N/A
     10 CFR 72.210......................................
14. Decommissioning/Reclamation:
    A. Byproduct, source, or special nuclear material            \7\ N/A
     licenses and other approvals authorizing
     decommissioning, decontamination, reclamation, or
     site restoration activities under parts 30, 40, 70,
     72, and 76 of this chapter, including master
     materials licenses (MMLs) [Program Code(s): 03900,
     11900, 21135, 21215, 21325, 22200].................
    B. Site-specific decommissioning activities                  \7\ N/A
     associated with unlicensed sites, including MMLs,
     whether or not the sites have been previously
     licensed...........................................
15. Import and Export licenses..........................         \8\ N/A
16. Reciprocity.........................................         \8\ N/A
17. Master materials licenses of broad scope issued to           340,000
 Government agencies [Program Code(s): 03614]...........
18. Department of Energy:
    A. Certificates of Compliance.......................  \10\ 1,514,000
    B. Uranium Mill Tailings Radiation Control Act               616,000
     (UMTRCA) activities................................
------------------------------------------------------------------------
\1\ Annual fees will be assessed based on whether a licensee held a
  valid license with the NRC authorizing possession and use of
  radioactive material during the current FY. The annual fee is waived
  for those materials licenses and holders of certificates,
  registrations, and approvals who either filed for termination of their
  licenses or approvals or filed for possession only/storage licenses
  before October 1, 2015, and permanently ceased licensed activities
  entirely before this date. Annual fees for licensees who filed for
  termination of a license, downgrade of a license, or for a possession-
  only license during the FY and for new licenses issued during the FY
  will be prorated in accordance with the provisions of Sec. 171.17.
  If a person holds more than one license, certificate, registration, or
  approval, the annual fee(s) will be assessed for each license,
  certificate, registration, or approval held by that person. For
  licenses that authorize more than one activity on a single license
  (e.g., human use and irradiator activities), annual fees will be
  assessed for each category applicable to the license.
\2\ Payment of the prescribed annual fee does not automatically renew
  the license, certificate, registration, or approval for which the fee
  is paid. Renewal applications must be filed in accordance with the
  requirements of parts 30, 40, 70, 71, 72, or 76 of this chapter.
\3\ Each FY, fees for these materials licenses will be calculated and
  assessed in accordance with Sec. 171.13 and will be published in the
  Federal Register for notice and comment.
\4\ Other facilities include licenses for extraction of metals, heavy
  metals, and rare earths.
\5\ There are no existing NRC licenses in these fee categories. If NRC
  issues a license for these categories, the Commission will consider
  establishing an annual fee for this type of license.
\6\ Standardized spent fuel facilities, 10 CFR parts 71 and 72
  Certificates of Compliance and related Quality Assurance program
  approvals, and special reviews, such as topical reports, are not
  assessed an annual fee because the generic costs of regulating these
  activities are primarily attributable to users of the designs,
  certificates, and topical reports.
\7\ Licensees in this category are not assessed an annual fee because
  they are charged an annual fee in other categories while they are
  licensed to operate.
\8\ No annual fee is charged because it is not practical to administer
  due to the relatively short life or temporary nature of the license.
\9\ Separate annual fees will not be assessed for pacemaker licenses
  issued to medical institutions that also hold nuclear medicine
  licenses under fee categories 7.B. or 7.C.
\10\ This includes Certificates of Compliance issued to the U.S.
  Department of Energy that are not funded from the Nuclear Waste Fund.
\11\ See Sec. 171.15(c).
\12\ See Sec. 171.15(c).
\13\ No annual fee is charged for this category because the cost of the
  general license registration program applicable to licenses in this
  category will be recovered through 10 CFR part 170 fees.
\14\ Persons who possess radium sources that are used for operational
  purposes in another fee category are not also subject to the fees in
  this category. (This exception does not apply if the radium sources
  are possessed for storage only.)
\15\ Licensees paying annual fees under category 1.A., 1.B., and 1.E.
  are not subject to the annual fees for categories 1.C., 1.D., and 1.F.
  for sealed sources authorized in the license.
\16\ Licensees subject to fees under categories 1.A., 1.B., 1.E., or
  2.A. must pay the largest applicable fee and are not subject to
  additional fees listed in this table.
\17\ Licensees paying fees under 3.C. are not subject to fees under 2.B.
  for possession and shielding authorized on the same license.
\18\ Licensees paying fees under 7.C. are not subject to fees under 2.B.
  for possession and shielding authorized on the same license.
\19\ Licensees paying fees under 3.N. are not subject to paying fees
  under 3.P. for calibration or leak testing services authorized on the
  same license.
\20\ Licensees paying fees under 7.B. are not subject to paying fees
  under 7.C. for broad scope license licenses issued under parts 30, 35,
  40, and 70 of this chapter for human use of byproduct material, source
  material, and/or special nuclear material, except licenses for
  byproduct material, source material, or special nuclear material in
  sealed sources contained in teletherapy devices authorized on the same
  license.

    (e) The fee-relief adjustment allocated to annual fees includes the 
budgeted resources for the activities listed in paragraph (e)(1) of this 
section, plus the total budgeted resources for the activities included 
in paragraphs (e)(2) and (3) of this section, as reduced by the 
appropriations the NRC receives for these types of activities. If the 
NRC's appropriations for these types of activities are greater than the 
budgeted resources for the activities included in paragraphs (e)(2) and 
(3) of this section for a given fiscal year, a

[[Page 865]]

negative fee-relief adjustment (or annual fee reduction) will be 
allocated to annual fees. The activities comprising the FY 2017 fee-
relief adjustment are as follows:
    (1) Low-level waste disposal generic activities;
    (2) Activities not attributable to an existing NRC licensee or class 
of licenses (e.g., international cooperative safety program and 
international safeguards activities, support for the Agreement State 
program); and
    (3) Activities not currently subject to 10 CFR part 170 licensing 
and inspection fees based on existing law or Commission policy (e.g., 
reviews and inspections conducted of nonprofit educational institutions, 
costs that would not be collected from small entities based on 
Commission policy in accordance with the Regulatory Flexibility Act, 5 
U.S.C. 601 et seq., regulatory support for Agreement States, generic 
decommissioning/reclamation activities for fee classes other than power 
reactors and spent fuel storage/reactor decommissioning, the in-situ 
leach rulemaking, and activities for unregistered general licensees).

[64 FR 31476, June 10, 1999; 64 FR 38816, July 20, 1999]

    Editorial Note: For Federal Register citations affecting Sec. 
171.16, see the List of CFR Sections Affected, which appears in the 
Finding Aids section of the printed volume and at www.fdsys.gov.



Sec. 171.17  Proration.

    Annual fees will be prorated for NRC licensees as follows:
    (a) Reactors, 10 CFR part 72 licensees who do not hold 10 CFR part 
50 licenses, and materials licenses with annual fees of $100,000 or 
greater for a single fee category.
    (1) New licenses. The annual fees for new licenses for power 
reactors, non-power reactors, 10 CFR part 72 licensees who do not hold a 
10 CFR part 50 license, and materials licenses with annual fees of 
$100,000 or greater for a single fee category for the current FY, that 
are subject to fees under this part and are granted a license to operate 
on or after October 1 of a FY, are prorated on the basis of the number 
of days remaining in the FY. Thereafter, the full annual fee is due and 
payable each subsequent FY.
    (2) Terminations. The base operating power reactor annual fee for 
operating reactor licensees who have requested amendment to withdraw 
operating authority permanently during the FY will be prorated based on 
the number of days during the FY the license was in effect before 
docketing of the certifications for permanent cessation of operations 
and permanent removal of fuel from the reactor vessel or when a final 
legally effective order to permanently cease operations has come into 
effect. The spent fuel storage/reactor decommissioning annual fee for 
reactor licensees who permanently cease operations and have permanently 
removed fuel from the site during the FY will be prorated on the basis 
of the number of days remaining in the FY after docketing of both the 
certifications of permanent cessation of operations and permanent 
removal of fuel from the site. The spent fuel storage/reactor 
decommissioning annual fee will be prorated for those 10 CFR part 72 
licensees who do not hold a 10 CFR part 50 license who request 
termination of the 10 CFR part 72 license and permanently cease 
activities authorized by the license during the FY based on the number 
of days the license was in effect before receipt of the termination 
request. The annual fee for materials licenses with annual fees of 
$100,000 or greater for a single fee category for the current FY will be 
prorated based on the number of days remaining in the FY when a 
termination request or a request for a possession-only license is 
received by the NRC, provided the licensee permanently ceased licensed 
activities during the specified period.
    (3) Downgraded licenses. The annual fee for a materials license with 
an annual fee of $100,000 or greater for a single fee category for the 
current FY, that is subject to fees under this part and downgraded on or 
after October 1 of a FY, is automatically prorated by the agency on the 
basis of the number of days remaining in the FY when the application for 
downgrade is received and approved by the NRC, provided the licensee 
permanently ceased the stated activities during the specified period.

[[Page 866]]

    (b) Materials licenses (excluding 10 CFR part 72 licenses and 
materials license with annual fees of $100,000 or greater for a single 
fee category, included in Sec. 171.17(a)).
    (1) New licenses. The annual fee for a materials license that is 
subject to fees under this part and issued on or after October 1 of the 
FY is prorated on the basis of when the NRC issues the new license. New 
licenses issued during the period October 1 through March 31 of the FY 
will be assessed one-half the annual fee for that FY. New licenses 
issued on or after April 1 of the FY will not be assessed an annual fee 
for that FY. Thereafter, the full fee is due and payable each subsequent 
FY.
    (2) Terminations. The annual fee will be prorated for licenses for 
which a termination request or a request for a POL has been received on 
or after October 1 of a FY on the basis of when the application for 
termination or POL is received by the NRC provided the licensee 
permanently ceased licensed activities during the specified period. 
Licenses for which applications for termination or POL are filed during 
the period October 1 through March 31 of the FY are assessed one-half 
the annual fee for the applicable category(ies) for that FY. Licenses 
for which applications for termination or POL are filed on or after 
April 1 of the FY are assessed the full annual fee for that FY. 
Materials licenses transferred to a new Agreement State during the FY 
are considered terminated by the NRC, for annual fee purposes, on the 
date that the Agreement with the State becomes effective; therefore, the 
same proration provisions will apply as if the licenses were terminated.
    (3) Downgraded licenses. (i) The annual fee for a materials license 
that is subject to fees under this part and downgraded on or after 
October 1 of a FY is automatically prorated on the basis of the date 
when the application for downgrade is received and approved by the NRC, 
provided the licensee permanently ceased the stated activities during 
the specified period.
    (ii) Annual fees for licenses for which applications to downgrade 
are filed during the period October 1 through March 31 of the FY will be 
prorated as follows:
    (A) Licenses for which applications have been filed to reduce the 
scope of the license from a higher fee category(ies) to a lower fee 
category(ies) will be assessed one-half the annual fee for the higher 
fee category and one-half the annual fee for the lower fee 
category(ies), and, if applicable, the full annual fee for fee 
categories not affected by the downgrade; and
    (B) Licenses with multiple fee categories for which applications 
have been filed to downgrade by deleting a fee category will be assessed 
one-half the annual fee for the fee category being deleted and the full 
annual fee for the remaining categories.
    (iii) Licenses for which applications to downgrade are filed on or 
after April 1 of the FY are assessed the full fee for that FY.

[72 FR 31431, June 6, 2007, as amended at 77 FR 35835, June 15, 2012]



Sec. 171.19  Payment.

    (a) Method of payment. Annual fee payments, made payable to the U.S. 
Nuclear Regulatory Commission, are to be made in U.S. funds by 
electronic funds transfer such as ACH (Automated Clearing House) using 
EDI (Electronic Data Interchange), check, draft, money order, or credit 
card. Federal agencies may also make payment by the On-line Payment and 
Collection System (OPAC's). Where specific payment instructions are 
provided on the invoices to applicants and licensees, payment should be 
made accordingly, e.g. invoices of $5,000 or more should be paid via ACH 
through NRC's Lockbox Bank at the address indicated on the invoice. 
Credit card payments should be made up to the limit established by the 
credit card bank, in accordance with specific instructions provided with 
the invoices, to the Lockbox Bank designated for credit card payments. 
In accordance with Department of the Treasury requirements, refunds will 
only be made upon receipt of information on the payee's financial 
institution and bank accounts.
    (b) Annual fees in the amount of $100,000 or more and described in 
the Federal Register document issued under Sec. 171.13, must be paid in 
quarterly installments of 25 percent as billed by

[[Page 867]]

the NRC. The quarters begin on October 1, January 1, April 1, and July 1 
of each fiscal year. The NRC will adjust the fourth quarterly invoice to 
recover the full amount of the revised annual fee. If the amounts 
collected in the first three quarters exceed the amount of the revised 
annual fee, the overpayment will be refunded. Licensees whose annual fee 
for the previous fiscal year was less than $100,000 (billed on the 
anniversary date of the license), and whose revised annual fee for the 
current fiscal year is $100,000 or greater (subject to quarterly 
billing), will be issued a bill upon publication of the final rule for 
the full amount of the revised annual fee for the current fiscal year, 
less any payments received for the current fiscal year based on the 
anniversary date billing process.
    (c) Annual fees that are less than $100,000 are billed on the 
anniversary date of the license. For annual fee purposes, the 
anniversary date of the license is considered to be the first day of the 
month in which the original license was issued by the NRC. Licensees 
that are billed on the license anniversary date will be assessed the 
annual fee in effect on the anniversary date of the license. Materials 
licenses subject to the annual fee that are terminated during the fiscal 
year but before the anniversary month of the license will be billed upon 
termination for the fee in effect at the time of the billing. New 
materials licenses subject to the annual fee will be billed in the month 
the license is issued or in the next available monthly billing for the 
fee in effect on the anniversary date of the license. Thereafter, annual 
fees for new licenses will be assessed in the anniversary month of the 
license.
    (d) Annual fees of less than $100,000 must be paid as billed by the 
NRC. Materials license annual fees that are less than $100,000 are 
billed on the anniversary date of the license. The materials licensees 
that are billed on the anniversary date of the license are those covered 
by fee categories 1.C., 1.D., 1.F., and 2.A.(2) through 9.D.
    (e) Payment is due on the invoice date and interest accrues from the 
date of the invoice. However, interest will be waived if payment is 
received within 30 days from the invoice date.
    (f) The NRC is entitled to collect any underpayment of fees as a 
result of an error by the NRC.

[65 FR 36968, June 12, 2000, as amended at 66 FR 32478, June 14, 2001; 
71 FR 30755, May 30, 2006; 71 FR 33190, June 8, 2006; 72 FR 31432, June 
6, 2007; 78 FR 39491, July 1, 2013; 79 FR 37154, June 30, 2014; 82 FR 
30708, June 30, 2017]



Sec. 171.21  [Reserved]



Sec. 171.23  Enforcement.

    If any person required to pay the annual fee fails to pay when the 
fee is due, or files a false certification with respect to qualifying as 
a small entity under the Regulatory Flexibility Criteria, the Commission 
may refuse to process any application submitted by or on behalf of the 
person with respect to any license issued to the person and may suspend 
or revoke any licenses held by the person. The filing of a false 
certification to qualify as a small entity under Sec. 171.16(c) of this 
part may also result in punitive action pursuant to 18 U.S.C. 1001.

[56 FR 31510, July 10, 1991]



Sec. 171.25  Collection, interest, penalties, and administrative costs.

    All annual fees in Sec. Sec. 171.15 and 171.16 will be collected 
pursuant to the procedures of 10 CFR part 15. Interest, penalties and 
administrative costs for late payments will be assessed in accordance 
with 10 CFR part 15, of this chapter, 4 CFR part 102, and other relevant 
regulations of the United States Government, as appropriate. In the 
event a quarterly installment is not made by the appropriate due date 
specified in Sec. 171.19, the full fee becomes due and payable, with 
interest, penalties, and administrative costs of collection calculated 
from the date that quarterly installment was due.

[56 FR 31511, July 10, 1991]

                        PARTS 172	199 [RESERVED]

[[Page 869]]



                              FINDING AIDS




  --------------------------------------------------------------------

  A list of CFR titles, subtitles, chapters, subchapters and parts and 
an alphabetical list of agencies publishing in the CFR are included in 
the CFR Index and Finding Aids volume to the Code of Federal Regulations 
which is published separately and revised annually.

  Table of CFR Titles and Chapters
  Alphabetical List of Agencies Appearing in the CFR
  List of CFR Sections Affected

[[Page 871]]



                    Table of CFR Titles and Chapters




                     (Revised as of January 1, 2018)

                      Title 1--General Provisions

         I  Administrative Committee of the Federal Register 
                (Parts 1--49)
        II  Office of the Federal Register (Parts 50--299)
       III  Administrative Conference of the United States (Parts 
                300--399)
        IV  Miscellaneous Agencies (Parts 400--599)
        VI  National Capital Planning Commission (Parts 600--699)

                    Title 2--Grants and Agreements

            Subtitle A--Office of Management and Budget Guidance 
                for Grants and Agreements
         I  Office of Management and Budget Governmentwide 
                Guidance for Grants and Agreements (Parts 2--199)
        II  Office of Management and Budget Guidance (Parts 200--
                299)
            Subtitle B--Federal Agency Regulations for Grants and 
                Agreements
       III  Department of Health and Human Services (Parts 300--
                399)
        IV  Department of Agriculture (Parts 400--499)
        VI  Department of State (Parts 600--699)
       VII  Agency for International Development (Parts 700--799)
      VIII  Department of Veterans Affairs (Parts 800--899)
        IX  Department of Energy (Parts 900--999)
         X  Department of the Treasury (Parts 1000--1099)
        XI  Department of Defense (Parts 1100--1199)
       XII  Department of Transportation (Parts 1200--1299)
      XIII  Department of Commerce (Parts 1300--1399)
       XIV  Department of the Interior (Parts 1400--1499)
        XV  Environmental Protection Agency (Parts 1500--1599)
     XVIII  National Aeronautics and Space Administration (Parts 
                1800--1899)
        XX  United States Nuclear Regulatory Commission (Parts 
                2000--2099)
      XXII  Corporation for National and Community Service (Parts 
                2200--2299)
     XXIII  Social Security Administration (Parts 2300--2399)
      XXIV  Housing and Urban Development (Parts 2400--2499)
       XXV  National Science Foundation (Parts 2500--2599)
      XXVI  National Archives and Records Administration (Parts 
                2600--2699)

[[Page 872]]

     XXVII  Small Business Administration (Parts 2700--2799)
    XXVIII  Department of Justice (Parts 2800--2899)
      XXIX  Department of Labor (Parts 2900--2999)
       XXX  Department of Homeland Security (Parts 3000--3099)
      XXXI  Institute of Museum and Library Services (Parts 3100--
                3199)
     XXXII  National Endowment for the Arts (Parts 3200--3299)
    XXXIII  National Endowment for the Humanities (Parts 3300--
                3399)
     XXXIV  Department of Education (Parts 3400--3499)
      XXXV  Export-Import Bank of the United States (Parts 3500--
                3599)
     XXXVI  Office of National Drug Control Policy, Executive 
                Office of the President (Parts 3600--3699)
    XXXVII  Peace Corps (Parts 3700--3799)
     LVIII  Election Assistance Commission (Parts 5800--5899)
       LIX  Gulf Coast Ecosystem Restoration Council (Parts 5900--
                5999)

                        Title 3--The President

         I  Executive Office of the President (Parts 100--199)

                           Title 4--Accounts

         I  Government Accountability Office (Parts 1--199)

                   Title 5--Administrative Personnel

         I  Office of Personnel Management (Parts 1--1199)
        II  Merit Systems Protection Board (Parts 1200--1299)
       III  Office of Management and Budget (Parts 1300--1399)
        IV  Office of Personnel Management and Office of the 
                Director of National Intelligence (Parts 1400--
                1499)
         V  The International Organizations Employees Loyalty 
                Board (Parts 1500--1599)
        VI  Federal Retirement Thrift Investment Board (Parts 
                1600--1699)
      VIII  Office of Special Counsel (Parts 1800--1899)
        IX  Appalachian Regional Commission (Parts 1900--1999)
        XI  Armed Forces Retirement Home (Parts 2100--2199)
       XIV  Federal Labor Relations Authority, General Counsel of 
                the Federal Labor Relations Authority and Federal 
                Service Impasses Panel (Parts 2400--2499)
       XVI  Office of Government Ethics (Parts 2600--2699)
       XXI  Department of the Treasury (Parts 3100--3199)
      XXII  Federal Deposit Insurance Corporation (Parts 3200--
                3299)
     XXIII  Department of Energy (Parts 3300--3399)
      XXIV  Federal Energy Regulatory Commission (Parts 3400--
                3499)
       XXV  Department of the Interior (Parts 3500--3599)
      XXVI  Department of Defense (Parts 3600--3699)

[[Page 873]]

    XXVIII  Department of Justice (Parts 3800--3899)
      XXIX  Federal Communications Commission (Parts 3900--3999)
       XXX  Farm Credit System Insurance Corporation (Parts 4000--
                4099)
      XXXI  Farm Credit Administration (Parts 4100--4199)
    XXXIII  Overseas Private Investment Corporation (Parts 4300--
                4399)
     XXXIV  Securities and Exchange Commission (Parts 4400--4499)
      XXXV  Office of Personnel Management (Parts 4500--4599)
     XXXVI  Department of Homeland Security (Parts 4600--4699)
    XXXVII  Federal Election Commission (Parts 4700--4799)
        XL  Interstate Commerce Commission (Parts 5000--5099)
       XLI  Commodity Futures Trading Commission (Parts 5100--
                5199)
      XLII  Department of Labor (Parts 5200--5299)
     XLIII  National Science Foundation (Parts 5300--5399)
       XLV  Department of Health and Human Services (Parts 5500--
                5599)
      XLVI  Postal Rate Commission (Parts 5600--5699)
     XLVII  Federal Trade Commission (Parts 5700--5799)
    XLVIII  Nuclear Regulatory Commission (Parts 5800--5899)
      XLIX  Federal Labor Relations Authority (Parts 5900--5999)
         L  Department of Transportation (Parts 6000--6099)
       LII  Export-Import Bank of the United States (Parts 6200--
                6299)
      LIII  Department of Education (Parts 6300--6399)
       LIV  Environmental Protection Agency (Parts 6400--6499)
        LV  National Endowment for the Arts (Parts 6500--6599)
       LVI  National Endowment for the Humanities (Parts 6600--
                6699)
      LVII  General Services Administration (Parts 6700--6799)
     LVIII  Board of Governors of the Federal Reserve System 
                (Parts 6800--6899)
       LIX  National Aeronautics and Space Administration (Parts 
                6900--6999)
        LX  United States Postal Service (Parts 7000--7099)
       LXI  National Labor Relations Board (Parts 7100--7199)
      LXII  Equal Employment Opportunity Commission (Parts 7200--
                7299)
     LXIII  Inter-American Foundation (Parts 7300--7399)
      LXIV  Merit Systems Protection Board (Parts 7400--7499)
       LXV  Department of Housing and Urban Development (Parts 
                7500--7599)
      LXVI  National Archives and Records Administration (Parts 
                7600--7699)
     LXVII  Institute of Museum and Library Services (Parts 7700--
                7799)
    LXVIII  Commission on Civil Rights (Parts 7800--7899)
      LXIX  Tennessee Valley Authority (Parts 7900--7999)
       LXX  Court Services and Offender Supervision Agency for the 
                District of Columbia (Parts 8000--8099)
      LXXI  Consumer Product Safety Commission (Parts 8100--8199)
    LXXIII  Department of Agriculture (Parts 8300--8399)

[[Page 874]]

     LXXIV  Federal Mine Safety and Health Review Commission 
                (Parts 8400--8499)
     LXXVI  Federal Retirement Thrift Investment Board (Parts 
                8600--8699)
    LXXVII  Office of Management and Budget (Parts 8700--8799)
      LXXX  Federal Housing Finance Agency (Parts 9000--9099)
   LXXXIII  Special Inspector General for Afghanistan 
                Reconstruction (Parts 9300--9399)
    LXXXIV  Bureau of Consumer Financial Protection (Parts 9400--
                9499)
    LXXXVI  National Credit Union Administration (Parts 9600--
                9699)
     XCVII  Department of Homeland Security Human Resources 
                Management System (Department of Homeland 
                Security--Office of Personnel Management) (Parts 
                9700--9799)
    XCVIII  Council of the Inspectors General on Integrity and 
                Efficiency (Parts 9800--9899)
      XCIX  Military Compensation and Retirement Modernization 
                Commission (Parts 9900--9999)
         C  National Council on Disability (Parts 10000--10049)

                      Title 6--Domestic Security

         I  Department of Homeland Security, Office of the 
                Secretary (Parts 1--199)
         X  Privacy and Civil Liberties Oversight Board (Parts 
                1000--1099)

                         Title 7--Agriculture

            Subtitle A--Office of the Secretary of Agriculture 
                (Parts 0--26)
            Subtitle B--Regulations of the Department of 
                Agriculture
         I  Agricultural Marketing Service (Standards, 
                Inspections, Marketing Practices), Department of 
                Agriculture (Parts 27--209)
        II  Food and Nutrition Service, Department of Agriculture 
                (Parts 210--299)
       III  Animal and Plant Health Inspection Service, Department 
                of Agriculture (Parts 300--399)
        IV  Federal Crop Insurance Corporation, Department of 
                Agriculture (Parts 400--499)
         V  Agricultural Research Service, Department of 
                Agriculture (Parts 500--599)
        VI  Natural Resources Conservation Service, Department of 
                Agriculture (Parts 600--699)
       VII  Farm Service Agency, Department of Agriculture (Parts 
                700--799)
      VIII  Grain Inspection, Packers and Stockyards 
                Administration (Federal Grain Inspection Service), 
                Department of Agriculture (Parts 800--899)
        IX  Agricultural Marketing Service (Marketing Agreements 
                and Orders; Fruits, Vegetables, Nuts), Department 
                of Agriculture (Parts 900--999)

[[Page 875]]

         X  Agricultural Marketing Service (Marketing Agreements 
                and Orders; Milk), Department of Agriculture 
                (Parts 1000--1199)
        XI  Agricultural Marketing Service (Marketing Agreements 
                and Orders; Miscellaneous Commodities), Department 
                of Agriculture (Parts 1200--1299)
       XIV  Commodity Credit Corporation, Department of 
                Agriculture (Parts 1400--1499)
        XV  Foreign Agricultural Service, Department of 
                Agriculture (Parts 1500--1599)
       XVI  Rural Telephone Bank, Department of Agriculture (Parts 
                1600--1699)
      XVII  Rural Utilities Service, Department of Agriculture 
                (Parts 1700--1799)
     XVIII  Rural Housing Service, Rural Business-Cooperative 
                Service, Rural Utilities Service, and Farm Service 
                Agency, Department of Agriculture (Parts 1800--
                2099)
        XX  Local Television Loan Guarantee Board (Parts 2200--
                2299)
       XXV  Office of Advocacy and Outreach, Department of 
                Agriculture (Parts 2500--2599)
      XXVI  Office of Inspector General, Department of Agriculture 
                (Parts 2600--2699)
     XXVII  Office of Information Resources Management, Department 
                of Agriculture (Parts 2700--2799)
    XXVIII  Office of Operations, Department of Agriculture (Parts 
                2800--2899)
      XXIX  Office of Energy Policy and New Uses, Department of 
                Agriculture (Parts 2900--2999)
       XXX  Office of the Chief Financial Officer, Department of 
                Agriculture (Parts 3000--3099)
      XXXI  Office of Environmental Quality, Department of 
                Agriculture (Parts 3100--3199)
     XXXII  Office of Procurement and Property Management, 
                Department of Agriculture (Parts 3200--3299)
    XXXIII  Office of Transportation, Department of Agriculture 
                (Parts 3300--3399)
     XXXIV  National Institute of Food and Agriculture (Parts 
                3400--3499)
      XXXV  Rural Housing Service, Department of Agriculture 
                (Parts 3500--3599)
     XXXVI  National Agricultural Statistics Service, Department 
                of Agriculture (Parts 3600--3699)
    XXXVII  Economic Research Service, Department of Agriculture 
                (Parts 3700--3799)
   XXXVIII  World Agricultural Outlook Board, Department of 
                Agriculture (Parts 3800--3899)
       XLI  [Reserved]
      XLII  Rural Business-Cooperative Service and Rural Utilities 
                Service, Department of Agriculture (Parts 4200--
                4299)

[[Page 876]]

                    Title 8--Aliens and Nationality

         I  Department of Homeland Security (Immigration and 
                Naturalization) (Parts 1--499)
         V  Executive Office for Immigration Review, Department of 
                Justice (Parts 1000--1399)

                 Title 9--Animals and Animal Products

         I  Animal and Plant Health Inspection Service, Department 
                of Agriculture (Parts 1--199)
        II  Grain Inspection, Packers and Stockyards 
                Administration (Packers and Stockyards Programs), 
                Department of Agriculture (Parts 200--299)
       III  Food Safety and Inspection Service, Department of 
                Agriculture (Parts 300--599)

                           Title 10--Energy

         I  Nuclear Regulatory Commission (Parts 0--199)
        II  Department of Energy (Parts 200--699)
       III  Department of Energy (Parts 700--999)
         X  Department of Energy (General Provisions) (Parts 
                1000--1099)
      XIII  Nuclear Waste Technical Review Board (Parts 1300--
                1399)
      XVII  Defense Nuclear Facilities Safety Board (Parts 1700--
                1799)
     XVIII  Northeast Interstate Low-Level Radioactive Waste 
                Commission (Parts 1800--1899)

                      Title 11--Federal Elections

         I  Federal Election Commission (Parts 1--9099)
        II  Election Assistance Commission (Parts 9400--9499)

                      Title 12--Banks and Banking

         I  Comptroller of the Currency, Department of the 
                Treasury (Parts 1--199)
        II  Federal Reserve System (Parts 200--299)
       III  Federal Deposit Insurance Corporation (Parts 300--399)
        IV  Export-Import Bank of the United States (Parts 400--
                499)
         V  Office of Thrift Supervision, Department of the 
                Treasury (Parts 500--599)
        VI  Farm Credit Administration (Parts 600--699)
       VII  National Credit Union Administration (Parts 700--799)
      VIII  Federal Financing Bank (Parts 800--899)
        IX  Federal Housing Finance Board (Parts 900--999)
         X  Bureau of Consumer Financial Protection (Parts 1000--
                1099)
        XI  Federal Financial Institutions Examination Council 
                (Parts 1100--1199)
       XII  Federal Housing Finance Agency (Parts 1200--1299)

[[Page 877]]

      XIII  Financial Stability Oversight Council (Parts 1300--
                1399)
       XIV  Farm Credit System Insurance Corporation (Parts 1400--
                1499)
        XV  Department of the Treasury (Parts 1500--1599)
       XVI  Office of Financial Research (Parts 1600--1699)
      XVII  Office of Federal Housing Enterprise Oversight, 
                Department of Housing and Urban Development (Parts 
                1700--1799)
     XVIII  Community Development Financial Institutions Fund, 
                Department of the Treasury (Parts 1800--1899)

               Title 13--Business Credit and Assistance

         I  Small Business Administration (Parts 1--199)
       III  Economic Development Administration, Department of 
                Commerce (Parts 300--399)
        IV  Emergency Steel Guarantee Loan Board (Parts 400--499)
         V  Emergency Oil and Gas Guaranteed Loan Board (Parts 
                500--599)

                    Title 14--Aeronautics and Space

         I  Federal Aviation Administration, Department of 
                Transportation (Parts 1--199)
        II  Office of the Secretary, Department of Transportation 
                (Aviation Proceedings) (Parts 200--399)
       III  Commercial Space Transportation, Federal Aviation 
                Administration, Department of Transportation 
                (Parts 400--1199)
         V  National Aeronautics and Space Administration (Parts 
                1200--1299)
        VI  Air Transportation System Stabilization (Parts 1300--
                1399)

                 Title 15--Commerce and Foreign Trade

            Subtitle A--Office of the Secretary of Commerce (Parts 
                0--29)
            Subtitle B--Regulations Relating to Commerce and 
                Foreign Trade
         I  Bureau of the Census, Department of Commerce (Parts 
                30--199)
        II  National Institute of Standards and Technology, 
                Department of Commerce (Parts 200--299)
       III  International Trade Administration, Department of 
                Commerce (Parts 300--399)
        IV  Foreign-Trade Zones Board, Department of Commerce 
                (Parts 400--499)
       VII  Bureau of Industry and Security, Department of 
                Commerce (Parts 700--799)
      VIII  Bureau of Economic Analysis, Department of Commerce 
                (Parts 800--899)
        IX  National Oceanic and Atmospheric Administration, 
                Department of Commerce (Parts 900--999)

[[Page 878]]

        XI  National Technical Information Service, Department of 
                Commerce (Parts 1100--1199)
      XIII  East-West Foreign Trade Board (Parts 1300--1399)
       XIV  Minority Business Development Agency (Parts 1400--
                1499)
            Subtitle C--Regulations Relating to Foreign Trade 
                Agreements
        XX  Office of the United States Trade Representative 
                (Parts 2000--2099)
            Subtitle D--Regulations Relating to Telecommunications 
                and Information
     XXIII  National Telecommunications and Information 
                Administration, Department of Commerce (Parts 
                2300--2399) [Reserved]

                    Title 16--Commercial Practices

         I  Federal Trade Commission (Parts 0--999)
        II  Consumer Product Safety Commission (Parts 1000--1799)

             Title 17--Commodity and Securities Exchanges

         I  Commodity Futures Trading Commission (Parts 1--199)
        II  Securities and Exchange Commission (Parts 200--399)
        IV  Department of the Treasury (Parts 400--499)

          Title 18--Conservation of Power and Water Resources

         I  Federal Energy Regulatory Commission, Department of 
                Energy (Parts 1--399)
       III  Delaware River Basin Commission (Parts 400--499)
        VI  Water Resources Council (Parts 700--799)
      VIII  Susquehanna River Basin Commission (Parts 800--899)
      XIII  Tennessee Valley Authority (Parts 1300--1399)

                       Title 19--Customs Duties

         I  U.S. Customs and Border Protection, Department of 
                Homeland Security; Department of the Treasury 
                (Parts 0--199)
        II  United States International Trade Commission (Parts 
                200--299)
       III  International Trade Administration, Department of 
                Commerce (Parts 300--399)
        IV  U.S. Immigration and Customs Enforcement, Department 
                of Homeland Security (Parts 400--599) [Reserved]

                     Title 20--Employees' Benefits

         I  Office of Workers' Compensation Programs, Department 
                of Labor (Parts 1--199)
        II  Railroad Retirement Board (Parts 200--399)

[[Page 879]]

       III  Social Security Administration (Parts 400--499)
        IV  Employees' Compensation Appeals Board, Department of 
                Labor (Parts 500--599)
         V  Employment and Training Administration, Department of 
                Labor (Parts 600--699)
        VI  Office of Workers' Compensation Programs, Department 
                of Labor (Parts 700--799)
       VII  Benefits Review Board, Department of Labor (Parts 
                800--899)
      VIII  Joint Board for the Enrollment of Actuaries (Parts 
                900--999)
        IX  Office of the Assistant Secretary for Veterans' 
                Employment and Training Service, Department of 
                Labor (Parts 1000--1099)

                       Title 21--Food and Drugs

         I  Food and Drug Administration, Department of Health and 
                Human Services (Parts 1--1299)
        II  Drug Enforcement Administration, Department of Justice 
                (Parts 1300--1399)
       III  Office of National Drug Control Policy (Parts 1400--
                1499)

                      Title 22--Foreign Relations

         I  Department of State (Parts 1--199)
        II  Agency for International Development (Parts 200--299)
       III  Peace Corps (Parts 300--399)
        IV  International Joint Commission, United States and 
                Canada (Parts 400--499)
         V  Broadcasting Board of Governors (Parts 500--599)
       VII  Overseas Private Investment Corporation (Parts 700--
                799)
        IX  Foreign Service Grievance Board (Parts 900--999)
         X  Inter-American Foundation (Parts 1000--1099)
        XI  International Boundary and Water Commission, United 
                States and Mexico, United States Section (Parts 
                1100--1199)
       XII  United States International Development Cooperation 
                Agency (Parts 1200--1299)
      XIII  Millennium Challenge Corporation (Parts 1300--1399)
       XIV  Foreign Service Labor Relations Board; Federal Labor 
                Relations Authority; General Counsel of the 
                Federal Labor Relations Authority; and the Foreign 
                Service Impasse Disputes Panel (Parts 1400--1499)
        XV  African Development Foundation (Parts 1500--1599)
       XVI  Japan-United States Friendship Commission (Parts 
                1600--1699)
      XVII  United States Institute of Peace (Parts 1700--1799)

                          Title 23--Highways

         I  Federal Highway Administration, Department of 
                Transportation (Parts 1--999)

[[Page 880]]

        II  National Highway Traffic Safety Administration and 
                Federal Highway Administration, Department of 
                Transportation (Parts 1200--1299)
       III  National Highway Traffic Safety Administration, 
                Department of Transportation (Parts 1300--1399)

                Title 24--Housing and Urban Development

            Subtitle A--Office of the Secretary, Department of 
                Housing and Urban Development (Parts 0--99)
            Subtitle B--Regulations Relating to Housing and Urban 
                Development
         I  Office of Assistant Secretary for Equal Opportunity, 
                Department of Housing and Urban Development (Parts 
                100--199)
        II  Office of Assistant Secretary for Housing-Federal 
                Housing Commissioner, Department of Housing and 
                Urban Development (Parts 200--299)
       III  Government National Mortgage Association, Department 
                of Housing and Urban Development (Parts 300--399)
        IV  Office of Housing and Office of Multifamily Housing 
                Assistance Restructuring, Department of Housing 
                and Urban Development (Parts 400--499)
         V  Office of Assistant Secretary for Community Planning 
                and Development, Department of Housing and Urban 
                Development (Parts 500--599)
        VI  Office of Assistant Secretary for Community Planning 
                and Development, Department of Housing and Urban 
                Development (Parts 600--699) [Reserved]
       VII  Office of the Secretary, Department of Housing and 
                Urban Development (Housing Assistance Programs and 
                Public and Indian Housing Programs) (Parts 700--
                799)
      VIII  Office of the Assistant Secretary for Housing--Federal 
                Housing Commissioner, Department of Housing and 
                Urban Development (Section 8 Housing Assistance 
                Programs, Section 202 Direct Loan Program, Section 
                202 Supportive Housing for the Elderly Program and 
                Section 811 Supportive Housing for Persons With 
                Disabilities Program) (Parts 800--899)
        IX  Office of Assistant Secretary for Public and Indian 
                Housing, Department of Housing and Urban 
                Development (Parts 900--1699)
         X  Office of Assistant Secretary for Housing--Federal 
                Housing Commissioner, Department of Housing and 
                Urban Development (Interstate Land Sales 
                Registration Program) (Parts 1700--1799)
       XII  Office of Inspector General, Department of Housing and 
                Urban Development (Parts 2000--2099)
        XV  Emergency Mortgage Insurance and Loan Programs, 
                Department of Housing and Urban Development (Parts 
                2700--2799) [Reserved]
        XX  Office of Assistant Secretary for Housing--Federal 
                Housing Commissioner, Department of Housing and 
                Urban Development (Parts 3200--3899)

[[Page 881]]

      XXIV  Board of Directors of the HOPE for Homeowners Program 
                (Parts 4000--4099) [Reserved]
       XXV  Neighborhood Reinvestment Corporation (Parts 4100--
                4199)

                           Title 25--Indians

         I  Bureau of Indian Affairs, Department of the Interior 
                (Parts 1--299)
        II  Indian Arts and Crafts Board, Department of the 
                Interior (Parts 300--399)
       III  National Indian Gaming Commission, Department of the 
                Interior (Parts 500--599)
        IV  Office of Navajo and Hopi Indian Relocation (Parts 
                700--899)
         V  Bureau of Indian Affairs, Department of the Interior, 
                and Indian Health Service, Department of Health 
                and Human Services (Part 900)
        VI  Office of the Assistant Secretary, Indian Affairs, 
                Department of the Interior (Parts 1000--1199)
       VII  Office of the Special Trustee for American Indians, 
                Department of the Interior (Parts 1200--1299)

                      Title 26--Internal Revenue

         I  Internal Revenue Service, Department of the Treasury 
                (Parts 1--End)

           Title 27--Alcohol, Tobacco Products and Firearms

         I  Alcohol and Tobacco Tax and Trade Bureau, Department 
                of the Treasury (Parts 1--399)
        II  Bureau of Alcohol, Tobacco, Firearms, and Explosives, 
                Department of Justice (Parts 400--699)

                   Title 28--Judicial Administration

         I  Department of Justice (Parts 0--299)
       III  Federal Prison Industries, Inc., Department of Justice 
                (Parts 300--399)
         V  Bureau of Prisons, Department of Justice (Parts 500--
                599)
        VI  Offices of Independent Counsel, Department of Justice 
                (Parts 600--699)
       VII  Office of Independent Counsel (Parts 700--799)
      VIII  Court Services and Offender Supervision Agency for the 
                District of Columbia (Parts 800--899)
        IX  National Crime Prevention and Privacy Compact Council 
                (Parts 900--999)
        XI  Department of Justice and Department of State (Parts 
                1100--1199)

[[Page 882]]

                            Title 29--Labor

            Subtitle A--Office of the Secretary of Labor (Parts 
                0--99)
            Subtitle B--Regulations Relating to Labor
         I  National Labor Relations Board (Parts 100--199)
        II  Office of Labor-Management Standards, Department of 
                Labor (Parts 200--299)
       III  National Railroad Adjustment Board (Parts 300--399)
        IV  Office of Labor-Management Standards, Department of 
                Labor (Parts 400--499)
         V  Wage and Hour Division, Department of Labor (Parts 
                500--899)
        IX  Construction Industry Collective Bargaining Commission 
                (Parts 900--999)
         X  National Mediation Board (Parts 1200--1299)
       XII  Federal Mediation and Conciliation Service (Parts 
                1400--1499)
       XIV  Equal Employment Opportunity Commission (Parts 1600--
                1699)
      XVII  Occupational Safety and Health Administration, 
                Department of Labor (Parts 1900--1999)
        XX  Occupational Safety and Health Review Commission 
                (Parts 2200--2499)
       XXV  Employee Benefits Security Administration, Department 
                of Labor (Parts 2500--2599)
     XXVII  Federal Mine Safety and Health Review Commission 
                (Parts 2700--2799)
        XL  Pension Benefit Guaranty Corporation (Parts 4000--
                4999)

                      Title 30--Mineral Resources

         I  Mine Safety and Health Administration, Department of 
                Labor (Parts 1--199)
        II  Bureau of Safety and Environmental Enforcement, 
                Department of the Interior (Parts 200--299)
        IV  Geological Survey, Department of the Interior (Parts 
                400--499)
         V  Bureau of Ocean Energy Management, Department of the 
                Interior (Parts 500--599)
       VII  Office of Surface Mining Reclamation and Enforcement, 
                Department of the Interior (Parts 700--999)
       XII  Office of Natural Resources Revenue, Department of the 
                Interior (Parts 1200--1299)

                 Title 31--Money and Finance: Treasury

            Subtitle A--Office of the Secretary of the Treasury 
                (Parts 0--50)
            Subtitle B--Regulations Relating to Money and Finance
         I  Monetary Offices, Department of the Treasury (Parts 
                51--199)
        II  Fiscal Service, Department of the Treasury (Parts 
                200--399)
        IV  Secret Service, Department of the Treasury (Parts 
                400--499)
         V  Office of Foreign Assets Control, Department of the 
                Treasury (Parts 500--599)

[[Page 883]]

        VI  Bureau of Engraving and Printing, Department of the 
                Treasury (Parts 600--699)
       VII  Federal Law Enforcement Training Center, Department of 
                the Treasury (Parts 700--799)
      VIII  Office of Investment Security, Department of the 
                Treasury (Parts 800--899)
        IX  Federal Claims Collection Standards (Department of the 
                Treasury--Department of Justice) (Parts 900--999)
         X  Financial Crimes Enforcement Network, Department of 
                the Treasury (Parts 1000--1099)

                      Title 32--National Defense

            Subtitle A--Department of Defense
         I  Office of the Secretary of Defense (Parts 1--399)
         V  Department of the Army (Parts 400--699)
        VI  Department of the Navy (Parts 700--799)
       VII  Department of the Air Force (Parts 800--1099)
            Subtitle B--Other Regulations Relating to National 
                Defense
       XII  Defense Logistics Agency (Parts 1200--1299)
       XVI  Selective Service System (Parts 1600--1699)
      XVII  Office of the Director of National Intelligence (Parts 
                1700--1799)
     XVIII  National Counterintelligence Center (Parts 1800--1899)
       XIX  Central Intelligence Agency (Parts 1900--1999)
        XX  Information Security Oversight Office, National 
                Archives and Records Administration (Parts 2000--
                2099)
       XXI  National Security Council (Parts 2100--2199)
      XXIV  Office of Science and Technology Policy (Parts 2400--
                2499)
     XXVII  Office for Micronesian Status Negotiations (Parts 
                2700--2799)
    XXVIII  Office of the Vice President of the United States 
                (Parts 2800--2899)

               Title 33--Navigation and Navigable Waters

         I  Coast Guard, Department of Homeland Security (Parts 
                1--199)
        II  Corps of Engineers, Department of the Army, Department 
                of Defense (Parts 200--399)
        IV  Saint Lawrence Seaway Development Corporation, 
                Department of Transportation (Parts 400--499)

                          Title 34--Education

            Subtitle A--Office of the Secretary, Department of 
                Education (Parts 1--99)
            Subtitle B--Regulations of the Offices of the 
                Department of Education
         I  Office for Civil Rights, Department of Education 
                (Parts 100--199)

[[Page 884]]

        II  Office of Elementary and Secondary Education, 
                Department of Education (Parts 200--299)
       III  Office of Special Education and Rehabilitative 
                Services, Department of Education (Parts 300--399)
        IV  Office of Career, Technical and Adult Education, 
                Department of Education (Parts 400--499)
         V  Office of Bilingual Education and Minority Languages 
                Affairs, Department of Education (Parts 500--599) 
                [Reserved]
        VI  Office of Postsecondary Education, Department of 
                Education (Parts 600--699)
       VII  Office of Educational Research and Improvement, 
                Department of Education (Parts 700--799) 
                [Reserved]
            Subtitle C--Regulations Relating to Education
        XI  (Parts 1100--1199) [Reserved]
       XII  National Council on Disability (Parts 1200--1299)

                          Title 35 [Reserved]

             Title 36--Parks, Forests, and Public Property

         I  National Park Service, Department of the Interior 
                (Parts 1--199)
        II  Forest Service, Department of Agriculture (Parts 200--
                299)
       III  Corps of Engineers, Department of the Army (Parts 
                300--399)
        IV  American Battle Monuments Commission (Parts 400--499)
         V  Smithsonian Institution (Parts 500--599)
        VI  [Reserved]
       VII  Library of Congress (Parts 700--799)
      VIII  Advisory Council on Historic Preservation (Parts 800--
                899)
        IX  Pennsylvania Avenue Development Corporation (Parts 
                900--999)
         X  Presidio Trust (Parts 1000--1099)
        XI  Architectural and Transportation Barriers Compliance 
                Board (Parts 1100--1199)
       XII  National Archives and Records Administration (Parts 
                1200--1299)
        XV  Oklahoma City National Memorial Trust (Parts 1500--
                1599)
       XVI  Morris K. Udall Scholarship and Excellence in National 
                Environmental Policy Foundation (Parts 1600--1699)

             Title 37--Patents, Trademarks, and Copyrights

         I  United States Patent and Trademark Office, Department 
                of Commerce (Parts 1--199)
        II  U.S. Copyright Office, Library of Congress (Parts 
                200--299)
       III  Copyright Royalty Board, Library of Congress (Parts 
                300--399)
        IV  National Institute of Standards and Technology, 
                Department of Commerce (Parts 400--599)

[[Page 885]]

           Title 38--Pensions, Bonuses, and Veterans' Relief

         I  Department of Veterans Affairs (Parts 0--199)
        II  Armed Forces Retirement Home (Parts 200--299)

                       Title 39--Postal Service

         I  United States Postal Service (Parts 1--999)
       III  Postal Regulatory Commission (Parts 3000--3099)

                  Title 40--Protection of Environment

         I  Environmental Protection Agency (Parts 1--1099)
        IV  Environmental Protection Agency and Department of 
                Justice (Parts 1400--1499)
         V  Council on Environmental Quality (Parts 1500--1599)
        VI  Chemical Safety and Hazard Investigation Board (Parts 
                1600--1699)
       VII  Environmental Protection Agency and Department of 
                Defense; Uniform National Discharge Standards for 
                Vessels of the Armed Forces (Parts 1700--1799)
      VIII  Gulf Coast Ecosystem Restoration Council (Parts 1800--
                1899)

          Title 41--Public Contracts and Property Management

            Subtitle A--Federal Procurement Regulations System 
                [Note]
            Subtitle B--Other Provisions Relating to Public 
                Contracts
        50  Public Contracts, Department of Labor (Parts 50-1--50-
                999)
        51  Committee for Purchase From People Who Are Blind or 
                Severely Disabled (Parts 51-1--51-99)
        60  Office of Federal Contract Compliance Programs, Equal 
                Employment Opportunity, Department of Labor (Parts 
                60-1--60-999)
        61  Office of the Assistant Secretary for Veterans' 
                Employment and Training Service, Department of 
                Labor (Parts 61-1--61-999)
   62--100  [Reserved]
            Subtitle C--Federal Property Management Regulations 
                System
       101  Federal Property Management Regulations (Parts 101-1--
                101-99)
       102  Federal Management Regulation (Parts 102-1--102-299)
  103--104  [Reserved]
       105  General Services Administration (Parts 105-1--105-999)
       109  Department of Energy Property Management Regulations 
                (Parts 109-1--109-99)
       114  Department of the Interior (Parts 114-1--114-99)
       115  Environmental Protection Agency (Parts 115-1--115-99)
       128  Department of Justice (Parts 128-1--128-99)
  129--200  [Reserved]
            Subtitle D--Other Provisions Relating to Property 
                Management [Reserved]

[[Page 886]]

            Subtitle E--Federal Information Resources Management 
                Regulations System [Reserved]
            Subtitle F--Federal Travel Regulation System
       300  General (Parts 300-1--300-99)
       301  Temporary Duty (TDY) Travel Allowances (Parts 301-1--
                301-99)
       302  Relocation Allowances (Parts 302-1--302-99)
       303  Payment of Expenses Connected with the Death of 
                Certain Employees (Part 303-1--303-99)
       304  Payment of Travel Expenses from a Non-Federal Source 
                (Parts 304-1--304-99)

                        Title 42--Public Health

         I  Public Health Service, Department of Health and Human 
                Services (Parts 1--199)
   ii--III  [Reserved]
        IV  Centers for Medicare & Medicaid Services, Department 
                of Health and Human Services (Parts 400--699)
         V  Office of Inspector General-Health Care, Department of 
                Health and Human Services (Parts 1000--1099)

                   Title 43--Public Lands: Interior

            Subtitle A--Office of the Secretary of the Interior 
                (Parts 1--199)
            Subtitle B--Regulations Relating to Public Lands
         I  Bureau of Reclamation, Department of the Interior 
                (Parts 400--999)
        II  Bureau of Land Management, Department of the Interior 
                (Parts 1000--9999)
       III  Utah Reclamation Mitigation and Conservation 
                Commission (Parts 10000--10099)

             Title 44--Emergency Management and Assistance

         I  Federal Emergency Management Agency, Department of 
                Homeland Security (Parts 0--399)
        IV  Department of Commerce and Department of 
                Transportation (Parts 400--499)

                       Title 45--Public Welfare

            Subtitle A--Department of Health and Human Services 
                (Parts 1--199)
            Subtitle B--Regulations Relating to Public Welfare
        II  Office of Family Assistance (Assistance Programs), 
                Administration for Children and Families, 
                Department of Health and Human Services (Parts 
                200--299)

[[Page 887]]

       III  Office of Child Support Enforcement (Child Support 
                Enforcement Program), Administration for Children 
                and Families, Department of Health and Human 
                Services (Parts 300--399)
        IV  Office of Refugee Resettlement, Administration for 
                Children and Families, Department of Health and 
                Human Services (Parts 400--499)
         V  Foreign Claims Settlement Commission of the United 
                States, Department of Justice (Parts 500--599)
        VI  National Science Foundation (Parts 600--699)
       VII  Commission on Civil Rights (Parts 700--799)
      VIII  Office of Personnel Management (Parts 800--899)
        IX  Denali Commission (Parts 900--999)
         X  Office of Community Services, Administration for 
                Children and Families, Department of Health and 
                Human Services (Parts 1000--1099)
        XI  National Foundation on the Arts and the Humanities 
                (Parts 1100--1199)
       XII  Corporation for National and Community Service (Parts 
                1200--1299)
      XIII  Administration for Children and Families, Department 
                of Health and Human Services (Parts 1300--1399)
       XVI  Legal Services Corporation (Parts 1600--1699)
      XVII  National Commission on Libraries and Information 
                Science (Parts 1700--1799)
     XVIII  Harry S. Truman Scholarship Foundation (Parts 1800--
                1899)
       XXI  Commission of Fine Arts (Parts 2100--2199)
     XXIII  Arctic Research Commission (Part 2301)
      XXIV  James Madison Memorial Fellowship Foundation (Parts 
                2400--2499)
       XXV  Corporation for National and Community Service (Parts 
                2500--2599)

                          Title 46--Shipping

         I  Coast Guard, Department of Homeland Security (Parts 
                1--199)
        II  Maritime Administration, Department of Transportation 
                (Parts 200--399)
       III  Coast Guard (Great Lakes Pilotage), Department of 
                Homeland Security (Parts 400--499)
        IV  Federal Maritime Commission (Parts 500--599)

                      Title 47--Telecommunication

         I  Federal Communications Commission (Parts 0--199)
        II  Office of Science and Technology Policy and National 
                Security Council (Parts 200--299)
       III  National Telecommunications and Information 
                Administration, Department of Commerce (Parts 
                300--399)

[[Page 888]]

        IV  National Telecommunications and Information 
                Administration, Department of Commerce, and 
                National Highway Traffic Safety Administration, 
                Department of Transportation (Parts 400--499)
         V  The First Responder Network Authority (Parts 500--599)

           Title 48--Federal Acquisition Regulations System

         1  Federal Acquisition Regulation (Parts 1--99)
         2  Defense Acquisition Regulations System, Department of 
                Defense (Parts 200--299)
         3  Health and Human Services (Parts 300--399)
         4  Department of Agriculture (Parts 400--499)
         5  General Services Administration (Parts 500--599)
         6  Department of State (Parts 600--699)
         7  Agency for International Development (Parts 700--799)
         8  Department of Veterans Affairs (Parts 800--899)
         9  Department of Energy (Parts 900--999)
        10  Department of the Treasury (Parts 1000--1099)
        12  Department of Transportation (Parts 1200--1299)
        13  Department of Commerce (Parts 1300--1399)
        14  Department of the Interior (Parts 1400--1499)
        15  Environmental Protection Agency (Parts 1500--1599)
        16  Office of Personnel Management, Federal Employees 
                Health Benefits Acquisition Regulation (Parts 
                1600--1699)
        17  Office of Personnel Management (Parts 1700--1799)
        18  National Aeronautics and Space Administration (Parts 
                1800--1899)
        19  Broadcasting Board of Governors (Parts 1900--1999)
        20  Nuclear Regulatory Commission (Parts 2000--2099)
        21  Office of Personnel Management, Federal Employees 
                Group Life Insurance Federal Acquisition 
                Regulation (Parts 2100--2199)
        23  Social Security Administration (Parts 2300--2399)
        24  Department of Housing and Urban Development (Parts 
                2400--2499)
        25  National Science Foundation (Parts 2500--2599)
        28  Department of Justice (Parts 2800--2899)
        29  Department of Labor (Parts 2900--2999)
        30  Department of Homeland Security, Homeland Security 
                Acquisition Regulation (HSAR) (Parts 3000--3099)
        34  Department of Education Acquisition Regulation (Parts 
                3400--3499)
        51  Department of the Army Acquisition Regulations (Parts 
                5100--5199)
        52  Department of the Navy Acquisition Regulations (Parts 
                5200--5299)
        53  Department of the Air Force Federal Acquisition 
                Regulation Supplement (Parts 5300--5399) 
                [Reserved]

[[Page 889]]

        54  Defense Logistics Agency, Department of Defense (Parts 
                5400--5499)
        57  African Development Foundation (Parts 5700--5799)
        61  Civilian Board of Contract Appeals, General Services 
                Administration (Parts 6100--6199)
        99  Cost Accounting Standards Board, Office of Federal 
                Procurement Policy, Office of Management and 
                Budget (Parts 9900--9999)

                       Title 49--Transportation

            Subtitle A--Office of the Secretary of Transportation 
                (Parts 1--99)
            Subtitle B--Other Regulations Relating to 
                Transportation
         I  Pipeline and Hazardous Materials Safety 
                Administration, Department of Transportation 
                (Parts 100--199)
        II  Federal Railroad Administration, Department of 
                Transportation (Parts 200--299)
       III  Federal Motor Carrier Safety Administration, 
                Department of Transportation (Parts 300--399)
        IV  Coast Guard, Department of Homeland Security (Parts 
                400--499)
         V  National Highway Traffic Safety Administration, 
                Department of Transportation (Parts 500--599)
        VI  Federal Transit Administration, Department of 
                Transportation (Parts 600--699)
       VII  National Railroad Passenger Corporation (AMTRAK) 
                (Parts 700--799)
      VIII  National Transportation Safety Board (Parts 800--999)
         X  Surface Transportation Board (Parts 1000--1399)
        XI  Research and Innovative Technology Administration, 
                Department of Transportation (Parts 1400--1499) 
                [Reserved]
       XII  Transportation Security Administration, Department of 
                Homeland Security (Parts 1500--1699)

                   Title 50--Wildlife and Fisheries

         I  United States Fish and Wildlife Service, Department of 
                the Interior (Parts 1--199)
        II  National Marine Fisheries Service, National Oceanic 
                and Atmospheric Administration, Department of 
                Commerce (Parts 200--299)
       III  International Fishing and Related Activities (Parts 
                300--399)
        IV  Joint Regulations (United States Fish and Wildlife 
                Service, Department of the Interior and National 
                Marine Fisheries Service, National Oceanic and 
                Atmospheric Administration, Department of 
                Commerce); Endangered Species Committee 
                Regulations (Parts 400--499)
         V  Marine Mammal Commission (Parts 500--599)

[[Page 890]]

        VI  Fishery Conservation and Management, National Oceanic 
                and Atmospheric Administration, Department of 
                Commerce (Parts 600--699)

[[Page 891]]





           Alphabetical List of Agencies Appearing in the CFR




                     (Revised as of January 1, 2018)

                                                  CFR Title, Subtitle or 
                     Agency                               Chapter

Administrative Committee of the Federal Register  1, I
Administrative Conference of the United States    1, III
Advisory Council on Historic Preservation         36, VIII
Advocacy and Outreach, Office of                  7, XXV
Afghanistan Reconstruction, Special Inspector     5, LXXXIII
     General for
African Development Foundation                    22, XV
  Federal Acquisition Regulation                  48, 57
Agency for International Development              2, VII; 22, II
  Federal Acquisition Regulation                  48, 7
Agricultural Marketing Service                    7, I, IX, X, XI
Agricultural Research Service                     7, V
Agriculture Department                            2, IV; 5, LXXIII
  Advocacy and Outreach, Office of                7, XXV
  Agricultural Marketing Service                  7, I, IX, X, XI
  Agricultural Research Service                   7, V
  Animal and Plant Health Inspection Service      7, III; 9, I
  Chief Financial Officer, Office of              7, XXX
  Commodity Credit Corporation                    7, XIV
  Economic Research Service                       7, XXXVII
  Energy Policy and New Uses, Office of           2, IX; 7, XXIX
  Environmental Quality, Office of                7, XXXI
  Farm Service Agency                             7, VII, XVIII
  Federal Acquisition Regulation                  48, 4
  Federal Crop Insurance Corporation              7, IV
  Food and Nutrition Service                      7, II
  Food Safety and Inspection Service              9, III
  Foreign Agricultural Service                    7, XV
  Forest Service                                  36, II
  Grain Inspection, Packers and Stockyards        7, VIII; 9, II
       Administration
  Information Resources Management, Office of     7, XXVII
  Inspector General, Office of                    7, XXVI
  National Agricultural Library                   7, XLI
  National Agricultural Statistics Service        7, XXXVI
  National Institute of Food and Agriculture      7, XXXIV
  Natural Resources Conservation Service          7, VI
  Operations, Office of                           7, XXVIII
  Procurement and Property Management, Office of  7, XXXII
  Rural Business-Cooperative Service              7, XVIII, XLII
  Rural Development Administration                7, XLII
  Rural Housing Service                           7, XVIII, XXXV
  Rural Telephone Bank                            7, XVI
  Rural Utilities Service                         7, XVII, XVIII, XLII
  Secretary of Agriculture, Office of             7, Subtitle A
  Transportation, Office of                       7, XXXIII
  World Agricultural Outlook Board                7, XXXVIII
Air Force Department                              32, VII
  Federal Acquisition Regulation Supplement       48, 53
Air Transportation Stabilization Board            14, VI
Alcohol and Tobacco Tax and Trade Bureau          27, I
Alcohol, Tobacco, Firearms, and Explosives,       27, II
     Bureau of
AMTRAK                                            49, VII
American Battle Monuments Commission              36, IV
American Indians, Office of the Special Trustee   25, VII

[[Page 892]]

Animal and Plant Health Inspection Service        7, III; 9, I
Appalachian Regional Commission                   5, IX
Architectural and Transportation Barriers         36, XI
     Compliance Board
Arctic Research Commission                        45, XXIII
Armed Forces Retirement Home                      5, XI
Army Department                                   32, V
  Engineers, Corps of                             33, II; 36, III
  Federal Acquisition Regulation                  48, 51
Bilingual Education and Minority Languages        34, V
     Affairs, Office of
Blind or Severely Disabled, Committee for         41, 51
     Purchase from People Who Are
Broadcasting Board of Governors                   22, V
  Federal Acquisition Regulation                  48, 19
Career, Technical and Adult Education, Office of  34, IV
Census Bureau                                     15, I
Centers for Medicare & Medicaid Services          42, IV
Central Intelligence Agency                       32, XIX
Chemical Safety and Hazardous Investigation       40, VI
     Board
Chief Financial Officer, Office of                7, XXX
Child Support Enforcement, Office of              45, III
Children and Families, Administration for         45, II, III, IV, X, XIII
Civil Rights, Commission on                       5, LXVIII; 45, VII
Civil Rights, Office for                          34, I
Council of the Inspectors General on Integrity    5, XCVIII
     and Efficiency
Court Services and Offender Supervision Agency    5, LXX
     for the District of Columbia
Coast Guard                                       33, I; 46, I; 49, IV
Coast Guard (Great Lakes Pilotage)                46, III
Commerce Department                               2, XIII; 44, IV; 50, VI
  Census Bureau                                   15, I
  Economic Analysis, Bureau of                    15, VIII
  Economic Development Administration             13, III
  Emergency Management and Assistance             44, IV
  Federal Acquisition Regulation                  48, 13
  Foreign-Trade Zones Board                       15, IV
  Industry and Security, Bureau of                15, VII
  International Trade Administration              15, III; 19, III
  National Institute of Standards and Technology  15, II; 37, IV
  National Marine Fisheries Service               50, II, IV
  National Oceanic and Atmospheric                15, IX; 50, II, III, IV, 
       Administration                             VI
  National Technical Information Service          15, XI
  National Telecommunications and Information     15, XXIII; 47, III, IV
       Administration
  National Weather Service                        15, IX
  Patent and Trademark Office, United States      37, I
  Secretary of Commerce, Office of                15, Subtitle A
Commercial Space Transportation                   14, III
Commodity Credit Corporation                      7, XIV
Commodity Futures Trading Commission              5, XLI; 17, I
Community Planning and Development, Office of     24, V, VI
     Assistant Secretary for
Community Services, Office of                     45, X
Comptroller of the Currency                       12, I
Construction Industry Collective Bargaining       29, IX
     Commission
Consumer Financial Protection Bureau              5, LXXXIV; 12, X
Consumer Product Safety Commission                5, LXXI; 16, II
Copyright Royalty Board                           37, III
Corporation for National and Community Service    2, XXII; 45, XII, XXV
Cost Accounting Standards Board                   48, 99
Council on Environmental Quality                  40, V
Court Services and Offender Supervision Agency    5, LXX; 28, VIII
     for the District of Columbia
Customs and Border Protection                     19, I
Defense Contract Audit Agency                     32, I
Defense Department                                2, XI; 5, XXVI; 32, 
                                                  Subtitle A; 40, VII
  Advanced Research Projects Agency               32, I

[[Page 893]]

  Air Force Department                            32, VII
  Army Department                                 32, V; 33, II; 36, III; 
                                                  48, 51
  Defense Acquisition Regulations System          48, 2
  Defense Intelligence Agency                     32, I
  Defense Logistics Agency                        32, I, XII; 48, 54
  Engineers, Corps of                             33, II; 36, III
  National Imagery and Mapping Agency             32, I
  Navy Department                                 32, VI; 48, 52
  Secretary of Defense, Office of                 2, XI; 32, I
Defense Contract Audit Agency                     32, I
Defense Intelligence Agency                       32, I
Defense Logistics Agency                          32, XII; 48, 54
Defense Nuclear Facilities Safety Board           10, XVII
Delaware River Basin Commission                   18, III
Denali Commission                                 45, IX
District of Columbia, Court Services and          5, LXX; 28, VIII
     Offender Supervision Agency for the
Drug Enforcement Administration                   21, II
East-West Foreign Trade Board                     15, XIII
Economic Analysis, Bureau of                      15, VIII
Economic Development Administration               13, III
Economic Research Service                         7, XXXVII
Education, Department of                          2, XXXIV; 5, LIII
  Bilingual Education and Minority Languages      34, V
       Affairs, Office of
  Career, Technical and Adult Education, Office   34, IV
       of
  Civil Rights, Office for                        34, I
  Educational Research and Improvement, Office    34, VII
       of
  Elementary and Secondary Education, Office of   34, II
  Federal Acquisition Regulation                  48, 34
  Postsecondary Education, Office of              34, VI
  Secretary of Education, Office of               34, Subtitle A
  Special Education and Rehabilitative Services,  34, III
       Office of
  Career, Technical, and Adult Education, Office  34, IV
       of
Educational Research and Improvement, Office of   34, VII
Election Assistance Commission                    2, LVIII; 11, II
Elementary and Secondary Education, Office of     34, II
Emergency Oil and Gas Guaranteed Loan Board       13, V
Emergency Steel Guarantee Loan Board              13, IV
Employee Benefits Security Administration         29, XXV
Employees' Compensation Appeals Board             20, IV
Employees Loyalty Board                           5, V
Employment and Training Administration            20, V
Employment Standards Administration               20, VI
Endangered Species Committee                      50, IV
Energy, Department of                             2, IX; 5, XXIII; 10, II, 
                                                  III, X
  Federal Acquisition Regulation                  48, 9
  Federal Energy Regulatory Commission            5, XXIV; 18, I
  Property Management Regulations                 41, 109
Energy, Office of                                 7, XXIX
Engineers, Corps of                               33, II; 36, III
Engraving and Printing, Bureau of                 31, VI
Environmental Protection Agency                   2, XV; 5, LIV; 40, I, IV, 
                                                  VII
  Federal Acquisition Regulation                  48, 15
  Property Management Regulations                 41, 115
Environmental Quality, Office of                  7, XXXI
Equal Employment Opportunity Commission           5, LXII; 29, XIV
Equal Opportunity, Office of Assistant Secretary  24, I
     for
Executive Office of the President                 3, I
  Environmental Quality, Council on               40, V
  Management and Budget, Office of                2, Subtitle A; 5, III, 
                                                  LXXVII; 14, VI; 48, 99
  National Drug Control Policy, Office of         2, XXXVI; 21, III
  National Security Council                       32, XXI; 47, 2

[[Page 894]]

  Presidential Documents                          3
  Science and Technology Policy, Office of        32, XXIV; 47, II
  Trade Representative, Office of the United      15, XX
       States
Export-Import Bank of the United States           2, XXXV; 5, LII; 12, IV
Family Assistance, Office of                      45, II
Farm Credit Administration                        5, XXXI; 12, VI
Farm Credit System Insurance Corporation          5, XXX; 12, XIV
Farm Service Agency                               7, VII, XVIII
Federal Acquisition Regulation                    48, 1
Federal Aviation Administration                   14, I
  Commercial Space Transportation                 14, III
Federal Claims Collection Standards               31, IX
Federal Communications Commission                 5, XXIX; 47, I
Federal Contract Compliance Programs, Office of   41, 60
Federal Crop Insurance Corporation                7, IV
Federal Deposit Insurance Corporation             5, XXII; 12, III
Federal Election Commission                       5, XXXVII; 11, I
Federal Emergency Management Agency               44, I
Federal Employees Group Life Insurance Federal    48, 21
     Acquisition Regulation
Federal Employees Health Benefits Acquisition     48, 16
     Regulation
Federal Energy Regulatory Commission              5, XXIV; 18, I
Federal Financial Institutions Examination        12, XI
     Council
Federal Financing Bank                            12, VIII
Federal Highway Administration                    23, I, II
Federal Home Loan Mortgage Corporation            1, IV
Federal Housing Enterprise Oversight Office       12, XVII
Federal Housing Finance Agency                    5, LXXX; 12, XII
Federal Housing Finance Board                     12, IX
Federal Labor Relations Authority                 5, XIV, XLIX; 22, XIV
Federal Law Enforcement Training Center           31, VII
Federal Management Regulation                     41, 102
Federal Maritime Commission                       46, IV
Federal Mediation and Conciliation Service        29, XII
Federal Mine Safety and Health Review Commission  5, LXXIV; 29, XXVII
Federal Motor Carrier Safety Administration       49, III
Federal Prison Industries, Inc.                   28, III
Federal Procurement Policy Office                 48, 99
Federal Property Management Regulations           41, 101
Federal Railroad Administration                   49, II
Federal Register, Administrative Committee of     1, I
Federal Register, Office of                       1, II
Federal Reserve System                            12, II
  Board of Governors                              5, LVIII
Federal Retirement Thrift Investment Board        5, VI, LXXVI
Federal Service Impasses Panel                    5, XIV
Federal Trade Commission                          5, XLVII; 16, I
Federal Transit Administration                    49, VI
Federal Travel Regulation System                  41, Subtitle F
Financial Crimes Enforcement Network              31, X
Financial Research Office                         12, XVI
Financial Stability Oversight Council             12, XIII
Fine Arts, Commission of                          45, XXI
Fiscal Service                                    31, II
Fish and Wildlife Service, United States          50, I, IV
Food and Drug Administration                      21, I
Food and Nutrition Service                        7, II
Food Safety and Inspection Service                9, III
Foreign Agricultural Service                      7, XV
Foreign Assets Control, Office of                 31, V
Foreign Claims Settlement Commission of the       45, V
     United States
Foreign Service Grievance Board                   22, IX
Foreign Service Impasse Disputes Panel            22, XIV
Foreign Service Labor Relations Board             22, XIV
Foreign-Trade Zones Board                         15, IV
Forest Service                                    36, II
General Services Administration                   5, LVII; 41, 105

[[Page 895]]

  Contract Appeals, Board of                      48, 61
  Federal Acquisition Regulation                  48, 5
  Federal Management Regulation                   41, 102
  Federal Property Management Regulations         41, 101
  Federal Travel Regulation System                41, Subtitle F
  General                                         41, 300
  Payment From a Non-Federal Source for Travel    41, 304
       Expenses
  Payment of Expenses Connected With the Death    41, 303
       of Certain Employees
  Relocation Allowances                           41, 302
  Temporary Duty (TDY) Travel Allowances          41, 301
Geological Survey                                 30, IV
Government Accountability Office                  4, I
Government Ethics, Office of                      5, XVI
Government National Mortgage Association          24, III
Grain Inspection, Packers and Stockyards          7, VIII; 9, II
     Administration
Gulf Coast Ecosystem Restoration Council          2, LIX; 40, VIII
Harry S. Truman Scholarship Foundation            45, XVIII
Health and Human Services, Department of          2, III; 5, XLV; 45, 
                                                  Subtitle A
  Centers for Medicare & Medicaid Services        42, IV
  Child Support Enforcement, Office of            45, III
  Children and Families, Administration for       45, II, III, IV, X, XIII
  Community Services, Office of                   45, X
  Family Assistance, Office of                    45, II
  Federal Acquisition Regulation                  48, 3
  Food and Drug Administration                    21, I
  Indian Health Service                           25, V
  Inspector General (Health Care), Office of      42, V
  Public Health Service                           42, I
  Refugee Resettlement, Office of                 45, IV
Homeland Security, Department of                  2, XXX; 5, XXXVI; 6, I; 8, 
                                                  I
  Coast Guard                                     33, I; 46, I; 49, IV
  Coast Guard (Great Lakes Pilotage)              46, III
  Customs and Border Protection                   19, I
  Federal Emergency Management Agency             44, I
  Human Resources Management and Labor Relations  5, XCVII
       Systems
  Immigration and Customs Enforcement Bureau      19, IV
  Transportation Security Administration          49, XII
HOPE for Homeowners Program, Board of Directors   24, XXIV
     of
Housing and Urban Development, Department of      2, XXIV; 5, LXV; 24, 
                                                  Subtitle B
  Community Planning and Development, Office of   24, V, VI
       Assistant Secretary for
  Equal Opportunity, Office of Assistant          24, I
       Secretary for
  Federal Acquisition Regulation                  48, 24
  Federal Housing Enterprise Oversight, Office    12, XVII
       of
  Government National Mortgage Association        24, III
  Housing--Federal Housing Commissioner, Office   24, II, VIII, X, XX
       of Assistant Secretary for
  Housing, Office of, and Multifamily Housing     24, IV
       Assistance Restructuring, Office of
  Inspector General, Office of                    24, XII
  Public and Indian Housing, Office of Assistant  24, IX
       Secretary for
  Secretary, Office of                            24, Subtitle A, VII
Housing--Federal Housing Commissioner, Office of  24, II, VIII, X, XX
     Assistant Secretary for
Housing, Office of, and Multifamily Housing       24, IV
     Assistance Restructuring, Office of
Immigration and Customs Enforcement Bureau        19, IV
Immigration Review, Executive Office for          8, V
Independent Counsel, Office of                    28, VII
Independent Counsel, Offices of                   28, VI
Indian Affairs, Bureau of                         25, I, V
Indian Affairs, Office of the Assistant           25, VI
   Secretary
[[Page 896]]

Indian Arts and Crafts Board                      25, II
Indian Health Service                             25, V
Industry and Security, Bureau of                  15, VII
Information Resources Management, Office of       7, XXVII
Information Security Oversight Office, National   32, XX
     Archives and Records Administration
Inspector General
  Agriculture Department                          7, XXVI
  Health and Human Services Department            42, V
  Housing and Urban Development Department        24, XII, XV
Institute of Peace, United States                 22, XVII
Inter-American Foundation                         5, LXIII; 22, X
Interior Department                               2, XIV
  American Indians, Office of the Special         25, VII
       Trustee
  Endangered Species Committee                    50, IV
  Federal Acquisition Regulation                  48, 14
  Federal Property Management Regulations System  41, 114
  Fish and Wildlife Service, United States        50, I, IV
  Geological Survey                               30, IV
  Indian Affairs, Bureau of                       25, I, V
  Indian Affairs, Office of the Assistant         25, VI
       Secretary
  Indian Arts and Crafts Board                    25, II
  Land Management, Bureau of                      43, II
  National Indian Gaming Commission               25, III
  National Park Service                           36, I
  Natural Resource Revenue, Office of             30, XII
  Ocean Energy Management, Bureau of              30, V
  Reclamation, Bureau of                          43, I
  Safety and Enforcement Bureau, Bureau of        30, II
  Secretary of the Interior, Office of            2, XIV; 43, Subtitle A
  Surface Mining Reclamation and Enforcement,     30, VII
       Office of
Internal Revenue Service                          26, I
International Boundary and Water Commission,      22, XI
     United States and Mexico, United States 
     Section
International Development, United States Agency   22, II
     for
  Federal Acquisition Regulation                  48, 7
International Development Cooperation Agency,     22, XII
     United States
International Joint Commission, United States     22, IV
     and Canada
International Organizations Employees Loyalty     5, V
     Board
International Trade Administration                15, III; 19, III
International Trade Commission, United States     19, II
Interstate Commerce Commission                    5, XL
Investment Security, Office of                    31, VIII
James Madison Memorial Fellowship Foundation      45, XXIV
Japan-United States Friendship Commission         22, XVI
Joint Board for the Enrollment of Actuaries       20, VIII
Justice Department                                2, XXVIII; 5, XXVIII; 28, 
                                                  I, XI; 40, IV
  Alcohol, Tobacco, Firearms, and Explosives,     27, II
       Bureau of
  Drug Enforcement Administration                 21, II
  Federal Acquisition Regulation                  48, 28
  Federal Claims Collection Standards             31, IX
  Federal Prison Industries, Inc.                 28, III
  Foreign Claims Settlement Commission of the     45, V
       United States
  Immigration Review, Executive Office for        8, V
  Independent Counsel, Offices of                 28, VI
  Prisons, Bureau of                              28, V
  Property Management Regulations                 41, 128
Labor Department                                  2, XXIX; 5, XLII
  Employee Benefits Security Administration       29, XXV
  Employees' Compensation Appeals Board           20, IV
  Employment and Training Administration          20, V
  Employment Standards Administration             20, VI
  Federal Acquisition Regulation                  48, 29
  Federal Contract Compliance Programs, Office    41, 60
     of
[[Page 897]]

  Federal Procurement Regulations System          41, 50
  Labor-Management Standards, Office of           29, II, IV
  Mine Safety and Health Administration           30, I
  Occupational Safety and Health Administration   29, XVII
  Public Contracts                                41, 50
  Secretary of Labor, Office of                   29, Subtitle A
  Veterans' Employment and Training Service,      41, 61; 20, IX
       Office of the Assistant Secretary for
  Wage and Hour Division                          29, V
  Workers' Compensation Programs, Office of       20, I, VII
Labor-Management Standards, Office of             29, II, IV
Land Management, Bureau of                        43, II
Legal Services Corporation                        45, XVI
Library of Congress                               36, VII
  Copyright Royalty Board                         37, III
  U.S. Copyright Office                           37, II
Local Television Loan Guarantee Board             7, XX
Management and Budget, Office of                  5, III, LXXVII; 14, VI; 
                                                  48, 99
Marine Mammal Commission                          50, V
Maritime Administration                           46, II
Merit Systems Protection Board                    5, II, LXIV
Micronesian Status Negotiations, Office for       32, XXVII
Military Compensation and Retirement              5, XCIX
     Modernization Commission
Millennium Challenge Corporation                  22, XIII
Mine Safety and Health Administration             30, I
Minority Business Development Agency              15, XIV
Miscellaneous Agencies                            1, IV
Monetary Offices                                  31, I
Morris K. Udall Scholarship and Excellence in     36, XVI
     National Environmental Policy Foundation
Museum and Library Services, Institute of         2, XXXI
National Aeronautics and Space Administration     2, XVIII; 5, LIX; 14, V
  Federal Acquisition Regulation                  48, 18
National Agricultural Library                     7, XLI
National Agricultural Statistics Service          7, XXXVI
National and Community Service, Corporation for   2, XXII; 45, XII, XXV
National Archives and Records Administration      2, XXVI; 5, LXVI; 36, XII
  Information Security Oversight Office           32, XX
National Capital Planning Commission              1, IV, VI
National Commission for Employment Policy         1, IV
National Commission on Libraries and Information  45, XVII
     Science
National Council on Disability                    5, C; 34, XII
National Counterintelligence Center               32, XVIII
National Credit Union Administration              5, LXXXVI; 12, VII
National Crime Prevention and Privacy Compact     28, IX
     Council
National Drug Control Policy, Office of           2, XXXVI; 21, III
National Endowment for the Arts                   2, XXXII
National Endowment for the Humanities             2, XXXIII
National Foundation on the Arts and the           45, XI
     Humanities
National Geospatial-Intelligence Agency           32, I
National Highway Traffic Safety Administration    23, II, III; 47, VI; 49, V
National Imagery and Mapping Agency               32, I
National Indian Gaming Commission                 25, III
National Institute of Food and Agriculture        7, XXXIV
National Institute of Standards and Technology    15, II; 37, IV
National Intelligence, Office of Director of      5, IV; 32, XVII
National Labor Relations Board                    5, LXI; 29, I
National Marine Fisheries Service                 50, II, IV
National Mediation Board                          29, X
National Oceanic and Atmospheric Administration   15, IX; 50, II, III, IV, 
                                                  VI
National Park Service                             36, I
National Railroad Adjustment Board                29, III
National Railroad Passenger Corporation (AMTRAK)  49, VII
National Science Foundation                       2, XXV; 5, XLIII; 45, VI

[[Page 898]]

  Federal Acquisition Regulation                  48, 25
National Security Council                         32, XXI
National Security Council and Office of Science   47, II
     and Technology Policy
National Telecommunications and Information       15, XXIII; 47, III, IV, V
     Administration
National Transportation Safety Board              49, VIII
Natural Resources Conservation Service            7, VI
Natural Resource Revenue, Office of               30, XII
Navajo and Hopi Indian Relocation, Office of      25, IV
Navy Department                                   32, VI
  Federal Acquisition Regulation                  48, 52
Neighborhood Reinvestment Corporation             24, XXV
Northeast Interstate Low-Level Radioactive Waste  10, XVIII
     Commission
Nuclear Regulatory Commission                     2, XX; 5, XLVIII; 10, I
  Federal Acquisition Regulation                  48, 20
Occupational Safety and Health Administration     29, XVII
Occupational Safety and Health Review Commission  29, XX
Ocean Energy Management, Bureau of                30, V
Oklahoma City National Memorial Trust             36, XV
Operations Office                                 7, XXVIII
Overseas Private Investment Corporation           5, XXXIII; 22, VII
Patent and Trademark Office, United States        37, I
Payment From a Non-Federal Source for Travel      41, 304
     Expenses
Payment of Expenses Connected With the Death of   41, 303
     Certain Employees
Peace Corps                                       2, XXXVII; 22, III
Pennsylvania Avenue Development Corporation       36, IX
Pension Benefit Guaranty Corporation              29, XL
Personnel Management, Office of                   5, I, XXXV; 5, IV; 45, 
                                                  VIII
  Human Resources Management and Labor Relations  5, XCVII
       Systems, Department of Homeland Security
  Federal Acquisition Regulation                  48, 17
  Federal Employees Group Life Insurance Federal  48, 21
       Acquisition Regulation
  Federal Employees Health Benefits Acquisition   48, 16
       Regulation
Pipeline and Hazardous Materials Safety           49, I
     Administration
Postal Regulatory Commission                      5, XLVI; 39, III
Postal Service, United States                     5, LX; 39, I
Postsecondary Education, Office of                34, VI
President's Commission on White House             1, IV
     Fellowships
Presidential Documents                            3
Presidio Trust                                    36, X
Prisons, Bureau of                                28, V
Privacy and Civil Liberties Oversight Board       6, X
Procurement and Property Management, Office of    7, XXXII
Public Contracts, Department of Labor             41, 50
Public and Indian Housing, Office of Assistant    24, IX
     Secretary for
Public Health Service                             42, I
Railroad Retirement Board                         20, II
Reclamation, Bureau of                            43, I
Refugee Resettlement, Office of                   45, IV
Relocation Allowances                             41, 302
Research and Innovative Technology                49, XI
     Administration
Rural Business-Cooperative Service                7, XVIII, XLII
Rural Development Administration                  7, XLII
Rural Housing Service                             7, XVIII, XXXV
Rural Telephone Bank                              7, XVI
Rural Utilities Service                           7, XVII, XVIII, XLII
Safety and Environmental Enforcement, Bureau of   30, II
Saint Lawrence Seaway Development Corporation     33, IV
Science and Technology Policy, Office of          32, XXIV
Science and Technology Policy, Office of, and     47, II
     National Security Council
Secret Service                                    31, IV

[[Page 899]]

Securities and Exchange Commission                5, XXXIV; 17, II
Selective Service System                          32, XVI
Small Business Administration                     2, XXVII; 13, I
Smithsonian Institution                           36, V
Social Security Administration                    2, XXIII; 20, III; 48, 23
Soldiers' and Airmen's Home, United States        5, XI
Special Counsel, Office of                        5, VIII
Special Education and Rehabilitative Services,    34, III
     Office of
State Department                                  2, VI; 22, I; 28, XI
  Federal Acquisition Regulation                  48, 6
Surface Mining Reclamation and Enforcement,       30, VII
     Office of
Surface Transportation Board                      49, X
Susquehanna River Basin Commission                18, VIII
Tennessee Valley Authority                        5, LXIX; 18, XIII
Thrift Supervision Office, Department of the      12, V
     Treasury
Trade Representative, United States, Office of    15, XX
Transportation, Department of                     2, XII; 5, L
  Commercial Space Transportation                 14, III
  Emergency Management and Assistance             44, IV
  Federal Acquisition Regulation                  48, 12
  Federal Aviation Administration                 14, I
  Federal Highway Administration                  23, I, II
  Federal Motor Carrier Safety Administration     49, III
  Federal Railroad Administration                 49, II
  Federal Transit Administration                  49, VI
  Maritime Administration                         46, II
  National Highway Traffic Safety Administration  23, II, III; 47, IV; 49, V
  Pipeline and Hazardous Materials Safety         49, I
       Administration
  Saint Lawrence Seaway Development Corporation   33, IV
  Secretary of Transportation, Office of          14, II; 49, Subtitle A
  Transportation Statistics Bureau                49, XI
Transportation, Office of                         7, XXXIII
Transportation Security Administration            49, XII
Transportation Statistics Bureau                  49, XI
Travel Allowances, Temporary Duty (TDY)           41, 301
Treasury Department                               2, X;5, XXI; 12, XV; 17, 
                                                  IV; 31, IX
  Alcohol and Tobacco Tax and Trade Bureau        27, I
  Community Development Financial Institutions    12, XVIII
       Fund
  Comptroller of the Currency                     12, I
  Customs and Border Protection                   19, I
  Engraving and Printing, Bureau of               31, VI
  Federal Acquisition Regulation                  48, 10
  Federal Claims Collection Standards             31, IX
  Federal Law Enforcement Training Center         31, VII
  Financial Crimes Enforcement Network            31, X
  Fiscal Service                                  31, II
  Foreign Assets Control, Office of               31, V
  Internal Revenue Service                        26, I
  Investment Security, Office of                  31, VIII
  Monetary Offices                                31, I
  Secret Service                                  31, IV
  Secretary of the Treasury, Office of            31, Subtitle A
  Thrift Supervision, Office of                   12, V
Truman, Harry S. Scholarship Foundation           45, XVIII
United States and Canada, International Joint     22, IV
     Commission
United States and Mexico, International Boundary  22, XI
     and Water Commission, United States Section
U.S. Copyright Office                             37, II
Utah Reclamation Mitigation and Conservation      43, III
     Commission
Veterans Affairs Department                       2, VIII; 38, I
  Federal Acquisition Regulation                  48, 8
Veterans' Employment and Training Service,        41, 61; 20, IX
     Office of the Assistant Secretary for
Vice President of the United States, Office of    32, XXVIII
Wage and Hour Division                            29, V
Water Resources Council                           18, VI

[[Page 900]]

Workers' Compensation Programs, Office of         20, I, VII
World Agricultural Outlook Board                  7, XXXVIII

[[Page 901]]



List of CFR Sections Affected



All changes in this volume of the Code of Federal Regulations (CFR) that 
were made by documents published in the Federal Register since January 
1, 2013 are enumerated in the following list. Entries indicate the 
nature of the changes effected. Page numbers refer to Federal Register 
pages. The user should consult the entries for chapters, parts and 
subparts as well as sections for revisions.
For changes to this volume of the CFR prior to this listing, consult the 
annual edition of the monthly List of CFR Sections Affected (LSA). The 
LSA is available at www.fdsys.gov. For changes to this volume of the CFR 
prior to 2001, see the ``List of CFR Sections Affected, 1949-1963, 1964-
1972, 1973-1985, and 1986-2000'' published in 11 separate volumes. The 
``List of CFR Sections Affected 1986-2000'' is available at 
www.fdsys.gov.

                                  2013

10 CFR
                                                                   78 FR
                                                                    Page
Chapter I
51 Authority citation revised......................................37316
    Policy statement........................................37324, 37325
    Authority citation correctly revised...........................46256
51.22 (c)(3) introductory text.....................................17021
    (c)(9) introductory text revised...............................34249
51.53 (c)(2), (3)(ii)(A) and (B) amended; (c)(3)(ii)(C), (E), (G) 
        and (K) revised; (c)(3)(ii)(F), (I) and (J) removed; 
        (c)(3)(ii)(N), (O) and (P) added...........................37316
51.71 (d) revised..................................................37317
51.95(c) introductory text revised; (c)(4) amended.................37317
51 Appendix B amended..............................................37317
52.17 (b)(2)(i) and (ii) revised...................................34249
    (b)(2)(i) and (ii) correctly revised...........................75450
52.18 Amended......................................................34249
    Correctly amended..............................................75450
52.79 (b)(4) amended...............................................34249
52.163 Amended.....................................................34249
54 Policy statement................................................37324
70 Policy statement..................................................663
    Policy statement; interim......................................33691
70.5 (b)(1)(iv) revised............................................32341
70.25 (f)(2) introductory text revised.............................34250
    (f)(2) introductory text correctly amended.....................75450
71.97 (b) introductory text revised................................17021
    Implementation (temporary).....................................35746
72 Policy statement..................................................663
72.214 Amended..............................................16604, 37930
    Correctly amended..............................................22413
    Regulation at 78 FR 16604 withdrawn............................32077
    Amended; eff. 1-7-14...........................................63379
    Amended; eff. 2-19-14..........................................73382
    Technical correction; Regulation at 78 FR 73382 eff. date 
delayed to 3-11-14; eff 1-7-14.....................................78165
    Regulation at 78 FR 63379 eff. date confirmed..................78693
73 Policy statement................................................31821
    Orders.........................................................50313
73.6 (a) and (b) revised...........................................34250
73.8 (b) revised...................................................29550
73.35 Added........................................................17021
73.37 Revised......................................................29550
    Implementation (temporary).....................................35746
73.38 Added........................................................29553
73.71 (a)(1) footnote 1 redesignated as (a)(1) footnote 3..........29557
73.72 (a) introductory text, (1), (4), (5) and (b) revised.........29557
95.33 Revised......................................................48041
    Regulation at 78 FR 48041 eff. date confirmed..................69286
100.20 (b) revised.................................................34250
100.21 (d) and (e) revised.........................................34250
100 Appendix A amended.............................................34250
110 Policy statement...............................................53020

[[Page 902]]

110.29 Amended......................................................8361
140.11 (a)(4) revised..............................................41836
170 Policy statement; interim......................................33691
170.20 Revised.....................................................39481
170.21 Table revised...............................................39481
170.31 Table amended...............................................32341
    Table revised..................................................39482
    Table correctly amended........................................54959
171 Policy statement; interim......................................33691
171.15 (b)(1), (2) introductory text, (c)(1), (2) introductory 
        text, (d)(1) introductory text, (2), (3) and (3) revised 
                                                                   39487
171.16 (d) table amended...........................................32342
    (c) introductory text, (d) introductory text and (e) 
introductory text revised..........................................39487
171.19 (d) revised.................................................39491

                                  2014

10 CFR
                                                                   79 FR
                                                                    Page
Chapter I
51 Nomenclature change.............................................75740
51.23 Heading, (a) and (b) revised.................................56260
51.30 (b) revised..................................................56260
51.34 (b) revised..................................................66604
51.50 (a), (b)(2) and (c) introductory text revised................56260
51.52 Footnote 1 revised...........................................66604
51.53 (b), (c)(2) and (d) revised..................................56260
    (d) amended....................................................66604
51.61 Revised......................................................56261
51.75 (a), (b) and (c) introductory text revised...................56261
51.80 (b)(1) revised...............................................56262
51.95 (b), (c)(2) and (d) revised..................................56262
51.97 (a) revised..................................................56262
51.102 (c) revised.................................................66604
51.10--51.125 (Subpart A) Appendix A amended.......................56262
51 Policy statement................................................56263
52 Policy statement................................................71295
52.1 (a) amended...................................................66604
52.5 (e)(2) revised................................................66604
52.11 (b) revised..................................................61983
52 Appendix E added................................................61983
55.5 (b)(3) revised................................................66604
55.40 (d) revised..................................................66604
55.53 (j) amended..................................................66605
55.55 (b) revised..................................................66605
60.9 (e)(2) revised................................................66605
61 Nomenclature change.............................................75740
61.9 (e)(2) revised................................................66605
62 Nomenclature change.............................................75740
63.9 (e)(2) revised................................................66605
70 Nomenclature change.............................................75740
70.7 (e)(3) revised................................................66605
70.50 (c)(2) introductory text amended; eff. 1-26-15...............57725
70.74 (b) revised; eff. 1-26-15....................................57725
70 Appendix A amended; eff. 1-26-15................................57725
71 Nomenclature changes............................................75741
71.9 (e)(2) revised................................................66605
72 Authority citation revised...............................21125, 44267
    Technical correction...........................................25486
    Regulation at 79 FR 21125 withdrawn............................35911
    Regulation at 79 FR 44267 eff. date confirmed..................58672
    Nomenclature changes...........................................75741
72.10 (e)(2) revised...............................................66606
72.214 Regulation at 78 FR 73382 and 78165 confirmed...............12362
    Amended.....................13196, 21125, 44267, 53284, 59626, 66606
    Correctly amended..............................................20754
    Regulation at 79 FR 13196 eff. date confirmed..................28393
    Regulation at 79 FR 21125 withdrawn............................35911
    Regulation at 79 FR 44267 eff. date confirmed..................58672
    Regulation at 79 FR 53284 withdrawn............................68763
    Regulation at 79 FR 59626 eff. date confirmed..................74594
73 Authority citation revised......................................66606
    Nomenclature changes...........................................75741
73.2 Amended; eff. 1-28-15.........................................58671
73.21 (a)(1)(ii) revised; eff. 1-28-15.............................58671
73.23 Introductory text and (a)(2) introductory text revised; eff. 
        1-28-15....................................................58671
73 Appendix I removed; eff. 1-28-15................................58671
    Appendices A and C amended.....................................66606
74 Nomenclature change.............................................75741
75 Nomenclature change.............................................75741
76.7 (e)(3) revised................................................66606
110.2 Amended......................................................39291
110.26 (a) introductory text revised...............................39291
110.30 Amended.....................................................39291
110.42 Footnote 1 revised..........................................39291
110.44 (a) and (b)(1) revised......................................39291
110 Appendices A and B revised.....................................39291

[[Page 903]]

    Appendix C revised.............................................39293
    Appendix D revised.............................................39294
    Appendix E revised.............................................39295
    Appendix F revised.............................................39296
    Appendices G and I revised; Appendix H amended.................39297
    Appendix J amended; Appendix K revised.........................39298
    Appendix M revised.............................................39299
    Appendix N amended; Appendix O revised.........................39299
140 Nomenclature change............................................75742
140.21 Introductory text correctly revised.........................38769
150 Nomenclature changes...........................................75742
150.15 (a)(9) removed; eff. 1-28-15................................58672
170 Technical correction...........................................42452
170.3 Amended......................................................37144
170.12 (b)(3) revised; (b)(5), (6) and (7) removed; (g) added......37144
170.20 Revised.....................................................37145
170.21 Table amended...............................................37145
170.31 Table revised...............................................37145
    Table corrected................................................51471
171 Technical correction...........................................42452
171.11 (a) through (d) redesignated as (b) through (e); new (a) 
        added; new (c) revised.....................................37150
171.15 (a), (b)(1), (2) introductory text, (c)(1), (2) 
        introductory text, (d)(1) introductory text, (2), (3) and 
        (e) revised................................................37150
171.16 (d) and (e) introductory text revised.......................37151
171.19 (f) added...................................................37154

                                  2015

10 CFR
                                                                   80 FR
                                                                    Page
Chapter I
51 Actions on petitions............................................48235
    Authority citation revised.....................................54234
    Nomenclature changes...........................................74980
51.123 (a) and (b) amended.........................................74980
52 Authority citation revised......................................54234
52.3 (a) amended...................................................74980
54 Authority citation revised......................................54234
    Authority citation correctly revised...........................58574
55 Authority citation revised......................................54234
    Nomenclature change............................................74980
55.40 Footnote 1 revised....................................45844, 74980
60 Authority citation revised......................................54234
60.4 (a) amended...................................................74980
61 Authority citation revised......................................54235
    Nomenclature changes...........................................74980
61.4 Amended.......................................................74980
62 Authority citation revised......................................54235
62.3 Amended.......................................................74980
63 Authority citation revised......................................54235
63.4 (a)(3) amended................................................74981
70 Authority citation revised......................................54235
70.5 (a)(3) amended................................................74981
70.74 Regulation at 79 FR 57725 eff. date confirmed..................143
70 Regulation at 79 FR 57725 eff. date confirmed.....................143
70.50 Regulation at 79 FR 57725 eff. date confirmed..................143
71 Authority citation revised......................................54235
71.0 (d)(1) amended................................................34011
71.1 (a) amended...................................................74981
71.4 Amended................................................34011, 74981
    Correctly amended..............................................48684
71.6 (b) revised...................................................34012
71.14 (a)(1) and (2) revised; (a)(3) added.........................34012
71.15 (d) revised..................................................34012
71.17 (c) revised..................................................34012
71.19 (b) through (e) redesignated as(a) through (d); new (b)(2) 
        revised....................................................34012
71.21 (a) and (d) revised..........................................34012
71.31 (b) amended..................................................34012
71.38 Revised......................................................34012
71.70 Added........................................................34013
    (a) correctly revised..........................................48684
71.75 (a)(5), (b)(2)(ii), (iii), (d)(1) and (2) revised............34013
71.85 (a), (b) and (c) revised; (d) added..........................34013
71.91 (a) introductory text amended................................34013
71.97 (c)(3)(ii) revised...........................................74981
71.101 (a) and (c)(2) revised......................................34013
71.103 (a) revised.................................................34014
71.106 Added.......................................................34014
71.135 Revised.....................................................34014
71 Appendix A amended..............................................34014
72 Authority citation revised......................................54235
    Nomenclature change............................................74981
72.4 Amended.......................................................74981
72.214 Amended..............3152, 4761, 6435, 12078, 14295, 20153, 35833
    Corrected......................................................15679
    Regulation at 80 FR 4761 eff. date confirmed...................16251
    Regulation at 80 FR 6435 withdrawn.............................21639
    Regulation at 80 FR 14295 eff. date confirmed..................30924

[[Page 904]]

    Regulation at 80 FR 20153 eff. date confirmed..................36467
    Regulation at 80 FR 35833 eff. date confirmed..................53691
    Amended eff. 2-16-16...........................................49891
    Amended; eff. 4-25-16..........................................58199
    Amended; eff. 2-1-16...........................................71934
73 Technical correction.............................................3865
    Authority citation revised.....................................54235
    Authority citation correctly revised...........................58574
    Nomenclature change............................................74981
73.2 Regulation at 79 FR 58671 eff. date confirmed..................3865
    Amended........................................................74981
73.8 (b) revised...................................................74981
73.21 Regulation at 79 FR 58671 eff. date confirmed.................3865
73.23 Regulation at 79 FR 58671 eff. date confirmed.................3865
73.37 (b)(2) introductory text amended.............................74981
73 Regulation at 79 FR 58671 eff. date confirmed....................3865
74 Authority citation revised......................................54235
74.4 Amended.......................................................45844
74.6 (c) amended...................................................74981
74.55 (b)(2) revised...............................................45844
75 Authority citation revised......................................54235
75.6 (d) revised...................................................45844
76 Authority citation revised......................................54235
76.5 (c) amended...................................................74981
81 Authority citation revised......................................54235
81.3 Amended.......................................................74982
95 Authority citation revised......................................54235
    Authority citation correctly revised...........................58574
95.9 (c) amended...................................................74982
100 Authority citation revised.....................................54235
100.4 Amended......................................................74982
110 Authority citation revised.....................................54236
    Authority citation correctly revised...........................58574
110.4 Amended......................................................74982
140 Authority citation revised.....................................54236
140.5 Amended......................................................74982
150 Technical correction............................................3865
     Authority citation revised....................................54236
150.2 Amended......................................................63419
150.4 Amended......................................................74982
150.15 Regulation at 79 FR 58672 eff. date confirmed................3865
150.15a (b)(6) amended.............................................74982
160 Authority citation revised.....................................54236
170 Authority citation revised.....................................54236
170.3 Amended......................................................37454
170.5 Amended......................................................74982
170.20 Revised.....................................................37454
170.21 Table amended...............................................37454
170.31 Table revised...............................................37455
171 Authority citation revised.....................................54236
171.9 Amended......................................................74982
171.15 (b)(1), (2) introductory text, (c)(1), (2) introductory 
        text, (d)(1) introductory text, (2), (3) and (e) revised 
                                                                   37460
171.16 (d) and (e) introductory text revised.......................37460

                                  2016

10 CFR
                                                                   81 FR
                                                                    Page
Chapter I
53 Policy statement................................................49863
55.59 (c)(3)(i)(G)(3) amended......................................86909
61 Nomenclature change.............................................86909
63 Nomenclature change.............................................86909
70 Nomenclature change.............................................86910
71.71 (c)(1) table amended.........................................86910
72 Nomenclature change.............................................86910
72.74 (b) amended..................................................86910
72.214 Amended..................................377, 13271, 57446, 69663
    Regulation at 80 FR 58199 eff. date confirmed...................1116
    Regulation at 80 FR 71934 eff. date confirmed...................4574
    Regulation at 81 FR 377 eff. date confirmed....................15153
    Correctly amended.......................................19022, 34242
    Regulation at 81 FR 13271 eff. date confirmed..................34241
    Regulation at 81 FR 13271 comment responses....................70004
    Amended; eff. 1-9-17...........................................73339
    Regulation at 81 FR 57446 confirmed............................78021
    Regulation at 81 FR 69663 eff. date confirmed..................88097
73 Policy statement.........................................21449, 49863
73.56 (o)(2)(i) amended............................................86910
74 Policy statement................................................49863
74.11 (b) amended..................................................86910
100 Nomenclature change............................................86910
140.11 (a)(4) revised..............................................96348
150 Policy statement...............................................49863
170.1 Revised......................................................41186
170.2 (u) added....................................................41186
170.3 Amended...............................................32627, 41186
170.11 (a)(1)(ii) revised; (a)(1)(iii) removed; (a)(13) added......41186
170.12 (d)(1)(v) and (vi) revised; (d)(1)(vii) added...............41186

[[Page 905]]

170.20 Revised.....................................................41186
170.21 Table amended...............................................41186
170.31 Table revised...............................................41187
171.5 Amended......................................................32627
    Correctly amended..............................................45964
171.15 (e) redesignated as (f); new (e) added......................32628
    (b)(1), (2) introductory text, (c)(1), (2) introductory text, 
(d)(1) introductory text, (2), (3) and (f) revised.................41192
    (e)(1) correctly revised.......................................45964
171.16 (c), (d) and (e) introductory text revised..................41192
    (d) table correctly amended....................................61101

                                  2017

10 CFR
                                                                   82 FR
                                                                    Page
Chapter I
61.2 Amended.......................................................52825
71.4 Amended.......................................................52825
72 Policy statement................................................44299
72.214 Amended......8359, 14991, 25935, 29229,31439, 34387, 41322, 44885
    Regulation at 81 FR 73339 eff. date confirmed...................8805
    Regulation at 82 FR 8359 eff. date confirmed...................17749
    Regulation at 82 FR 14991 confirmed............................24457
    Regulation at 82 FR 25935 confirmed............................37511
    Regulation at 82 FR 29229 eff. date confirmed..................41873
    Regulation at 82 FR 31439 confirmed............................44053
    Regulation at 82 FR 44885 eff. date confirmed..................57819
73.2 Amended.......................................................52825
73 Appendix A amended..............................................52825
110.2 Amended......................................................52826
110.23 (a)(3) amended..............................................52826
110.32 (f)(1) amended..............................................52826
110 Appendix P amended.............................................52826
170.20 Revised.....................................................30699
170.21 Table revised...............................................30699
170.31 Table revised...............................................30699
171.15 (b)(1), (2) introductory text, (c)(1), (2) introductory 
        text, (d)(1) introductory text, (2), (3) and (f) revised 
                                                                   30704
171.16 (c), (d) and (e) introductory text revised..................30704
    (d) table correctly amended....................................33001
171.19 (d) revised.................................................30708


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