[Federal Register Volume 59, Number 184 (Friday, September 23, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-23329]


[[Page Unknown]]

[Federal Register: September 23, 1994]


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Part II





Nuclear Regulatory Commission





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10 CFR Part 19, et al.




Certification of Gaseous Diffusion Plants; Final Rule
NUCLEAR REGULATORY COMMISSION

10 CFR Parts 19, 20, 21, 26, 51, 70, 71, 73, 74, 76 and 95

RIN 3150-AE62

 
Certification of Gaseous Diffusion Plants

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its 
regulations to add a new part that includes the requirements for 
certification of uranium enrichment activities of the United States 
Enrichment Corporation (the Corporation) in its operation of the two 
gaseous diffusion plants that the Corporation is leasing from the U.S. 
Department of Energy (DOE). These two plants are known as the 
Portsmouth Plant and the Paducah Plant, located at Piketon, Ohio, and 
Paducah, Kentucky, respectively. These regulations are being 
promulgated to establish standards for the protection of the public 
health and safety from radiological hazards and provide for the common 
defense and security, including adequate safeguards. A number of 
conforming amendments are also being made to other NRC regulations. In 
addition, appendix A to part 95 is being removed, since this material 
is now available in a separate publication.

EFFECTIVE DATE: October 24, 1994.

FOR FURTHER INFORMATION CONTACT: Mr. C.W. Nilsen, Office of Nuclear 
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 
20555, telephone (301) 415-6209; Mr. C.B. Sawyer, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555, telephone (301) 415-8174; or Mr. J.K. Everly, 
Office of Administration, Division of Security, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555, telephone (301) 415-7048.

SUPPLEMENTARY INFORMATION:

Background

    The President signed H.R. 776, the ``Energy Policy Act of 1992'' 
(the Act), into law on October 24, 1992. The Act amended the Atomic 
Energy Act of 1954 (AEA), to establish a new Government Corporation, 
the U.S. Enrichment Corporation (the Corporation), for the purpose of 
managing and operating the uranium enrichment enterprise owned and 
previously operated by the Department of Energy (DOE). Section 1701 of 
the AEA, as amended, provides that within 2 years after enactment of 
the legislation, the NRC is to promulgate standards that will apply to 
the two operating gaseous diffusion plants to protect the public health 
and safety from radiological hazards, and to provide for the common 
defense and security.
    Section 1701(b)(2) of the AEA, as amended, directs the NRC to 
establish a certification process under which the two gaseous diffusion 
plants at Piketon, Ohio, and Paducah, Kentucky, to be operated by the 
Corporation, will be certified annually by the NRC for compliance with 
those standards.
    On February 11, 1994 (59 FR 6792), the Commission published a 
proposed new part 76 in the Federal Register for comment establishing 
requirements and procedures for the certification process by addition 
of this new part to chapter I of title 10 of the Code of Federal 
Regulations. In addition to the new part, a number of conforming 
changes to the provisions of Chapter I of Title 10 of the Code of 
Federal Regulations were also proposed which are necessary to implement 
the new part. The comment period expired on April 12, 1994.
    The new 10 CFR part 76 is based upon comparable NRC requirements 
that have been in place for a number of years. The NRC believes these 
requirements are adequate and appropriate for the gaseous diffusion 
plants. The NRC will assume regulatory oversight authority after it 
completes the first certification process in late 1995.

Summary of Requirements and Analysis of Public Comments

    The Nuclear Regulatory Commission is amending its regulations to 
add a new 10 CFR part 76 entitled, ``Certification of Gaseous Diffusion 
Plants.'' This new part includes procedural requirements, generally 
applicable NRC health and safety standards, technical safety 
requirements, and safeguards and security requirements specific to the 
gaseous diffusion plants. The Commission will use the requirements 
included in this new 10 CFR part 76 to satisfy Energy Policy Act 
requirements. The certification requirements in this rulemaking include 
actions that are either required by the Act or required by the 
Commission's procedures to protect the public health and safety from 
radiological hazards, to provide for the common defense and security, 
and to ensure adequate safeguards. Because this action does not 
constitute a licensing action, many of the processes associated with 
issuance of a license do not apply in this certification action.
    Twenty comment letters were received on the proposed rule and are 
available for public inspection, and copying for a fee, at the 
Commission's Public Document Room located at 2120 L Street, NW. (Lower 
Level), Washington, DC. The comments on the proposed rule came from a 
variety of sources that included the Corporation, the Department of 
Energy, citizens' groups, industry representatives, other Government 
agencies, and legal firms. The comments and their resolutions are 
discussed below and, to the extent possible, are arranged under the 
identified section of the rule to which they are related.

A. General Requirements

    The general requirements are based on and mainly derived from 10 
CFR Part 70. Part 70 contains the requirements used by the Commission 
to license the possession and use of special nuclear material at major 
fuel cycle facilities for which the NRC has regulatory responsibility 
for protecting public health and safety and the common defense and 
security. Specific sections in this new part, which are based on 10 CFR 
Part 70 as modified for the certification process, include the 
following:
    Section 76.1  Purpose. This section defines the purpose of 10 CFR 
part 76 to be limited to certification of the existing 40-year-old 
gaseous diffusion plants previously operated by the DOE.
    A comment was received indicating that reference made to ``life of 
the plant'' should be changed to ``duration of lease.'' The final 
regulation has been so changed.
    Section 76.2  Scope. This section defines the scope of part 76 to 
cover the operation of gaseous diffusion plants previously operated by 
DOE and now leased to the Corporation, and clarifies that the new part 
applies only to those plants.
    Comments were received indicating that the rules should be 
clarified as only applying to operation of those portions of the 
diffusion plants leased to the Corporation. The appropriate changes to 
the rule have been made.
    Section 76.4  Definitions. This section contains definitions of 
terms used in this part.
    In response to comments received, several definitions have been 
added to, or revised in the final rule as follows:
    Corporation. In response to a comment by the Corporation, the NRC 
agrees that the definition should be clarified to show the continued 
applicability of Part 76 to the operation of the gaseous diffusion 
plants after privatization of the Corporation if privatization were to 
occur.
    Alert and Site area emergency. Definitions are added for 
consistency with other regulations.
    Radioactive material. Added as requested for clarification.
    Unreviewed safety question. This definition was suggested by DOE, 
and was added in response to comments by DOE and the Corporation, to 
clarify its use in Sec. 76.68 as one factor in limiting changes that 
the Corporation can make without prior Commission approval.
    Section 76.5  Communications. This section describes requirements 
for verbal and written submissions to the Commission.
    No comments were received on this section.
    Section 76.6  Interpretations. This section contains requirements 
for interpretations of these regulations that are authorized by the 
Commission.
    No comments were received on this section.
    Section 76.7  Employee protection. This section specifies 
activities that are protected and prohibits discrimination against an 
employee for engaging in protected activities.
    Comments were received concerning the transition from operation 
under DOE orders to operation under NRC regulations. Specifically, it 
was suggested that various requirements for posting of NRC regulations 
and forms be delayed in some cases until after the NRC has taken action 
on the application. This section and Sec. 76.60 have been modified to 
provide additional flexibility in the posting of notices by requiring 
posting not later than the date of the Director's initial decision on 
certification.
    One commenter recommended that the final rule include a reference 
to activities protected by the National Labor Relations Act. The labor 
standards and/or statutes applicable to the Corporation are specified 
in section 1312(d) of the AEA. No further delineation of those 
standards and/or statutes is necessary for inclusion in NRC's 
certification regulations.
    A comment was received expressing a perceived lack of willingness 
of the NRC to solicit comments from organizations that represent the 
plant workers. This rulemaking has been done under full public 
participation as required by NRC procedures within the time limits 
imposed by the legislation for transferring operation of the facilities 
to the Corporation. The certification procedure provides an opportunity 
for public participation at all stages of the process through written 
comments and participation in public meetings to be held near the 
sites.
    Section 76.8  Information collection requirements: OMB approval not 
required. This section indicates that the information collection 
requirements contained in this part need not be reviewed and approved 
by the Office of Management and Budget in accordance with the Paperwork 
Reduction Act.
    No comments were received on this section.
    Section 76.9  Completeness and accuracy of information. This 
section specifies that all information provided to the NRC must be 
complete and accurate.
    No comments were received on this section.
    Section 76.10  Deliberate misconduct. This section describes 
prohibited activities and states that violations are subject to 
enforcement action.
    No comments were received on this section.
    Section 76.23  Specific exemptions. This section specifies that the 
Commission may grant exemptions from the requirements in part 76 
provided certain conditions are met.
    A comment was received from the Corporation recommending that the 
rule be expanded to provide that the Commission may grant exemptions 
where certain ``special circumstances'' exist due to the ``unique 
status'' of the Corporation. The special circumstances presented 
included a request by the Corporation or DOE that an exemption would be 
in the furtherance of the common defense and security of the United 
States, the nonproliferation of atomic weapons, or any of the other 
important governmental functions identified in the statutory purposes 
for the Corporation set forth in Section 1202 of the AEA. As proposed, 
Sec. 76.23 already provides that NRC may grant exemptions and 
specifically includes consistency with the common defense and security 
of the United States as a prerequisite for granting an exemption. The 
NRC does not conclude that the Corporation's ``unique status'' 
introduces any additional considerations in considering requests for 
exemptions not already within the purview of Sec. 76.23.
    Section 76.65  Inalienability of certificates. This section sets 
forth the conditions for transfer of certification.
    Comments were received that the proposed rule should address 
inalienability of certificates. This section has been added to the 
final rule.
    Section 76.76  Backfitting. This section sets forth the conditions 
for requiring backfitting of the plants and establishes backfit 
guidelines. Backfitting is defined as any NRC-required modification or 
addition to systems, structures, or components of the facility, or 
procedures or organizations used to operate the facility.
    Commissioner Rogers was particularly interested in comments on two 
issues regarding the provisions of this section: (1) Whether the 
provisions of Sec. 76.76 should become effective immediately when 10 
CFR part 76 becomes final, as would happen were the proposed section to 
remain unchanged, or whether there should be some interim period before 
these provisions become effective (e.g., until completion of the first 
annual certification following initial certification) and; (2) Whether 
the standard for requiring a backfit should be that of 
Sec. 76.76(a)(3), ``* * * a substantial increase in the overall 
protection of the public health and safety or the common defense and 
security * * *'' or the less stringent standard of cost-effectiveness 
that is contained in section 1(b)(6) of Executive Order 12866 of 
September 30, 1993, ``* * * a reasoned determination that the benefits 
of the intended regulation justify its costs.''
    A number of commenters agreed that the provisions of Sec. 76.76 
should be made effective when the rule becomes final. There were no 
comments received in support of a delay in the implementation of the 
backfit provisions. However, the Ohio Citizens for Responsible Energy 
opposed the application of the proposed backfit requirements to these 
facilities. They commented that: (1) Operations have not been trouble-
free and environmentally benign, (2) the NRC has no previous experience 
with these plants, (3) the backfit rule would essentially ``freeze'' 
the plant design and operational practices, and (4) the NRC must be 
free to demand changes in the design and operation of these plants. 
They further commented that if the NRC establishes any backfit standard 
it should be the standard of Executive Order 12886: ``a reasoned'' 
determination that the benefits of the intended regulation ``justify 
its costs.''
    The Corporation, DOE, and the Nuclear Energy Institute agreed with 
incorporation of the backfit provisions as written. The Corporation 
specifically supported the rewrite of 10 CFR 50.109, as proposed, as 
being consistent with NRC practice.
    In response to the comment suggesting that the proposed backfit 
provisions would prevent the Commission from taking action as is 
required to protect public health and safety, the Commission does not 
apply backfit provisions in a manner which would inhibit imposition of 
requirements necessary to achieve an adequate level of safety. Under 
the backfit requirements in the final rule, costs are considered only 
for determining the need to impose requirements that provide for 
enhanced levels of safety that go beyond those basic requirements 
needed to provide adequate protection of the public health and safety.
    The final rule requires a cost benefit analysis for any new 
requirement or NRC staff position unless the modification is required 
to bring the facility into compliance with written rules or orders, or 
into conformance with written commitments by the Corporation, or if the 
change is necessary to ensure that the facility provides adequate 
protection of the public health and safety. The final rule is 
unchanged.
    Section 76.81  Authorized use of radioactive material. The section 
sets forth requirements for the Corporation's possession and use of 
radioactive material.
    The Corporation commented that it wants language in the regulations 
which would authorize it to receive, possess, own, acquire possession 
of, and use radioactive materials in places and for purposes not 
covered by the certificate, if otherwise authorized by law. Such 
authorization would not be part of certification and would involve 
approval by other Federal agencies. This comment goes beyond NRC's 
authority with respect to certification of the gaseous diffusion 
facilities. To the extent that the Corporation wants NRC to approve 
activities associated with radioactive materials involving other 
locations and other activities, other locations and activities are not 
included in the certification authority contained in the AEA, as 
amended by the Energy Policy Act. The final rule has been revised to 
make clear that to the extent the Corporation engages in activities not 
covered by the certification process, it may do so as long as it 
complies with all applicable State and Federal regulations.
    Section 76.83  Transfer of radioactive material. This section 
contains requirements for the Corporation's transfer of radioactive 
material.
    DOE recommended that the provision of Sec. 76.83(d)(3) concerning 
emergency shipments be deleted as they are not defined and continued 
implementation of current DOE practices provides methods for shipment 
of material outside the normal process. This comment was not adopted 
and the section was retained to provide the flexibility for such 
transfers under NRC certification in the event it would be needed and 
is not inconsistent with current NRC practices.
    Section 76.89  Criticality accident requirements. This section 
contains monitoring requirements for criticality accidents.
    Commenters requested that Sec. 76.89 be revised to specifically 
state that certain areas do not require criticality alarms: (1) Areas 
containing less than 700 grams of U-235 contained in uranium of any 
enrichment, (2) areas containing less than 1500 grams of U-235 
contained in uranium enriched up to 4%, (3) areas containing less than 
1400 grams of U-235 contained in uranium enriched up to 5%, (4) areas 
where special nuclear material is packaged and stored in approved 
containers and in isolated arrays in compliance with 10 CFR part 71, 
and (5) process buildings containing homogeneous uranium material 
enriched to less than 1%. The NRC does not intend to require monitoring 
for areas where quantities of enriched uranium are controlled so that a 
criticality accident is not credible. Rather than attempting to specify 
quantity limits, the rule was modified to include a generic provision 
such that criticality alarms will not be required for such controlled 
areas.
    Section 76.91  Emergency planning. This section contains emergency 
planning requirements.
    Some commenters agreed with the emergency planning provisions as 
proposed. Others recommended that the emergency planning provisions be 
revised. A commenter's proposed changes were to (1) add a ``general 
emergency'' category to the classification of accidents, (2) give 
annual briefings and tours to fire, police, medical, and other 
emergency personnel, (3) conduct annual drills in addition to the 
proposed annual exercises, and (4) add separate sections to emergency 
planning documents that address the emergency operations center and 
public notification of basic emergency planning and information in 
emergency planning zones. A commenter also suggested that the proposed 
language would permit individuals to evaluate their own performance in 
the required biennial exercise, rather than have an independent and 
impartial evaluation.
    The emergency planning provisions in 10 CFR part 76 are essentially 
those of 10 CFR part 70. Adoption of these comments would result in 
emergency planning requirements similar to those in place at nuclear 
power plants. The nature of the postulated accidents that are 
considered in emergency planning for nuclear power plants would be 
substantially different from those that would be involved in emergency 
planning for the gaseous diffusion plants. The regulatory analysis for 
the emergency preparedness requirements contained in Part 70 evaluated 
the risks associated with the release of UF6 and concluded that 
offsite emergency preparedness should be based on chemical toxicity 
from a large UF6 release. The current part 70 requirements are 
considered adequate for these facilities, therefore, these additional 
measures were not adopted.
    One commenter concluded that Sec. 76.91, ``Emergency Planning,'' 
does not provide for any offsite emergency planning except for a 
minimal notification procedure to offsite response organizations and a 
request for offsite assistance, and that this omission implies that no 
offsite consequences will occur. Actually, the rule requires 
considerable coordination with offsite organizations, including 
offering opportunities for orientations and participation in exercises. 
Although there is a small risk of an incident which may require an 
offsite response, the NRC believes the nature of these incidents is 
such that State and local governments can be expected to respond in an 
adequate manner whether or not there are any formal written emergency 
plans for offsite releases.
    Section 76.120  Reporting requirements. This section contains 
requirements for 1-hour notification, 4-hour notification, 24-hour 
notification, and for preparation and submission of reports.
    One commenter recommended deletion of ``general emergency'' to make 
the language of the requirement consistent with that of Sec. 76.91(c). 
Because there was no intent of including a general emergency class, 
this correction was made.
    Another commenter recommended changing ``or'' to ``and'' between 
paragraphs (c)(1)(ii) and (iii), and between paragraphs (c)(2)(ii) and 
(iii). This change was adopted as being the intent of the proposed rule 
and to be consistent with 10 CFR parts 30, 40, and 70.
    One commenter recommended changing the language in 
Sec. 76.120(c)(1)(iii) from ``to decay to a level that would allow 
decontamination'' to ``to decay prior to decontamination.'' This change 
was adopted for consistency with part 70.
    The Corporation suggested that Sec. 76.120(c)(2) could be changed 
to provide that the failure of equipment required by an operational 
safety requirement to perform certain functions should be reported to 
the NRC. The NRC agrees with the intent of the suggestion but will use 
the technical safety requirement for consistency of terminology. The 
appropriate changes have been made to the final regulation. The comment 
also recommended deletion of the requirement for reporting equipment 
failure in the case of equipment required to restore the facility to a 
preestablished safe condition. This suggestion was not adopted. The 
requirement is needed to ensure that the NRC is aware of instances when 
facility safety during shutdown and restart could be threatened.
    The Corporation suggested a modification to Sec. 76.120(c)(3) to 
reflect that both GDPs have onsite medical facilities that negate the 
need for reporting radioactive contamination of personnel. This 
suggestion was not adopted. The purpose of the requirement is to make 
the NRC aware of any event in which a worker needs medical attention, 
either onsite or offsite, due to radiological contamination.
    The Corporation suggested the deletion of the record or log 
requirement in Sec. 76.120(d). The NRC maintains telephone event report 
logs in its database system and written reports submitted on emergency 
actions carried out in response to an emergency plan activation. There 
is no health and safety benefit to be gained by the Corporation 
maintaining an additional log for two years after an event. Therefore, 
the final regulation has been changed as suggested.
    One commenter suggested that the proposed verbal and written 
reporting requirements should be modified to be consistent with the 
current part 70 requirements and that the same language should be used. 
This suggestion was not adopted. The proposed new language only 
clarifies what is already required by the current wording of 10 CFR 
20.2201, 20.2202, 70.50, and 70.52.
    Section 76.121  Inspections. This section states that the 
Corporation shall afford the Commission opportunity for inspection and 
that office space for Commission inspection personnel must be provided.
    No comments were received on this section.
    Section 76.131  Violations. This section specifies actions the 
Commission may take to prevent a violation, such as obtaining a court 
order, and contains civil penalty provisions.
    A commenter asserted that the proposed rules do not include 
enforcement provisions. The post issuance provisions in Sec. 76.70 
pertain to revocation, suspension, or amendment for cause. Revocation 
of a certificate or approved compliance plan would be an extremely 
severe sanction and, quite arguably, the most severe possible sanction 
for the Corporation. In addition, Sec. 76.60 makes 10 CFR Part 21 
(Reporting of Defects and Noncompliance) applicable to the gaseous 
diffusion plants, and Sec. 76.22(d) includes provision for civil 
penalties for violations of 10 CFR part 21. Section 76.131 pertains to 
violations and provides for the Commission to seek an injunction or 
other court order to prevent a violation of the regulations and to seek 
an order for payment of a civil penalty for violation of Section 206 of 
the Energy Reorganization Act of 1974 (relating to reporting of defects 
and noncompliance). The commenter also indicated difficulty in 
determining what criminal penalties apply when examining Sec. 76.133 
and the citations therein. Section 76.133(b) identifies those sections 
of part 76 for which criminal penalties do not apply. As set forth in 
Section 223 of the AEA, as amended, the general penalty for such 
violation, upon conviction, is punishment ``by a fine of not more than 
$5,000 or by imprisonment for not more than two years, or both.'' The 
rule was not changed.
    Section 76.133  Criminal penalties. This section specifies criminal 
sanctions for violations. For purposes of section 223 of the AEA which 
provides for criminal sanctions, the regulations in 10 CFR part 76 for 
which criminal penalties apply are issued under sections 161b, or 161i. 
The sections for which criminal penalties do not apply are listed in 
Sec. 76.133(b).
    The Corporation agreed that criminal sanctions could be imposed for 
violations of part 76 regulations issued under sections 161b or 161o of 
the AEA because these sections give the Commission authority to issue 
regulations to govern the possession and use of special nuclear 
material. However, the Corporation indicated that part 76 regulations 
could not be issued under section 161o of the AEA, and therefore, 
section 161o should be removed as a potential basis for criminal 
sanctions under Sec. 76.133 and other NRC regulations (e.g., 10 CFR 
19.40) made applicable to the Corporation. The Corporation reasoned 
that the activities regulated in part 76 do not constitute licensed or 
other activity within the scope of 161o.
    The Commission agrees that 161o of the AEA applies to licensed and 
other activities that are not the subjects of the regulations in part 
76. Therefore, Sec. 76.133 has been revised by deleting section 161o as 
an authority for the issuance of regulations in part 76 and imposition 
of criminal sanctions under section 223 of the AEA. The Commission does 
not believe that it is necessary to revise the ``Criminal Penalties'' 
sections of other parts that apply to the Corporation because the 
references to 161o as one of the non-exclusionary bases for issuance of 
regulations in the other parts also apply to actions of licensees and 
other persons engaged in activities within the scope of 161o.

B. Procedural Requirements

    As directed by section 1701(c) of the AEA, as amended, the rule 
contains procedures for the annual certification process. Apart from 
requiring an annual application for a certificate of compliance and a 
determination by the Commission, in consultation with EPA, of 
compliance with the NRC's standards, the legislation does not specify 
procedures for the certification process. In addition, the amendments 
to the AEA provide that the requirement for a certificate of compliance 
is in lieu of any requirement for a license. Thus, the NRC has 
substantial discretion in determining appropriate procedures for the 
certification process. By providing for public notice and a written 
comment period with respect to an application for a certificate of 
compliance, as well as the opportunity for the Corporation and other 
interested parties to petition the Commission for review of the 
decision to grant or deny a certificate or request for approval of a 
compliance plan, the Commission believes that it is adopting a fair and 
efficient certification process/procedure.
    The procedural requirements for the certification process to 
implement provisions of the Act and to constitute the Commission's 
certification process include:
    Section 76.21  Certificate required. This section contains the 
requirement that the gaseous diffusion plants may not be operated 
without a certificate of compliance or an approved compliance plan.
    A comment was received concerning operation of the GDPs between the 
time the NRC issues the standards and issues a certificate or approves 
a compliance plan. The Corporation's authority to continue to operate 
the GDPs under DOE oversight after part 76 becomes effective, but 
before the NRC completes the initial certification process, has been 
clarified.
    A commenter stated the belief that the Corporation should not be 
able to operate the facilities without a certificate of compliance. 
This view appears to be based on a misunderstanding of the AEA. Section 
1403 of the AEA requires that the Corporation lease the facilities for 
a period of 6 years, which commenced on July 1, 1993 (see also section 
1314(e)), but section 1701 also gave the NRC 2 years from October 24, 
1992, for establishment of standards under which the NRC would then 
determine whether to certify compliance with the standards. During the 
interim period, DOE has oversight responsibility for the GDPs until the 
NRC establishes its standards and completes the first certification 
process.
    In response to another comment, the rule has been revised to permit 
receipt of radioactive material under either a certificate or an 
approved compliance plan.
    Section 76.31  Annual application requirement. This section 
specifies the date by which the annual application must be filed. The 
initial certification would be based on review of an application 
submitted by the Corporation. The initial application would contain a 
complete description of operations, a safety analysis, and other 
information required to demonstrate compliance with NRC requirements. 
Subsequent applications could reference previously submitted 
information. For annual reviews after the initial certification, the 
Commission would focus on new information and changes from the previous 
year and public comments. The Commission anticipates that it will 
perform a complete review, similar to that performed for the initial 
certification, every 10 years.
    The footnote concerning the date for submission of the initial 
application has been changed in response to a comment from the 
Corporation to provide at least 6 months for submission of the initial 
application after the rule becomes effective.
    Section 76.33  Application procedures. This section contains filing 
requirements and specifies the required contents of the application.The 
rule requires any application which contains restricted data, 
classified national security information, unclassified controlled 
nuclear information, safeguards information, or proprietary or other 
withholdable data to be prepared in such a manner that all such 
information or data are separated from the information to be made 
available to the public.
    The Corporation stated that the word ``identifiable,'' used in 
Sec. 76.33(c)(2) to describe areas of noncompliance, was unclear and 
should be revised to be ``identified'' as stated in other NRC 
regulations (e.g., 10 CFR 21.1 and 70.9(b)). They indicated that it is 
not clear how the NRC would determine whether a particular 
noncompliance to be addressed in a compliance plan was 
``identifiable.'' The NRC agrees that this word is ambiguous, and it 
has been changed to ``identified'' in the final rule as stated in 10 
CFR 20.1 and 70.9(b).
    Several comments were received concerning the environmental aspects 
of the certification process and existing environmental conditions at 
the facilities including the presence of contamination due to 
transuranics and their daughters. The Department of Energy prepared an 
Environmental Impact Statement for the Portsmouth gaseous diffusion 
plant in 1977 and an Environmental Assessment of the Paducah facility 
in 1982. The NRC has reviewed those documents, as well as environmental 
reports prepared by DOE for both facilities in 1992 and environmental 
audits prepared by DOE prior to turning operation of the Facilities 
over to the Corporation in 1993. The NRC also conducted extensive site 
visits. No significant differences in operations, previously evaluated 
by DOE, were identified that would result in current operations having 
significantly different environmental effects than those already 
evaluated in DOE's environmental reviews. In addition, any known 
quantities of transuranics or their daughters at facilities under the 
NRC regulatory certification process most likely came from the 
processing of recycled uranium in the past. The Corporation will be 
required to provide for adequate protection of public health and safety 
as a result of operations at the leased facilities, including releases 
of effluents to the environment as specified in Sec. 76.60(d) that is 
based on the regulations in 10 CFR part 20. As established by the Act, 
the NRC will issue a certificate only for the current operations of the 
facility and will not evaluate preexisting conditions. All preexisting 
conditions are outside of NRC authority. In consideration of this 
limited authority, this section was changed to only require submittal 
of additional information that deviates from DOE-published 
environmental documents for these facilities. Also, in this regard, the 
Act requires the Director, as specified in Sec. 76.53, to consult with 
the Environmental Protection Agency (EPA) on applications for 
certification.
    The NRC has reviewed comments concerning decommissioning and 
existing site environmental contamination. The NRC is currently working 
with the EPA in establishing standards for the decommissioning of 
nuclear facilities. These EPA standards will be applied in the 
decommissioning of these plants.
    Several commenters responded to the requirement concerning 
separation of certain material, such as classified or proprietary 
material, from the information to be made available to the public. This 
requirement conforms to other NRC regulations on the separation of 
submitted information. The special handling of the specified material 
is required to protect information that could be detrimental to 
national or facility security and the Corporation's business. In 
appropriate cases, the Commission has procedures to permit access to 
the material for individuals who have been properly cleared and are 
bound by law to protect the information.
    The Corporation suggested that the proposed rule be modified in 
several places to state that the Corporation need not describe 
procedures for special nuclear material where the function is the 
responsibility of DOE. The NRC recognizes that the Corporation will not 
control all activities at the enrichment plant sites, and that DOE will 
continue to conduct certain activities involving enriched uranium at 
sites which are outside of NRC jurisdiction. Any interaction between 
DOE and the Corporation-leased facilities will be carefully monitored 
by NRC to assure that safety and safeguards requirements are met by the 
Corporation. However, the suggested rule changes were not adopted 
because it is inappropriate for the rule to attempt to address DOE 
activities which fall outside NRC jurisdiction.
    Also, in response to a comment, the final rule requires more 
detailed information about the Corporation's management structure 
similar to that required by part 70.
    Section 76.36  Annual renewal. The Corporation requested a change 
in format regarding contents of applications for the purpose of 
increased clarity regarding the precise scope of the initial 
application and of renewal applications. Included in the proposed 
restructuring was revision of proposed Sec. 76.35 pertaining to 
contents of applications so as to limit its scope to the contents of 
the initial application. The Corporation also recommended the addition 
of a new Sec. 76.36 so as to set forth the precise content of the 
annual resubmittal.
    The NRC agrees that revisions to specifically address the renewal 
procedures would add clarity to the prescribed content of the initial 
and renewal applications. As a result, the final rule adds a new 
Section 76.36 to address required contents for annual renewal 
applications and identifies the information that must be submitted for 
annual review following the initial certification action. This new 
section clarifies and confirms that the Corporation may, as part of its 
application for renewal, either submit the information specified in 
Sec. 76.35 pertaining to the initial application or rely upon the 
application(s) upon which the existing certificate is based and 
identify any pertinent changes or proposed changes as specified in 
Sec. 76.36(c)(2). The provision permitting incorporation of previous 
submissions by clear and specific reference has been moved from 
proposed Sec. 76.33(f) to Sec. 76.36(b).
    Section 76.37  Federal Register notice. This section describes the 
public notice on a filing of an application, provides an opportunity 
for public comment, and indicates the date of any public meeting.
    Ohio Citizens for Responsible Energy (OCRE) requested that the 
Commission provide at least an 80-day period for public comment on the 
initial application for a certificate and for complete review of 
renewal applications that is intended every 10 years. OCRE views the 
proposed 30-day period as too brief for learning through publication in 
the Federal Register of the filing of an application and to respond to 
such a complex matter.
    Another commenter, the Central Mid-West Interstate Low-Level 
Radioactive Waste Commission, recommended that the Commission provide 
for at least a 60-day period for public comment on an application for 
initial issuance or renewal of a certificate.
    Section 76.37 does not specify the time period which will be 
afforded for public comment on an application. However, the Commission 
has indicated that it plans to provide at least a 30-day comment period 
(February 11, 1994; 59 FR 6797). In light of the comments received, the 
Commission has determined, as a matter of policy, that it intends to 
provide a comment period of at least 45 days. However, the Commission 
cannot assure that any longer public comment period will be provided in 
light of the need for an expeditious determination of the application 
on an annual basis, including NRC staff review of the application and 
public comments, preparation and issuance of the Director's decision, 
and consideration of petitions for review by the Commission.
    The Commission notes that it has provided for the annual filing of 
an application by a specific date and that it will promptly make a copy 
of the application available in local public document rooms near the 
gaseous diffusion plants. These aspects of the certification process 
should enhance the ability of the public to provide comment on the 
application.
    Section 76.39  Public meeting. This section describes the 
procedures for conducting a public meeting on applications at the 
discretion of the Director, Office of Nuclear Material Safety and 
Safeguards (NMSS), NRC. A public meeting will be held on the initial 
certification application.
    Ohio Citizens for Responsible Energy (OCRE) requested that the 
regulations require a public meeting on the initial certification 
process and for the complete review that the NRC anticipates performing 
every 10 years.
    The final rule, as did the proposed rule, provides that a public 
meeting will be held if the Director, at his or her discretion, 
determines that a meeting is in the public interest with respect to a 
decision on the application. The NRC has already indicated, as a matter 
of policy, that a public meeting will be held on the initial 
certification application. The Commission continues to be committed to 
holding such a meeting. The scope of the Commission's review and public 
expression of interest in a public meeting will be important factors in 
the Director's decision on whether a meeting on any certificate renewal 
is in the public interest.
    However, it is not clear that a public meeting will be necessary on 
any annual renewals. Commenters on an application may request a public 
meeting on annual renewals. The Director, NMSS, will consider these 
comments in making a determination of whether a public meeting is in 
the public interest.
    OCRE also requested that the NRC provide persons whose interests 
may be affected by operation of the facilities with the opportunity for 
a formal adjudication to contest a certification and ensure correction 
of past problems.
    The Commission has not made provision for a formal adjudicatory 
hearing on a certification decision whenever requested by a person 
whose interests are adversely affected. Public notice, opportunity for 
written comment, and opportunity to petition the Commission regarding a 
Director's decision should provide a fair and efficient procedural 
process for public participation in the certification decision. It must 
be recognized that Congress explicitly provided for a certification 
process in lieu of licensing requirements and did not specify any 
particular procedures for the certification process. However, in 
addition to the specific procedures which the Commission is providing, 
the Commission has also made clear its discretion to adopt by order 
further procedures that it determines would serve the purpose of the 
Commission's review of the Director's decision (Secs. 76.62(c) and 
76.64(c)).
    Section 76.41  Record underlying decisions. This section specifies 
that any decision will be based on information in the record and that 
significant information on any proceeding, with limited exceptions, 
will be part of the public docket. This is not intended to constitute a 
requirement of adjudication on the record after opportunity for agency 
hearing under the Administrative Procedure Act.
    No comments were received on this section.
    Section 76.43  Annual date for decision. This section describes the 
timing of the annual decision on the application by the Director, NMSS, 
to be made within 6 months of receipt of the application.
    No comments were received on this section.
    Section 76.45  Application for amendment of certificate. This 
section states the procedures to be followed by the Corporation in 
applying for an amendment of a certificate before the established date 
of the next application for a certificate.
    DOE commented that applications for amendment should be submitted 
by the Corporation under oath or affirmation. The Commission has 
included this change in the final rule.
    Section 76.51  Conditions of certification. This section states 
that the Corporation shall comply with all requirements set forth and 
referenced in part 76, or in a certificate of compliance, or in an 
approved compliance plan.
    In one of its comments, the Corporation requested that this section 
be revised to permit the Corporation to modify its programs for 
material control and accounting, physical protection, protection of 
special nuclear material in transit, security, safeguards, and 
emergency response so long as the changes do not decrease the 
effectiveness of the applicable plans. This permission is already 
granted in Sec. 76.68 of the proposed rule. That section permits the 
Corporation to make changes to the plant or the plant's operations 
without prior Commission approval provided certain conditions are met.
    In another comment, the Corporation suggested various retention 
periods for records of changes to material control and accounting plans 
made without prior Commission approval and for records of changes to 
security and safeguards plans made without prior Commission approval. 
Requirements for retention of these kinds of records are addressed in 
the proposed Sec. 76.68(d). The record retention period for procedural-
like changes is standardized at two years and is shorter than the 
periods proposed by the Corporation. Records of changes to the plant 
must be retained for the duration of the lease. The Corporation comment 
did not explicitly address retention of records of changes to the 
plant. The required period is deemed justified because it is important 
to both safety and safeguards to have available records describing the 
current and past plant configurations.
    A final comment from the Corporation on this section suggested a 
schedule for informing the Commission of various kinds of changes made 
without prior Commission approval. The submission requirement is 
addressed in Sec. 76.68(b). The time allowed has been extended from 90 
days in the proposed rule to annually in the final rule. The annual 
submission date allows more time for submission than any of the 
Corporation's suggestions. The annual submission date could coincide 
with the annual application and is justified by the continuing presence 
of an onsite NRC resident inspector who would be aware of the changes.
    Section 76.53  Consultation with Environmental Protection Agency 
(EPA). This section states that the Commission will consult with the 
EPA in making the annual decision on the application for a certificate, 
including the provisions of any compliance plan, and solicit their 
written comments on the application.
    No comments were received on this section.
    Section 76.55  Timely renewal. This section states that timely 
filing of an application for a certificate of compliance will maintain 
in effect any existing certification or approved compliance plan 
effective until issuance of a final decision on the application. This 
addresses the unlikely situation in which the Commission is unable to 
make the required annual determination regarding an application for a 
certificate of compliance despite timely filing of the application. In 
this case, the Commission will deem its prior determination regarding 
compliance effective until final resolution of the subsequent 
application and will advise Congress annually as required under Section 
1701(b) of the AEA.
    The Corporation requested that the provision on timely renewal be 
modified by providing that an existing certificate of compliance or 
approved compliance plan not expire until the annual application for a 
certificate of compliance ``has been finally determined by the 
Commission'' rather than at the time of the Director's determination of 
the application. The Corporation also requested that the condition of 
timely filing of ``a sufficient annual application'' be changed to 
timely filing of ``an annual application in proper form.''
    The Commission agrees that an existing certificate or approved 
compliance plan should not expire until a final determination is made 
by the agency on the renewal application for the certificate. The final 
rule has been revised accordingly. The Commission intends that a 
certification process will normally be completed on an annual basis in 
the absence of extraordinary or unusual circumstances preventing the 
completion of the process.
    The final rule has been revised to clarify that the Corporation 
will not be penalized if NRC does not complete the certification 
process expeditiously. However, the Corporation must timely file a 
sufficient application that addresses all the elements in Sec. 76.36 
for the Commission's determination. NRC staff questions regarding 
information provided in the application will not cause an application 
to be judged insufficient.
    Section 76.60  Regulatory requirements which apply. This section 
specifies the requirements which the NRC will apply in certifying the 
Corporation's operation of the gaseous diffusion plants.
    One commenter suggested that in several places the phrase ``shall 
demonstrate compliance'' should be changed to ``shall comply.'' The NRC 
agrees with this comment and has changed the final regulation.
    The Corporation requested that the rule be changed to allow two 
years to convert administrative and procedural elements of its 
radiation protection program to meet the standards for protection 
against radiation contained in 10 CFR part 20. DOE commented that the 
implementation of part 20 requirements should be based upon a schedule 
that achieves implementation in a timely, cost-effective manner. 
Although the Corporation agreed that the dose limits should become 
immediately effective upon receipt of the certification or an approved 
compliance plan, they provided no information on how they would be 
capable of implementing the dose limits without procedures or 
administrative controls in place. The requested two-year extension 
could mean that the elements of part 20 would not be in place until 
late 1996. The Commission recognizes that although there will be 
significant effort required to implement part 20, sufficient time is 
available for the Corporation to begin to implement these requirements. 
If the Corporation is unable to complete development of the appropriate 
procedures and administrative controls, including training before the 
date of the NMSS Director's decision, any remaining activities should 
be presented as a part of a compliance plan. In addition, the 
Corporation expressed concern with obtaining National Voluntary 
Laboratory Accreditation Program (NVLAP) approvals. Because NVLAP 
testing occurs every 3 months and the facilities possess Department of 
Energy Laboratory Accreditation Program (DOELAP) certification, there 
should be no difficulty in obtaining NVLAP accreditation before the 
NMSS Director's decision.
    Another comment noted that until the initial certification, DOE has 
the regulatory oversight authority over the gaseous diffusion plants 
(GDPs) and, therefore, the implementation date for 10 CFR parts 19 and 
21 should coincide with issuance of the initial certificate, rather 
than earlier as in the proposed regulation. The NRC agrees with this 
comment, and the regulation has been so changed.
    Louisiana Energy Services (LES) raised the issue of requiring, 
through part 76, that the Corporation maintain liability insurance 
comparable to that required by 10 CFR part 140 for uranium enrichment 
facilities. The provision cited by LES, 10 CFR 140.13b, is based on 
section 193 of the AEA. This section specifically requires that the NRC 
require, as a condition of licensing any enrichment facility, that 
liability insurance be maintained by the licensee sufficient to cover 
liability arising from operations at the licensed facility. The 
legislation establishing the Corporation specifically provides that 
Price-Anderson indemnification will be provided by the Department of 
Energy under Section 170d of the Atomic Energy Act of 1954, as amended 
(AEA) for the gaseous diffusion facilities leased to the Corporation by 
the DOE. Further, Section 170a of the AEA provides that NRC may require 
financial protection for facilities licensed under sections 53, 63, 81, 
103, 104, and 185. The certification process does not constitute 
issuance of a license within any of these sections of the AEA. 
Accordingly, it is the Commission's conclusion that requiring 
additional NRC mandated liability insurance for the Corporation's 
operations is neither appropriate nor necessary.
    One commenter recommended the inclusion of the reference to 10 CFR 
part 95 that covers security and safeguarding information in this 
section for consistency as other regulations which apply are listed. 
The NRC agrees with this comment and the final regulation has been so 
changed.
    Several commenters expressed concerns about the applicability of 
Environmental Protection Agency regulations in 40 CFR parts 61 and 190, 
noting that although 10 CFR part 20 incorporates 40 CFR part 190, 10 
CFR part 76 did not explicitly reference 40 CFR part 190. The NRC notes 
that because the Corporation is required to comply with 10 CFR part 20, 
it must also comply with 40 CFR part 190, and 40 CFR part 61, Subpart 
H, and that explicit references in part 76 are not necessary.
    One commenter noted that certain of the existing regulations 
referenced by the proposed rule provided for the imposition of civil 
penalties but contended that authority for the NRC to issue a civil 
penalty is not included in the Energy Policy Act. The NRC agrees with 
the comment and the final rule has been revised to delete the civil 
penalty provisions.
    Section 76.62  Issuance of certificate and/or approval of 
compliance plan. This section specifies that the Director, NMSS, will 
issue a written decision on the Corporation's application and states 
that the Corporation or affected members of the public who have 
provided comments in the proceeding may seek the Commission's review of 
the Director's decision.
    The Corporation recommended that this section be revised to clarify 
that a certificate and a compliance plan are not exclusive of the 
issuance of the other. They also expressed concern that the proposed 
language might be interpreted to require the Director to withhold the 
certificate of compliance in its entirety if there are any outstanding 
areas of noncompliance. They requested that the language of the 
proposed rule be modified to explicitly state that a certificate of 
compliance would be issued for all areas of full compliance and a 
compliance plan for areas of current noncompliance. The Commission 
agrees that it may issue a certificate of compliance covering those 
areas where the Corporation is in compliance with applicable 
requirements and the Commission may also approve concurrently a 
compliance plan for areas of noncompliance. This section is modified to 
clarify this intent.
    The Corporation requested modification of proposed Sec. 76.62(c) to 
provide that petitions for the Commission's review of a Director's 
decision to issue a certificate and/or approve a compliance plan 
``shall be limited to matters raised in the petitioner's written or 
verbal comments.'' The Commission declines to limit petitioners for 
Commission review to matters raised in that petitioner's previous 
written or verbal comments. A Director's decision on a certificate or 
proposed compliance plan may respond to issues raised by other 
commenters or include provisions that a commenter did not anticipate. 
For these reasons, those persons whose interests may be affected and 
who submitted written or verbal comment on an application will be 
permitted to seek Commission review of the Director's decision.
    One commenter, OCRE, felt that the 15-day period (from the date of 
Federal Register Notice) for filing a petition for Commission review of 
a Director's decision to grant or deny a certificate, or approve or 
disapprove a compliance plan, was too short. OCRE requested that this 
15-day period be extended to at least 25 days. It stated that some 
commenters, particularly individuals and public interest groups that 
depend upon libraries for access to the Federal Register, may not learn 
of the Director's decision within 15 days unless the Director's 
decision is provided to all commenters on the application for a 
certificate.
    The Corporation stated that the 15-day period for filing of a 
petition for review of a Director's decision to deny a certificate or 
not approve a compliance plan was too short and requested at least 30 
days to file such a petition. The Corporation also recommended that the 
rules provide that a Commission decision denying an application for a 
certificate or disapproving a compliance plan must state that it does 
not become effective until at least 10 days after the date of the 
decision. In support of these recommendations, the Corporation stated 
that a denial could have a significant impact on it and may have 
potential implications for national and public policy because the 
gaseous diffusion plants supply 40 percent of the world market and 90 
percent of the domestic market for enriched uranium and are currently 
the sole domestic source of enrichment services.
    Both the Corporation and OCRE felt that the 10-day period from the 
date of filing a petition for review for responding to a petition for 
review was too short. The Corporation requested that this 10-day period 
for filing responses to a petition for review be extended to 30 days 
because of the burden and prejudice that might occur if the Corporation 
were faced with multiple petitions.
    OCRE requested that this 10-day period for responding to a petition 
be lengthened to at least 20 days. To ensure adequate notice to 
interested commenters, OCRE requested not only service of the 
Director's decision on commenters but also a mechanism for ensuring 
that commenters could receive timely notice of a petition for review. 
OCRE observed that the cost of requiring a petitioner to serve all 
commenters could be prohibitive and suggested a remedy such as a 
telephone information line with recorded information on the case or a 
computerized bulletin board system.
    The Commission recognizes that the time periods for filing of a 
petition for Commission review and responding to a petition for review 
are relatively short. The Commission's flexibility in the timing of the 
certification process is limited, as noted above, because of the need 
for an expeditious determination of the application on an annual basis, 
including staff review of the application and public comments, 
preparation and issuance of the NMSS Director's decision, and 
consideration of petitions for review by the Commission.
    The Commission will promptly make copies of an application for a 
certificate or approval of a compliance plan available in local public 
document rooms at or near the gaseous diffusion plants and will issue a 
press release at the time the Director's decision is issued. The 
Commission also intends to make promptly available copies of all 
Federal Register notices relating to the certification process, as well 
as petitions for review, and responses to petitions for review at those 
locations. In addition, the NRC staff will examine the feasibility of 
establishing a computer bulletin board to provide information on the 
application's status.
    For these reasons, the Commission has not altered the time periods 
for filing of petitions for review or responses thereto. However, the 
Commission has added Sec. 76.74 to the final rule that clarifies the 
computation of designated time periods and confirms the Commission's 
ability to extend or shorten time periods for action for good cause. 
Therefore, the Commission may be able to provide some extension of the 
period for filing of petitions and responses if time permits during the 
period of a particular certification process.
    The Commission declines to specify by regulation that a decision 
denying an application for a certificate or disapproving a compliance 
plan must state that it does not become effective until at least 10 
days after the date of the decision. The Commission has determined that 
binding itself to such a delay would be inappropriate in emergency 
circumstances.
    Section 76.64  Denial of certificate or compliance plan. This 
section states that the Director, NMSS, may deny the Corporation's 
application and that the denial will be noticed in the Federal 
Register. This section also provides an opportunity for the Corporation 
to submit a compliance plan before the denial is issued. It also states 
that the Corporation or affected members of the public who have 
provided comments on the application may seek the Commission's review 
of the Director's decision.
    In response to a comment, this section is revised to clarify that 
the compliance plan is a DOE document.
    Section 76.66  Expiration and termination of certificate. The 
Corporation requested that the NRC add a new section to the final rule 
which would address expiration and termination of certificates.
    The Commission agrees that these provisions are useful. Thus, a 
Sec. 76.66 has been added to the final rule. Paragraph (a) clarifies 
that ``except as provided in Sec. 76.55 [timely renewal], a certificate 
expires at the end of the day, in the month and year stated.'' 
Paragraph (b) adds a requirement of prompt notice to the Commission 
when the Corporation decides to terminate operation of either of the 
GDPs and other authorized activities under the certificate. Paragraph 
(c) clarifies that the Corporation must terminate operations on or 
before the expiration date in the existing certificate if it does not 
submit an application for renewal of the certificate.
    Section 76.68  Plant changes. This section describes plant or 
operational changes by the Corporation permitted without prior 
Commission approval. Documentation of these revisions must be submitted 
to the NRC. To make other changes would require Commission approval and 
would require the Corporation to apply for an amendment of the 
certificate under Sec. 76.45.
    Several comments were received concerning this section. The 
Commonwealth of Kentucky commented that the Corporation should not be 
allowed to make changes without modification of their certificate. 
Another commenter stated that the section should be preserved as 
written and incorporated into 10 CFR Part 70. The Corporation commented 
that the proposed section is overly restrictive and should be closely 
modeled after 10 CFR 50.59. The Department of Energy (DOE) recommended 
changes that would make it consistent with current DOE Orders.
    As written, Sec. 76.68 permits changes similar to those permitted 
under 10 CFR 50.59 for reactors and provides flexibility that is beyond 
that currently provided for in 10 CFR part 70. Because these plants 
will not have technical specifications as referenced in 10 CFR 50.59, 
the detailed criteria for evaluation of changes permitted without prior 
Commission approval are needed in Sec. 76.68. The Commission does not 
believe the evaluation provisions are overly restrictive as suggested 
by the Corporation and the evaluation provisions are retained.
    Comments were also received concerning the requirement that reports 
describing changes made under this section be submitted within 90 days 
of their adoption. The final rule has been changed to conform with 10 
CFR 50.59 and thus requires that the information on changes be 
submitted annually or at shorter intervals as specified in the 
certificate.
    The Commission believes that the clarified final rule will permit 
changes that do not decrease safety and still provide the Corporation 
flexibility in the operation of the facilities. The Commission has not 
deleted this section as requested by one commenter because the 
procedures contained in this section ensure that those changes which 
are permitted will not be in conflict with any certification 
requirements.
    Still another comment on Sec. 76.68 requested that the term 
``unreviewed safety question'' be defined. The NRC has no objection to 
this definition and has added a definition similar to the usage of the 
term in 10 CFR 50.59.
    A comment from DOE was also adopted that requires the Corporation 
to evaluate any as-found conditions that do not agree with the plant's 
programs, plans, policies, and operations in accordance with this 
section. This comment was adopted to ensure that any exceptions to what 
is assumed or understood are evaluated.
    Section 76.70  Post-issuance. This section specifies procedures for 
amendment, revocation, suspension, or amendment for cause of the 
certificate.
    The proposed rule provided that the Commission would provide ``the 
Corporation and other interested persons with an opportunity to provide 
written views to the Commission'' in connection with a proceeding to 
amend, revoke, or suspend a certificate of compliance or compliance 
plan. The proposed rule also provided that the Commission ``may adopt 
by order further procedures for a hearing of the issues before making a 
final enforcement decision.''
    In its comments, the Corporation requested that participation in 
these enforcement actions be limited to persons whose interests may be 
``adversely affected'' by the proposed enforcement action. The 
Corporation indicates that this change would make public participation 
rights more consistent with those applicable to similar enforcement 
proceedings for NRC licensees. In particular, the Corporation seeks to 
ensure that the NRC would preclude participation in an NRC enforcement 
action by persons seeking more stringent enforcement action than is 
proposed by the Commission.
    The Commission does not believe it is necessary to limit public 
participation to those who are adversely affected by the order or the 
proceeding. Such a limitation could necessitate substantial or 
protracted consideration of whether a person submitting written 
comments on a proposed enforcement action was adversely affected. This 
would be inefficient and contrary to the intent of providing for an 
expeditious, informal resolution of the enforcement action unless such 
a procedure is inadequate for determination of the issues. Informal 
enforcement procedures that would foster expeditious resolutions are 
desirable, wherever sufficient, because a certification process which 
also affords opportunities for public participation will be occurring 
on an annual basis.
    If the Commission determines that more extensive adjudicatory 
procedures are necessary in a particular case, it may order use of 
further procedures, such as those in 10 CFR part 2, subpart G or 
subpart L. In these cases, intervention would depend on the showing of 
how a petitioner's interest is affected in accordance with the adopted 
procedures.
    However, the general procedural description of post-issuance 
enforcement action in the proposed rule does not foreclose the 
Commission's ability to limit the scope of a proceeding or define the 
issues for determination in any enforcement action. For clarity, 
Sec. 76.70 has been revised to specify the procedures that would be 
followed in an enforcement action in more detail.
    First, the final rule makes explicit that the Commission may 
institute a proceeding to modify, suspend, or revoke a certificate or 
approved compliance plan, or to take other action as appropriate by 
service of an order on the Corporation that specifies: The proposed 
action; the alleged violations, or potentially hazardous conditions, or 
other facts deemed to be sufficient ground for the proposed action; a 
reasonable period for submission of a written response to the order and 
for submission of written views by interested persons within a 
reasonable period after publication of the order in the Federal 
Register; issues for resolution if the proposed action is contested; 
and the effective date of the order. If the order is made immediately 
effective pending further order, the order must include a statement of 
reasons for making the proposed action immediately effective.
    Second, the final rule clarifies, inter alia, that the Corporation 
may promptly request that the Commission set aside the effectiveness of 
an immediately effective order, provided that the request specifically 
states the reason why the order is not based on adequate evidence and 
is accompanied by affidavits or evidence upon which the Corporation 
relies. The NRC shall respond within 5 days of the receipt of the 
motion.
    These details of the procedural process are similar to those which 
apply to issuance of orders to licensees under 10 CFR part 2, subpart 
B. However, they preserve the provision for informal procedures for 
resolution of the action in the absence of a determination that more 
extensive procedures are appropriate.
    In addition, the final rule adopts a suggestion from DOE that 
information submitted under this section by the Corporation be signed 
under oath or affirmation.
    Section 76.72  Miscellaneous procedural matters. This section 
addresses procedures for filing petitions, ruling on matters of 
procedure, and communication between Commission and NRC staff. 
Additional guidance regarding the filing and service of petitions for 
review of the NMSS Director's decision and responses to these petitions 
may be included in the Director's decision or by order of the 
Commission.
    Except for proceedings under 10 CFR part 2, subpart G, for 
imposition of a civil penalty resulting from violations of section 206 
of the Energy Reorganization Act of 1974, the Commission is not 
imposing 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 this regulatory process. The NRC staff would not participate 
in a review of the Director's decision as a party but would serve as an 
advisor to the Commission. Congress has not required formal 
adjudication. The Commission believes that informal processing without 
such formal restrictions on communication is best suited for resolution 
of annual applications for a certificate.
    Section 76.74  Computation of extension of time. This section has 
been added to the final rule to specify the duration of designated time 
periods and confirm the Commission's ability to extend or shorten time 
periods for action for good cause and specifies that additional time 
would be granted in the event that a required date falls on a Saturday, 
Sunday or legal holiday.

C. Technical Safety Requirements

    The major technical safety requirements are found in the following 
sections:
    Section 76.35  Contents of initial applications. This section 
specifies that applications must include a safety analysis report, a 
compliance status report which includes environmental and effluent 
monitoring data, a quality assurance program description, a description 
of the use of radioactive material, a description of the training 
program, a nuclear material control and accounting plan, a physical 
protection plan for special nuclear material in transit, a plant 
physical security plan, an emergency plan, a plan for security facility 
approval and protection of classified information and hardware, a 
description of the Corporation's response necessary to implement the 
International Atomic Energy Agency safeguards agreement, and a 
description of the waste treatment and management program.
    The Corporation requested a change in format regarding contents of 
applications for the purpose of increased clarity regarding the precise 
scope of the initial application and of renewal applications. Included 
in the proposed restructuring was revision of proposed Sec. 76.35 
pertaining to contents of application so as to limit its scope to the 
contents of the initial application. The Corporation also recommended 
the addition of a new Sec. 76.36 that would present the precise content 
of the annual resubmittal.
    The NRC agrees that the revised format will add clarity to the 
prescribed content of the initial and renewal applications. As a result 
of the restructuring, the final rule makes Sec. 76.35 applicable to 
initial applications and adds a new Sec. 76.36 applicable to annual 
renewal.
    The Corporation also recommended an application procedure which 
would generally follow the guidance of NRC Regulatory Guide 3.52. These 
proposed changes were based on an application which would contain a 
``Part I'' comprised of binding certificate ``conditions'' and a ``Part 
II'' containing a nonbinding safety demonstration. This restructuring 
was not adopted. This decision is based on a recent review of the 
Commission's current licensing and oversight programs for fuel cycle 
plants1 that indicates the ``Part I/II'' approach will probably be 
changed and that safety analysis reports will be required. The 
Corporation, in its comments, identified the ``Part II'' safety 
demonstration to be functionally equivalent to the safety analysis 
report. While this is generally true, with respect to technical 
content, the NRC believes that safety analysis reports are preferable 
because they provide more rigorous, binding documentation of the basis 
for safe operation of a plant. Changes to the safety analysis report 
would be permitted only in accordance with Sec. 76.68.
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    \1\ Proposed Method for Regulating Major Materials Licensees, 
NUREG-1324.
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    In publishing the draft 10 CFR part 76, the Commission specifically 
requested comments on the appropriateness of requiring the Corporation 
to provide financial assurance for the costs associated with 
decontamination and decommissioning of the gaseous diffusion plants. 
Comments were received favoring both retention and deletion of a 
financial assurance requirement. The Corporation commented that DOE was 
responsible for decontamination and decommissioning of the gaseous 
diffusion plants under the AEA and that the financial assurance 
requirements should not apply to the Corporation. DOE, on the other 
hand, noted that it is only responsible for decontamination and 
decommissioning of pre-existing conditions under the AEA and that the 
Corporation will remain responsible for other costs associated with 
decontamination and decommissioning, including the costs associated 
with disposal of wastes generated during Corporation operation of the 
GDPs.
    The NRC has determined that the Corporation does have some limited 
financial responsibility for decontamination and decommissioning 
activities. The Corporation has acknowledged in its comments that, 
under its lease with DOE, there is at least one area where it remains 
responsible for the costs of decommissioning. Specifically, the 
Corporation has acknowledged that it is responsible for any increased 
costs for DOE decontamination and decommissioning of the facilities 
that arise from removal by the Corporation of capital improvements the 
Corporation makes at the facilities. In addition, the terms of the DOE/
Corporation lease provide that the Corporation is to remain financially 
responsible, even after return of the GDPs to DOE, for the ultimate 
treatment and disposal of wastes generated by the Corporation. 
Nevertheless, the NRC has determined that the language in the draft 10 
CFR part 76 requiring financial assurance from the Corporation was 
written to apply to a broader scope of decontamination and 
decommissioning activities than are the Corporation's responsibility. 
Accordingly, the final rule has been revised to require that the 
Corporation provide financial assurance for only those aspects of the 
decontamination and decommissioning costs which are their 
responsibility.
    Two commenters asked that the Corporation be required to 
demonstrate compliance with the applicable provisions of 10 CFR Part 61 
which deal with waste classification and waste disposal because these 
requirements are essential for the proper handling and disposal of all 
wastes at the GDPs. Waste classification is covered under 10 CFR part 
20, subpart K; therefore, an additional reference to 10 CFR part 61 is 
not needed.
    One commenter suggested that a specific license be required if the 
Corporation proposes to treat radioactive waste at one plant that was 
received from the other plant and that the Corporation be required to 
obtain approvals for the treatment from the Central Midwest Interstate 
Low-Level Radioactive Waste Commission. Plans for treatment of any 
radioactive waste stream by the Corporation are a required part of the 
initial application for certification under proposed Sec. 76.35(k). The 
certification process, therefore, will include consideration of the 
waste stream issue. Under Section 1701 (c)(3) of the AEA, the 
certification process is in lieu of any other requirement for a license 
for the gaseous diffusion plants leased by the Corporation from the 
DOE. Accordingly, no NRC issued specific license addressing the 
radioactive waste streams at the DOE gaseous diffusion plants being 
leased to the Corporation is required.
    DOE suggested that the rule specifically prohibit the Corporation 
from transporting special nuclear material of moderate strategic 
significance (Category II material) or formula quantities of special 
nuclear material (Category I material). These activities are not 
contemplated, and this prohibition has been included in the rule.
    One commenter suggested that the rule include the requirement for 
semiannual reporting of effluents as contained in the Corporation 
proposal. Although semiannual reporting is a requirement in 10 CFR part 
70, this recommendation was not adopted. Semiannual reporting is 
intended for licensees who hold multi-year licenses. The Corporation 
will be required to report its annual effluent with the certification 
application every year. This is adequate for assessment purposes. There 
appears to be no additional benefit in receiving the information on a 
semiannual basis.
    Section 76.85  Assessment of accidents. This section contains the 
requirement for performance of a safety analysis of the potential for 
releases of radioactive material from accidents.
    Specifically, the rule requires that a safety analysis of the site 
activities be performed to evaluate the potential for releases of 
radiological material from the existing plants. The analysis should 
evaluate expected releases from a reasonable spectrum of postulated 
accident scenarios which may occur in the gaseous diffusion plants, 
taking into account existing systems in operation, including 
procedures, that are intended to mitigate the consequence of any 
release. These potential releases, together with operational practices 
and site characteristics, including meteorology, are to be used to 
evaluate the potential for onsite and offsite radiological 
consequences.
    The Corporation must provide a level of protection against 
accidents during plant operations sufficient to provide adequate 
protection of the public health and safety. In assessing the level of 
protection provided by the Corporation, the NRC will consider both the 
total radiation dose to the whole body and the intake of soluble 
uranium for an individual at the site boundary.
    Several comments were received concerning the level of protection 
against accidents during plant operations sufficient to provide 
adequate protection of public health and safety. The Commission 
specifically requested comments on the use of safety objectives, 
including suggested limiting values with supporting rationale, and 
whether or not they should be included as part of the rule. The 
Environmental Protection Agency stated that the EPA Protective Guides 
(1-5 rem) should be used rather than the criteria discussed in the 
proposed rule and that the values should be specified in the 
regulation. Several other commenters agreed with this approach. Another 
commenter stated that the final standards for accident dose assessment 
should be applied equally to all enrichment facilities. The Corporation 
objected to the use of any limits in the rule or its accompanying 
statements to determine the adequacy of accident analysis results and 
indicated that it is well beyond current regulatory practice. DOE 
suggested addressing chemically toxic material as well.
    The Commission has decided not to include numerical accident limits 
in the final rule. The NRC believes that to include a specific 
numerical limit in the regulation could be unduly restrictive, 
considering that the plants have already been designed and sited and 
the uncertainty of health effects for uranium intakes. The NRC staff 
contracted with Pacific Northwest Laboratory2 to review the 
available literature on uranium toxicity and the results of this review 
suggested that the best estimate of a toxicity threshold would be an 
intake of 30 milligrams of uranium. In assessing the adequacy of 
protection of the public health and safety from potential accidents, 
the NRC will consider whether the potential consequences of a 
reasonable spectrum of postulated accident scenarios exceed .25 Sv (25 
rems), or uranium intakes of 30 milligrams, taking into account the 
uncertainties associated with modeling and estimating such 
consequences.
---------------------------------------------------------------------------

    \2\Fisher, D. R. et al., ``Uranium Hexafluoride Public Risk,'' 
PNL-10065, August 1994.
---------------------------------------------------------------------------

    In considering intakes of soluble uranium, the Commission 
recognizes that the chemical toxicity of uranium could be the limiting 
factor in the accident analysis under this section. The Commission's 
intended use of chemical toxicity considerations in part 76 is 
consistent with its practice elsewhere (e.g., 10 CFR 20.1201(e)), and 
prevents any potential regulatory gap in public protection against 
toxic effects of soluble uranium.
    The EPA guidelines of 1-5 rem for offsite protection action 
recommendations are appropriate for emergency planning purposes but are 
not appropriate for accident analysis.
    The final rule requires that a safety analysis of the site 
activities be performed to evaluate the potential for releases of 
radiological material from the existing plants. The analysis should 
evaluate releases from a reasonable spectrum of postulated accident 
scenarios which may occur in the gaseous diffusion plants, taking into 
account the existing systems in operation, including procedures, that 
are intended to mitigate the consequence of any release. These 
potential releases, together with operational practices and site 
characteristics, including meteorology, are to be used to evaluate the 
potential onsite and offsite radiological consequences. Technical 
safety requirements will be established to ensure that releases are 
unlikely and, in any case, if releases occur they will be within an 
acceptable range.
    One commenter stated that the NRC would have no mechanism for 
enforcement of numerical limits if they are not included in the 
standards. The certificate issued by the NRC will include limiting 
conditions for operation that will be enforceable.
    LES commented that specific natural phenomena and specific accident 
dose limits should be applied equally to all enrichment facilities. The 
apparent reference for this suggestion was the current NRC review of 
their license application for a new uranium enrichment facility. 
Another commenter expressed concern that the Paducah plant resides in a 
geological rift zone. The NRC will not include specific reference 
design assessment values for the existing Corporation facilities, since 
these facilities are already sited, but will evaluate consequences of 
potential accidents resulting from natural phenomena during review of 
the Corporation's safety analysis.
    A comment was also received concerning the discussion in the 
statement of considerations on the development of guidance on an 
integrated safety analysis (ISA) and applicability to the GDPs. The 
final rule does not include requirements for an ISA because its 
incorporation into the regulatory process is still under NRC staff 
review.
    Section 76.87  Technical safety requirements. This section 
specifies that safety requirements must be included in the application. 
Safety topics to be considered are those mainly associated with plant 
operations, management controls, and confinement of radioactive 
material.
    The rule requires the application to include technical safety 
requirements derived from the analyses and evaluations in the safety 
analysis report. These safety requirements would include safety limits 
and limiting control settings within which process variables would be 
maintained for adequate control to guard against an uncontrolled 
release of radioactivity. The safety requirements would also include 
limiting conditions for operation, surveillance requirements, design 
features, and administrative controls. The requirements are similar to 
operating technical specifications or license conditions applied to 
licensed nuclear facilities to assure that operations are controlled as 
described in the safety analysis report.
    The Corporation requested that the use of the term ``technical 
safety requirements'' (TSRs) be changed to ``operational safety 
requirements'' (OSRs) as the GDPs have historically operated under OSRs 
which are similar to TSRs. The Corporation also suggested a change from 
``Safety Analysis Report'' (SAR) to ``Safety Demonstration'' (SD) as 
being ``functionally equivalent.'' The Commission prefers the term 
``technical safety requirements'' because the requirements may cover 
subjects broader than operations, and because existing Corporation 
operational requirements include matters beyond NRC jurisdiction. 
Similarly, the term ``safety analysis report'' is preferred because it 
is a more generally accepted term. Therefore, no change was made to the 
rule.
    The Corporation also recommended deletion of the list of the 14 
safety topics that are to be addressed as being more appropriate for 
identifying accidents for analysis. DOE referenced the list of safety 
topics as those which must be addressed under assessment of accidents. 
The list of topics to be addressed in the technical safety requirements 
is included to ensure that operations are controlled within certain 
safe parameters under normal, off-normal, and accident conditions. 
Therefore, the list has been retained, but the rule has been revised to 
clarify that the Corporation must describe the procedures and/or 
equipment that reflect consideration of each of the listed safety 
topics.
    Section 76.93  Quality assurance. This section requires a quality 
assurance program. The Commission recognizes that the GDPs are fuel 
cycle facilities and that the appropriate quality assurance (QA) for 
GDPs is not the same as for reactors. The GDPs are existing plants 
designed and constructed around 40 years ago. The QA requirements for 
the GDPs will be based on applying the applicable requirements of ASME 
NQA-1-1989, ``Quality Assurance Program Requirements for Nuclear 
Facilities,'' in a graded approach and to an extent that is 
commensurate with the importance to safety.
    A Corporation comment agreed with use of ASME NQA-1 as a basis for 
a quality assurance program (Sec. 76.93), but expressed concern that 
implementation problems could result if NQA-1 is applied in a manner 
similar to reactors. The Corporation suggested that the rule should 
allow use of equivalent alternatives to NQA-1. If found adequate under 
review, the NRC could approve use of an equivalent alternative to NQA-
1, and the final rule has been revised accordingly.
    Section 76.95  Training. This section requires a description of the 
training program that will be provided to personnel to enable them to 
perform the functions of their jobs, including information on the 
positions for which training will be provided, to assure that personnel 
are qualified to operate and maintain the plants safely and in 
compliance with regulatory requirements.
    The Corporation strongly recommended that the performance-based 
training concept be deleted from the proposed rule and instead require 
the Corporation to ``establish, implement and maintain a training 
program to assure that personnel are adequately trained to perform 
their nuclear-safety related functions.'' They indicated that 
development of performance-based training would go well beyond both the 
existing requirements of 10 CFR part 70 and current practices at the 
GDPs. They further commented that it would subject the Corporation to 
the very costly and difficult task of fully implementing a performance-
based training program by the time that it submits its initial 
application for a certificate. The Corporation believes the proposed 
section will require the GDPs ``to adopt the full performance-based 
training concept embodied in part 50'' which uses the Institute of 
Nuclear Power Operations (INPO) training methodologies for commercial 
power reactor licensees. The Corporation estimates it will cost about 
$8 million to fully develop and implement a training program for 
selected tasks affecting nuclear safety or radiological controls.
    The Commission believes that the performance-based training 
requirement should be retained. The Corporation's main concern is that 
it might be expected to establish training programs of similar 
complexity to those of power reactors, which is not the case. The final 
rule allows flexibility, and the Commission believes that the existing 
training program inherited by the Corporation can be adapted to comply 
with the rule at reasonable cost.
    The Commission must be assured that adequate training is provided 
and that those persons performing operations that could have an effect 
on health and safety have mastery of their operating tasks. Therefore, 
the final rule was not changed. The Commission believes that a training 
program that includes the concepts of performance-based training 
provides that assurance. The Commission also notes that a requirement 
for performance-based training has been established for nuclear power 
reactors and has been determined to be cost-effective for such 
facilities. The Commission does not see any reason to conclude that 
this will not also be the case for the enrichment plants.

D. Incorporation of Existing Regulations

    Portions of existing Commission regulations are applicable to 
certification of the Corporation's operation of the gaseous diffusion 
plants and cross referenced (Sec. 76.60).
    Requirements for notices, instructions, and reports to workers are 
contained in 10 CFR part 19, ``Notices, Instructions, and Reports To 
Workers: Inspection and Investigations.'' Part 19 specifies the 
requirements for notices, instructions, and reports by the Corporation 
to individuals participating in gaseous diffusion activities. It also 
sets forth the rights and responsibilities of the Commission and 
individuals during interviews on any matter within the Commission's 
jurisdiction.
    Requirements for protection against ionizing radiation are 
contained in 10 CFR part 20, ``Standards For Protection Against 
Radiation.'' Part 20 specifies the requirements to control the receipt, 
possession, use, storage, transfer, and disposal of byproduct, source, 
and special nuclear material by the Corporation in such a manner that 
the total dose to an individual (including doses resulting from 
radioactive material and from radiation sources other than background 
radiation) does not exceed the standards for protection against 
radiation prescribed by the NRC for normal operating conditions and 
anticipated operational occurrences.
    A comment was received indicating that the health of the public is 
being placed at risk presently and this policy would continue under the 
proposed NRC rules. The NRC standards require that the Corporation must 
meet part 20 requirements for protection of workers and the public 
against radiation. This includes specific effluent limits that the 
Corporation must meet. The Commission believes that the current 
requirements of part 20 provide for adequate safety for workers and the 
public from radiation effects.
    Requirements for reporting of defects and noncompliance are 
contained in 10 CFR part 21, ``Reporting of Defects and 
Noncompliance.'' Part 21 specifies the procedures and requirements for 
persons to notify the Commission immediately of component defects or 
failure to comply with regulatory requirements which could create a 
substantial safety hazard.
    Requirements for fitness-for-duty programs are contained in 10 CFR 
part 26, ``Fitness-for-Duty Programs.'' Part 26 prescribes requirements 
and standards for the establishment and maintenance of fitness-for-duty 
programs to reduce the likelihood of theft or diversion of strategic 
special nuclear material. The requirements of this part are relevant 
only to the extent that the Corporation elects to engage in activities 
which involve formula quantities of strategic special nuclear material.
    Requirements for packaging and transportation are contained in 10 
CFR part 71, ``Packaging and Transportation of Radioactive Material.'' 
Part 71 establishes requirements and procedures for packaging, 
preparation for shipment, and transportation of radioactive material.
    Requirements for physical security and material control and 
accounting are 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,'' as specified in subpart E to this part. 
Subpart E to part 74 identifies the specific sections that establish 
the requirements and procedures for transfer, protection at fixed sites 
and in transit, and control and accounting of the various enrichments 
of U-235 covered under the certification.
    Safeguards regulation of special nuclear material is conducted on a 
graded basis. The grades reflect the importance of specified kinds and 
quantities of material to the public safety and to the common defense 
and security. Three grades of material are defined in Commission 
regulations. In declining order of importance they are:
    (1) Formula quantities of strategic special nuclear material (also 
referred to by the shorter phrase ``Category I material'');
    (2) Special nuclear material of moderate strategic significance 
(Category II), and
    (3) Special nuclear material of low strategic significance 
(Category III).
    The gaseous diffusion plants are to produce only Category III 
material, and only the safeguards for that grade of material need apply 
to production activities. Nonetheless, the Commission recognizes that 
the Corporation may need to or may opt to engage in nonproduction 
activities that involve the other categories of material. In the past, 
the Portsmouth plant has produced high enriched uranium hexafluoride 
(UF6). As a result of this past production, there may be portions 
of the plant under lease by the Corporation or to which it will have 
access that will continue to have high enriched UF6 fixed to 
interior surfaces of process equipment. Additionally, some areas, such 
as the analytical laboratory, may continue to have a high enriched 
inventory. The Corporation may elect to engage in nonproduction 
business activities that involve high enriched UF6. To be 
responsive to the full range of possible Corporation activities, 
safeguards regulations for all three categories of material are listed 
in subpart E and are to be applied in accordance with the categories of 
material the Corporation actually uses, possesses, or has access to.
    One commenter noted that the referenced requirement of 
Sec. 70.51(d) is not consistent with Sec. 74.33(c)(4)(i) [12 months 
verses 370 days] in specifying the static inventory frequency for 
material control and accounting for uranium. The NRC agrees with this 
comment and has revised Sec. 76.117(a) to specify 370 days as the 
static inventory frequency for the GDPs. The 370-day period contained 
in Sec. 74.33(c)(4)(i) and revised Sec. 76.117(a) provides a full year 
with an additional margin of a few days to provide flexibility.
    Other comments focus on Secs. 74.15(b)(2), 74.33(c)(2), 
74.33(c)(4)(i) and 74.33(c)(6), which are among the various material 
control and accounting requirements referenced in Sec. 76.117. The 
comments request relief from various aspects of these requirements and 
provide rationale in support of the request. The requirements of 
Sec. 74.15 and Sec. 74.33 are performance requirements that must be 
implemented on a site-specific basis for the fundamental nuclear 
material control plans for each site that the Corporation must submit 
for NRC approval. The nuclear material control plans must describe how 
each requirement will be carried out at each of the two sites. After 
approval, the plan will become the principal document that governs 
material control and accounting at the site. Because the requirements 
are performance requirements rather than prescriptive requirements, 
wide latitude exists for achieving appropriate performance for the 
overall material control and accounting program. Accordingly, no change 
to the proposed regulation was made in response to these specific 
comments.
    The requirement the Corporation believes has the greatest potential 
cost impact is Sec. 74.33(c)(4)(i), which requires enrichment 
facilities to conduct periodic inventories of in-process enriched 
uranium for safeguards accountability purposes. This inventory consists 
of a large quantity of material in gaseous form and a relatively small 
quantity of solids. The Corporation requested that the rule require 
measurement of material in the gas phase only. The Corporation believes 
that, due to the size of the facilities, the relatively small quantity 
of solids, and the limitations of instruments in distinguishing between 
the solids and the gaseous material, extensive direct measurement of 
the solids is not practical and the cost would, in any case, be 
prohibitive. The Commission believes that a broad exemption from 
measurement of the solids would undermine the well-established domestic 
and international safeguards principle requiring strict accountability 
of special nuclear material. The Commission further believes that the 
rule can be met by methods other than extensive direct measurements, 
for example, appropriate sampling and use of previous measurements, at 
reasonable cost and, therefore the rule has not been changed.
    In the course of reviewing the comments, it was found that 
Sec. 70.22(h), which contains requirements for physical security plans 
for Category I material, had not been incorporated by reference in 
Sec. 76.113 as was intended. That reference has now been incorporated. 
The change is for completeness and will affect the Corporation only in 
the unlikely event that it elects to operate a Category I plant. 
Additionally, it was found that Sec. 73.70 had been unintentionally 
incorporated by reference into Sec. 76.117. The reference is not 
relevant to Sec. 76.117 and has been deleted.
    NRC does not intend to incorporate any additional requirements for 
personnel security screening for access to or control over special 
nuclear material as contained in 10 CFR part 11, ``Criteria and 
Procedures for Determining Eligibility for Access to or Control over 
Special Nuclear Material,'' if the Corporation elects to engage in 
activities which involve strategic special nuclear material. The 
requirements for this separate access program are met by the DOE access 
authorization program for the GDPs.
    A comment was received indicating that no unrecovered costs should 
be incurred by the NRC in conjunction with certification, and a fee 
schedule should be included in the rule. All NRC costs associated with 
GDP certification are recovered from the Corporation and need not be 
covered in this rule. Fees are covered in 10 CFR parts 170 and 171.
    Requirements for security facility approval and protection of 
classified matter are contained in 10 CFR part 95, ``Security Facility 
Approval and Safeguarding of National Security Information and 
Restricted Data.'' The Corporation and its contractor personnel will be 
considered as authorized by the Commission under Sec. 95.35(a) for 
access to classified matter based on their DOE access authorizations.
    In addition, the Corporation commented that the proposed 
modification to Sec. 95.5 should be deleted because it incorrectly 
attempts to incorporate the Corporation, which is not a licensee, under 
the definition of a ``licensee.'' This suggested revision was adopted 
as ``corporation,'' is covered in Sec. 76.60 and is under the 
definition of ``person'' listed in 10 CFR 95.5.
    The Corporation requested that Sec. 76.119 be modified to require 
examination of 25 percent of the security containers daily on a 
rotational basis if the containers are in a controlled access area. The 
Corporation also recommended that Sec. 76.119 be modified to 
specifically state that 10 CFR 95.37(g), 95.41, 95.43, and parts of 
Sec. 95.47 do not apply to the Corporation and to clarify that document 
control practices implemented under DOE security oversight may 
continue. DOE commented that the rule should include an exception that 
the Corporation be permitted to continue using the applicable DOE 
procedures and practices when a conflict occurs between NRC 
requirements and the DOE documents. The Commission does not accept this 
recommendation, because the regulations for protection of classified 
matter should be consistent for all regulated organizations. The 
provisions of 10 CFR part 95, coupled with an approved security plan 
for the protection of classified matter, will contain all of the 
applicable requirements for security facility approval and for the 
safeguarding of classified matter at the gaseous diffusion plants. The 
Commission does not anticipate any significant conflicts with the 
previous DOE procedures. However, any conflicts that may be identified 
will be resolved on a case-by-case basis.

Security Facility Approval and Safeguarding of National Security 
Information and Restricted Data; Minor Conforming Changes

    Minor editorial changes are also being made to certain sections of 
10 CFR part 95 to clarify that there are unique aspects of uranium 
enrichment facilities and operations which handle, store, process, 
transport, transmit, and destroy classified matter. Specific changes 
include replacing the use of the term ``documents'' with ``matter'' in 
order to include the classified equipment and hardware associated with 
uranium enrichment plants; more precisely defining ``NRC access 
authorizations'' because the Corporation will not be subject to 10 CFR 
part 25; and modifying Sec. 95.36 to include participants in other 
international agreements.
    Section 95.37(a) is also being revised to replace the reference to 
classification guidance previously included as Appendix A to part 95. 
This guidance is available separately in a more usable form such as 
NUREG/BR-0069, Revision 2, ``NRC Classification Guide for National 
Security Information Concerning Nuclear Material And Facilities.'' 
NUREG/BR-0069, which is publicly available, can readily be updated to 
promptly reflect Executive Orders that require modifications to the 
guidance associated with classification issues. Currently, each NRC 
licensee has committed in its approved security plans to using NUREG/BR 
0069 instead of relying on 10 CFR part 95, appendix A. Similarly, the 
GDPs will be expected to reference more up-to-date classification 
guidance such as NUREG/BR-0069 in complying with 10 CFR part 95. 
Because NUREG/BR-0069 is a more appropriate reference than 10 CFR part 
95, appendix A, this appendix is being deleted and appropriate changes 
to Sec. 95.37(a) are being made to reflect the actual use of 
alternative NRC classification guidance documents.

Finding of No Significant Environmental Impact: Availability; 
Categorical Exclusion

    The Commission has determined under the National Environmental 
Policy Act (NEPA) of 1969, as amended, and the Commission's regulations 
in subpart A of 10 CFR part 51, that this rule is not a major Federal 
action significantly affecting the quality of the human environment 
and, therefore, an environmental impact statement is not required. The 
two plants to be regulated by this rule have already been subject to 
evaluation in accordance with NEPA. The Department of Energy has 
prepared an environmental impact statement for the gaseous diffusion 
plant in Piketon, Ohio,3 and an environmental assessment for the 
plant in Paducah, Kentucky.4 The NRC has reviewed those documents, 
as well as environmental reports prepared by DOE for both facilities in 
1992 and environmental audits prepared by DOE prior to turning 
operation of the Facilities over to the Corporation in 1993. The NRC 
also conducted extensive site visits. No significant differences in 
operations, previously evaluated by DOE, were identified that would 
result in current operations having significantly different 
environmental effects than those already evaluated in DOE's 
environmental reviews. The Commission's certification requirements are 
intended to be at least as stringent as the existing requirements 
applicable to the two plants which are currently operating and have 
been operating for nearly 40 years. The promulgation of a rule 
governing these plants, and their subsequent regulation by the NRC, 
will not result in any environmental impacts beyond those previously 
considered by DOE in its environmental reviews and which currently 
exist or would be expected to continue absent NRC regulatory oversight. 
The NRC environmental assessment and finding of no significant impact 
on which this determination is based are available for inspection at 
the NRC Public Document Room, 2120 L Street NW. (Lower Level), 
Washington, DC.
---------------------------------------------------------------------------

    \3\ Final Environmental Impact Statement, Portsmouth Gaseous 
Diffusion Plant Site, May 1977, ERDA-1555; Final Environmental 
Statement, Portsmouth Gaseous Diffusion Plant Expansion, September 
1977, ERDA-1549.
    \4\ Final Environmental Impact Assessment Of The Paducah Gaseous 
Diffusion Plant Site, August 1982, DOE/EA-0155.
---------------------------------------------------------------------------

    Similarly, subsequent certificates of compliance including 
amendments, modifications, and renewals issued pursuant to this part 
will consist of findings of compliance with 10 CFR part 76. Therefore, 
these actions will not result in any significant new environmental 
impacts. The regulations require that the Corporation submit 
information for use by NRC in preparing an environmental assessment for 
certification applications addressing areas where the facilities are 
not in compliance with the requirements of part 76. Part 51 of Title 10 
of the Code of Federal Regulations is being amended to include a 
categorical exclusion for such certification actions pursuant to part 
76.
    Under its procedures implementing NEPA, the Commission may exclude 
from preparation of an environmental impact statement or an 
environmental assessment a category of actions which do not 
individually or cumulatively have a significant effect on the human 
environment and which have been found to have no such effect in NRC 
procedures. In this rulemaking, the Commission finds that the issuance, 
amendment, modification, and revision of a certificate of compliance 
for the Corporation comprise a category of actions which does not 
individually or cumulatively have a significant effect on the human 
environment. Actions within this category are similar in that they will 
be based on a finding by NRC that the Corporation has demonstrated 
compliance with the requirements in part 76. After conducting an 
environmental assessment for part 76, the Commission made a finding of 
no significant environmental impact, and concluded that part 76 
requirements, if promulgated, would not allow the enrichment facilities 
to operate in such a way as to result in any adverse environmental 
effects greater than those which currently exist or would be expected 
to continue absent NRC regulatory oversite. Accordingly, a Commission 
finding of compliance with the part 76 requirements would not have a 
significant effect on the human environment.

Paperwork Reduction Act Statement

    The information collection requirements contained in this rule of 
limited applicability apply only to a wholly-owned instrumentality of 
the United States and affect fewer than 10 respondents. Therefore, 
Office of Management and Budget clearance is not required pursuant to 
the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.).

Regulatory Analysis

    The Commission has prepared a regulatory analysis on this 
regulation. The analysis examines the costs and benefits of the 
alternatives considered by the Commission. The analysis is available 
for inspection in the NRC Public Document Room, 2120 L Street NW. 
(Lower Level), Washington, DC.

Regulatory Flexibility Certification

    As required by the Regulatory Flexibility Act of 1980, 5 U.S.C. 
605(b), the Commission certifies that this rule will not have a 
significant economic impact upon a substantial number of small entities 
because it only addresses the Corporation's operation of two existing 
plants which do not fall into this category.

Backfit Analysis

    The NRC has determined that the backfit rule, 10 CFR 50.109, does 
not apply to this rule, and therefore, a backfit analysis is not 
required.

List of Subjects

10 CFR Part 19

    Criminal penalties, Environmental protection, Nuclear materials, 
Nuclear power plants and reactors, Occupational safety and health, 
Radiation protection, Reporting and recordkeeping requirements, Sex 
discrimination.

10 CFR Part 20

    Byproduct material, Criminal penalties, Licensed material, Nuclear 
materials, Nuclear power plants and reactors, Occupational safety and 
health, Packaging and containers, Radiation protection, Reporting and 
recordkeeping requirements, Source material, Special nuclear material, 
Waste treatment and disposal.

10 CFR Part 21

    Nuclear power plants and reactors, Penalties, Radiation protection, 
Reporting and recordkeeping requirements.

10 CFR Part 26

    Alcohol abuse, Alcohol testing, Appeals, Chemical testing, Drug 
abuse, Drug testing, Employee assistance programs, Fitness for duty, 
Management actions, Nuclear power reactors, Protection of information, 
Reporting and recordkeeping requirements.

10 CFR Part 51

    Administrative practice and procedure, Environmental impact 
statement, Nuclear materials, Nuclear power plants and reactors, 
Reporting and recordkeeping requirements.

10 CFR Part 70

    Criminal penalties, Hazardous materials transportation, Material 
control and accounting, Nuclear materials, Packaging and containers, 
Radiation protection, Reporting and recordkeeping requirements, 
Scientific equipment, Security measures, Special nuclear material.

10 CFR Part 71

    Criminal penalties, Hazardous materials transportation, Nuclear 
materials, Packaging and containers, Reporting and recordkeeping 
requirements.

10 CFR Part 73

    Criminal penalties, Hazardous materials transportation, Export, 
Import, Nuclear materials, Nuclear power plants and reactors, Reporting 
and recordkeeping requirements, Security measures.

10 CFR Part 74

    Accounting, Criminal penalties, Hazardous materials transportation, 
Material control and accounting, Nuclear materials, Packaging and 
containers, Radiation protection, Reporting and recordkeeping 
requirements, Scientific equipment, Special nuclear material.

10 CFR Part 76

    Certification, Criminal penalties, Radiation protection, Reporting 
and recordkeeping requirements, Security measures, Special nuclear 
material, Uranium enrichment by gaseous diffusion.

10 CFR Part 95

    Classified information, Criminal penalties, Reporting and 
recordkeeping requirements, Security measures.

    For the reasons set out in the preamble and under the authority of 
the Atomic Energy Act of 1954, as amended; the Energy Reorganization 
Act of 1974, as amended; and 5 U.S.C. 553; the NRC is adopting the 
following amendments to 10 CFR parts 19, 20, 21, 26, 51, 70, 71, 73, 
74, and 95 and the new 10 CFR part 76.

PART 19--NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: INSPECTION 
AND INVESTIGATIONS

    1. The authority citation for part 19 is revised to read as 
follows:

    Authority: Secs. 53, 63, 81, 103, 104, 161, 186, 68 Stat. 930, 
933, 935, 936, 937, 948, 955, as amended, sec. 234, 83 Stat. 444, as 
amended, sec. 1701, 106 Stat. 2951, 2952, 2953 (42 U.S.C. 2073, 
2093, 2111, 2133, 2134, 2201, 2236, 2282, 2297f); sec. 201, 88 Stat. 
1242, as amended (42 U.S.C. 5841); Pub. L. 95-601, sec. 10, 92 Stat. 
2951 (42 U.S.C. 5851).

    2. Section 19.2 is revised to read as follows:


Sec. 19.2  Scope.

    The regulations in this part apply to all persons who receive, 
possess, use, or transfer material licensed by the Nuclear Regulatory 
Commission pursuant to the regulations in parts 30 through 36, 39, 40, 
60, 61, or part 72 of this chapter, including persons licensed to 
operate a production or utilization facility pursuant to part 50 of 
this chapter, persons licensed to possess power reactor spent fuel in 
an independent spent fuel storage installation (ISFSI) pursuant to part 
72 of this chapter, and in accordance with 10 CFR 76.60 to persons 
required to obtain a certificate of compliance or an approved 
compliance plan under part 76 of this chapter. The regulations 
regarding interviews of individuals under subpoena apply to all 
investigations and inspections within the jurisdiction of the Nuclear 
Regulatory Commission other than those involving NRC employees or NRC 
contractors. The regulations in this part do not apply to subpoenas 
issued pursuant to 10 CFR 2.720.

PART 20--STANDARDS FOR PROTECTION AGAINST RADIATION

    3. The authority citation for Part 20 is revised to read as 
follows:

    Authority: Secs. 53, 63, 65, 81, 103, 104, 161, 182, 186, 68 
Stat. 930, 933, 935, 936, 937, 948, 953, 955, as amended, sec. 1701, 
106 Stat. 2951, 2952, 2953 (42 U.S.C. 2073, 2093, 2095, 2111, 2133, 
2134, 2201, 2232, 2236, 2297f), secs. 201, as amended, 202, 206, 88 
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).

    4. Section 20.1002 is revised to read as follows:


Sec. 20.1002  Scope.

    The regulations in this part apply to persons licensed by the 
Commission to receive, possess, use, transfer, or dispose of byproduct, 
source, or special nuclear material or to operate a production or 
utilization facility under parts 30 through 36, 39, 40, 50, 60, 61, 70, 
or 72 of this chapter, and in accordance with 10 CFR 76.60 to persons 
required to obtain a certificate of compliance or an approved 
compliance plan under part 76 of this chapter. The limits in this part 
do not apply to doses due to background radiation, to exposure of 
patients to radiation for the purpose of medical diagnosis or therapy, 
or to voluntary participation in medical research programs.

PART 21--REPORTING OF DEFECTS AND NONCOMPLIANCE

    5. The authority citation for Part 21 is revised to read as 
follows:

    Authority: Sec. 161, 68 Stat. 948, as amended, sec. 234, 83 
Stat. 444, as amended, sec. 1701, 106 Stat. 2951, 2953 (42 U.S.C. 
2201, 2282, 2297f); secs. 201, as amended, 206, 88 Stat. 1242, as 
amended, 1246 (42 U.S.C. 5841, 5846).
    Section 21.2 also issued under secs. 135, 141, Pub. L. 97-425, 
96 Stat. 2232, 2241 (42 U.S.C. 10155, 10161).

    6. Section 21.2 is amended by adding paragraph (e) to read as 
follows:


Sec. 21.2  Scope.

* * * * *
    (e) The regulations in this part apply in accordance with 10 CFR 
76.60 to each individual, partnership, corporation, or other entity 
required to obtain a certificate of compliance or an approved 
compliance plan under part 76 of this chapter.

PART 26--FITNESS-FOR-DUTY PROGRAMS

    7. The authority citation for Part 26 is revised to read as 
follows:

    Authority: Secs. 53, 81, 103, 104, 107, 161, 68 Stat. 930, 935, 
936, 937, 948, as amended, sec. 1701, 106 Stat. 2951, 2952, 2953 (42 
U.S.C. 2073, 2111, 2112, 2133, 2134, 2137, 2201, 2297f); secs. 201, 
202, 206, 88 Stat. 1242, 1244, 1246, as amended (42 U.S.C. 5841, 
5842, 5846).

    8. Section 26.2 is amended by adding paragraph (d) to read as 
follows:


Sec. 26.2  Scope.

* * * * *
    (d) The regulations in this part apply to the Corporation required 
to obtain a certificate of compliance or an approved compliance plan 
under part 76 of this chapter 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. 26.2(a)(1) through (5).

PART 51--ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC 
LICENSING AND RELATED REGULATORY FUNCTIONS

    9. The authority citation for Part 51 is revised to read as 
follows:

    Authority: Sec. 161, 68 Stat. 948, as amended, sec. 1701, 106 
Stat. 2951, 2952, 2953, (42 U.S.C. 2201, 2297f); secs. 201, as 
amended, 202, 88 Stat. 1242, as amended, 1244 (42 U.S.C. 5841, 
5842).

    10. Section 51.22 is amended by adding paragraph (c)(19) to read as 
follows:


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

* * * * *
    (c) * * *
    (19) Issuance, amendment, modification, or renewal of a certificate 
of compliance of gaseous diffusion enrichment facilities pursuant to 10 
CFR part 76.
* * * * *

PART 70--DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL

    11. The authority citation for Part 70 is revised to read as 
follows:

    Authority: Secs. 51, 53, 161, 182, 183, 68 Stat. 929, 930, 948, 
953, 954, as amended, sec. 234, 83 Stat. 444, as amended, sec. 1701, 
106 Stat. 2951, 2952, 2953 (42 U.S.C. 2071, 2073, 2201, 2232, 2233, 
2282, 2297f); secs. 201, as amended, 202, 204, 206, 88 Stat. 1242, 
as amended, 1244, 1245, 1246, (42 U.S.C. 5841, 5842, 5845, 5846).
    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 70.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 
2951 (42 U.S.C. 5851). Section 70.21(g) also issued under sec. 122, 
68 Stat. 939 (42 U.S.C. 2152). Section 70.31 also issued under sec. 
57d, Pub. L. 93-377, 88 Stat. 475 (42 U.S.C. 2077). Sections 70.36 
and 70.44 also issued under sec. 184, 68 Stat. 954, as amended (42 
U.S.C. 2234). Section 70.61 also issued under secs. 186, 187, 68 
Stat. 955 (42 U.S.C. 2236, 2237). Section 70.62 also issued under 
sec. 108, 68 Stat. 939, as amended (42 U.S.C. 2138).

    12. Section 70.1 is amended by revising paragraph (a) and adding 
paragraph (d) to read as follows:


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.
* * * * *
    (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.

PART 71--PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL

    13. The authority citation for Part 71 is revised to read as 
follows:

    Authority: Secs. 53, 57, 62, 63, 81, 161, 182, 183, 68 Stat. 
930, 932, 933, 935, 948, 953, 954, as amended, sec. 1701, 106 Stat. 
2951, 2952, 2953 (42 U.S.C. 2073, 2077, 2092, 2093, 2111, 2201, 
2232, 2233, 2297f); secs. 201, as amended, 202, 206, 88 Stat. 1242, 
as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).
    Section 71.97 also issued under sec. 301, Pub. L. 96-295, 94 
Stat. 789-790.

    14. Section 71.0 is amended by adding paragraph (e) to read as 
follows:


Sec. 71.0  Purpose and scope.

* * * * *
    (e) 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.

PART 73--PHYSICAL PROTECTION OF PLANTS AND MATERIALS

    15. The authority citation for Part 73 is revised to read as 
follows:

    Authority: Secs. 53, 161, 68 Stat. 930, 948, as amended, sec. 
147, 94 Stat. 780 (42 U.S.C. 2073, 2167, 2201); sec. 201, as 
amended, 204, 88 Stat. 1242, as amended, 1245, sec. 1701, 106 Stat. 
2951, 2952, 2953 (42 U.S.C. 5841, 5844, 2297f).
    Section 73.1 also issued under secs. 135, 141, Pub. L. 97-425, 
96 Stat. 2232, 2241 (42 U.S.C. 10155, 10161). Section 73.37(f) also 
issued under sec. 301, Pub. L. 96-295, 94 Stat. 789 (42 U.S.C. 5841 
note). Section 73.57 is issued under sec. 606, Pub. L. 99-399, 100 
Stat. 876 (42 U.S.C. 2169).

    16. Section 73.1 is amended by adding paragraph (b)(9) to read as 
follows:


Sec. 73.1  Purpose and scope.

* * * * *
    (b) * * *
    (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.

PART 74--MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR 
MATERIAL

    17. The authority citation for Part 74 is revised to read as 
follows:

    Authority: Secs. 53, 57, 161, 182, 183, 68 Stat. 930, 932, 948, 
953, 954, as amended, sec. 234, 83 Stat. 444, as amended, sec. 1701, 
106 Stat. 2951, 2952, 2953 (42 U.S.C. 2073, 2077, 2201, 2232, 2233, 
2282, 2297f); secs. 201, as amended, 202, 206, 88 Stat. 1242, as 
amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).

    18. Section 74.2 is amended by adding paragraph (d) to read as 
follows:


Sec. 74.2  Scope.

* * * * *
    (d) 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.
    19. A new part 76 is added to 10 CFR Chapter I to read as follows:

PART 76--CERTIFICATION OF GASEOUS DIFFUSION PLANTS

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.
76.23  Specific exemptions.

Subpart B--Application

76.31  Annual application requirement.
76.33  Application procedures.
76.35  Contents of initial application.
76.36  Annual renewals.
76.37  Federal Register notice.
76.39  Public meeting.
76.41  Record underlying decisions.
76.43  Annual 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: Secs. 161, 68 Stat. 948, as amended, secs. 1312, 
1701, 106 Stat. 2932, 2951, 2952, 2953 (42 U.S.C. 2201, 2297b-11, 
2297f); secs. 201, as amended, 204, 206, 88 Stat. 1244, 1245, 1246 
(42 U.S.C. 5841, 5842, 5845, 5846).
    Sec. 76.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 
2951 (42 U.S.C. 5851). Sec. 76.35(j) also issued under sec. 122, 68 
Stat. 939 (42 U.S.C. 2152).

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).


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), 
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 pursuant to a plan for the 
privatization of USEC that is approved by the President in accordance 
with Sections 1501 and 1502 of the Atomic Energy Act of 1954, as 
amended.
    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 (Secs. 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 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 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.
    Uranium enrichment plant means:
    (1) Any plant used for separating the isotopes of uranium or 
enriching uranium in the isotope 235, using gaseous diffusion 
technology; 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, using 
gaseous diffusion technology.


Sec. 76.5  Communications.

    Except where otherwise specified, all correspondence, reports, 
applications, and other written communications submitted pursuant to 10 
CFR part 76 should be addressed to the Director, Office of Nuclear 
Material Safety and Safeguards, ATTN: Document Control Desk, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, and copies 
sent to the NRC Region III Office (shown in appendix D of part 20 of 
this chapter) and the applicable Resident Inspector. Communications and 
reports may be delivered in person at the Commission's offices at 11555 
Rockville Pike, Rockville, Maryland, or at the NRC Public Document Room 
2120 L Street, NW. (Lower Level), Washington DC.


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.
    (2) 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 not later than the date of 
Director's decision on the initial certificate of compliance and/or an 
initial plan for achieving compliance, 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 or by 
contacting the NRC Office of Information Resource Management, Division 
of Information Support Services, Information and Records Management 
Branch.
    (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.


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 of 1980 (44 U.S.C. 3501 et seq.).


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.
    (c) Paragraph (b) of this section does not apply until the initial 
certification application is submitted pursuant to Sec. 76.31.


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 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; except, that the Corporation is 
not subject to the authority of Section 234 of the Act.
    (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.


Sec. 76.21  Certificate required.

    (a) After the Commission completes the initial certification 
process, 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 pursuant to this part. Except as authorized by the 
NRC under other provisions of this chapter, no person other than the 
Corporation or its contractors may 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 Secs. 30.41, 40.41, 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.


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  Annual application requirement.

    The Corporation shall file an initial certificate application in 
19951, and thereafter, the Corporation shall apply to the 
Commission each year on or before April 15, for a certificate of 
compliance in accordance with Sec. 76.36.
---------------------------------------------------------------------------

    \1\The initial filing for a certificate of compliance must be 
tendered no later than 6 months after the effective date of this 
rule or by April 15, 1995, whichever is later.
---------------------------------------------------------------------------


Sec. 76.33  Application procedures.

    (a) Filing requirements. (1) An application for an initial 
certificate of compliance must be tendered by filing 20 copies of the 
application with the Director, 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 of this 
part.
    (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, 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 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.
    (b) Oath or affirmation. An application for an initial 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 prior to filing an initial application.
    (d) Additional information. At any time during the review of an 
initial application, the Corporation may be required to supply 
additional information to the Commission's staff in order 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. An initial application which contains 
Restricted Data, National Security Information, Safeguards Information, 
Unclassified Controlled Nuclear Information, proprietary data, or other 
withholdable information, must be prepared in such a manner that all 
such information or data are separated from the information to be made 
available to the public.


Sec. 76.35  Contents of initial application.

    The application for an initial 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 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) In response to a written request by the Commission, the 
Corporation shall file with the Commission the installation information 
described in Sec. 75.11 of this chapter on Form N-71. The Corporation 
shall also permit verification of this installation information by the 
International Atomic Energy Agency and take any other action necessary 
to implement the US/IAEA Safeguards Agreement, as set forth 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 annual application for certification.


Sec. 76.36  Annual renewals.

    (a) After issuance by the Commission of the initial certificate of 
compliance and/or an approved compliance plan, the Corporation shall 
file an annual application 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 in 
Sec. 76.35. The changes must be marked and dated for easy 
identification.


Sec. 76.37  Federal Register notice.

    The Director shall 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 in the Commission's Public Document Room at 2120 L Street, 
NW. (Lower Level), Washington, DC, and in the local public document 
room at or near the location of the plant);
    (b) A notice of opportunity for written public comment on the 
application; and
    (c) The date of any scheduled public meeting regarding the 
application.


Sec. 76.39  Public meeting.

    (a) A public meeting will be held on an application 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.
    (b) Conduct of public meeting.
    (1) The Director shall conduct any public meeting held on the 
application.
    (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 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.


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 2.790.


Sec. 76.43  Annual 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 decision and publishes notice of the new date in the Federal 
Register.


Sec. 76.45  Application for amendment of certificate.

    (a) Contents of amendment application. In addition to the annual 
application for certification submitted pursuant to Sec. 76.31, the 
Corporation may at any time apply for amendment of the certificate to 
cover proposed new or modified activities. The amendment application 
should contain sufficient information for the Director to make findings 
of compliance or acceptability for the proposed activities as required 
for the original certificate.
    (b) Director's decision. Upon receipt of the Corporation's 
application for amendment of the certificate, the Director will 
determine whether the proposed activities are significant, and if so, 
follow the procedures specified in Secs. 76.37 and 76.39. If the 
Director determines that the activities are not significant, the 
Director will, after appropriate review, issue a decision pursuant to 
subpart C of this part.
    (c) 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.

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 
annual 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.


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) Civil penalties may not be imposed on the Corporation pursuant 
to Sec. 19.30 of this chapter except for violations of Section 206 of 
the Energy Reorganization Act.
    (2) The Corporation shall post NRC Form 3 not later than the date 
of Director's decision on the initial certificate of compliance and/or 
an initial plan for achieving compliance, 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) Civil penalties may not be imposed on the Corporation pursuant 
to Sec. 20.2401 of this chapter except for violations of section 206 of 
the Energy Reorganization Act.
    (2) The Corporation shall comply with the requirements in this part 
not later than the date of the Director's decision on the initial 
certificate of compliance and/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 
Secs. 21.6 and 21.21 not later than the date of the Director's decision 
on the initial certificate of compliance and/or an initial plan for 
achieving compliance.
    (2) Under Sec. 21.31, procurement documents issued by the 
Corporation after it submits the initial application for a certificate 
of compliance 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. 26.2(a) (1) 
through (5).
    (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 provided, however, that civil penalties shall 
not be imposed on the Corporation pursuant to Sec. 95.61 of this 
chapter except for violations of Section 206 of the Energy 
Reorganization Act.


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.
    (b) The Director shall publish notice of the decision in the 
Federal Register.
    (c) The Corporation, or any person whose interest may be affected 
and who submitted written comments in response to the Federal Register 
Notice on the application or compliance plan under Sec. 76.37, or 
provided oral comments at any meeting held on the application or 
compliance plan conducted under Sec. 76.39, 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 15 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 10 days after the filing of the petition. 
Unless the Commission grants the petition for review or otherwise acts 
within 60 days after the publication of the Federal Register notice, 
the Director's initial decision on the certificate application or 
compliance plan becomes effective and final. 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.


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 
and who submitted written comments in response to the Federal Register 
notice on the application or compliance plan under Sec. 76.37 or 
provided oral comments at any meeting held on the application or 
compliance plan conducted under Sec. 76.39, 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 15 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 10 days after filing of the petition. Unless 
the Commission grants the petition for review or otherwise acts within 
60 days after the publication of the Federal Register notice, the 
Director's initial decision on the certificate application or 
compliance plan becomes effective and final. 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.


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 gaseous diffusion plants and other 
activities authorized under the certificate.
    (c) If the Corporation does not submit an annual 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.


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 annually as 
specified in Sec. 76.36 of this part or at a shorter interval as may be 
specified in the certificate.
    (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.


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 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 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 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.


Sec. 76.72  Miscellaneous procedural matters.

    (a) The filing of any petitions for review or any responses thereto 
are governed by the procedural requirements set forth in 10 CFR 
2.701(a) and (c), 2.708, 2.709, 2.710, 2.711, and 2.712. 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 2.772.
    (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 2.780 and 2.781 apply to proceedings under 10 CFR part 
2, subpart G, for imposition of a civil penalty.
    (d) The procedures set forth in 10 CFR 2.205, and in 10 CFR part 2, 
subpart G, will be applied in connection with NRC action to impose a 
civil penalty pursuant to 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.


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 (c) 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 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 approved by the Executive Director for Operations or 
his or her designee.

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 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, 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(d) 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 
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 expected to respond in 
case of an accident 60 days to comment on the emergency plan before 
submitting it to NRC with the initial certification application. 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.


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 Corporation2 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 uncontrolled classified 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.
---------------------------------------------------------------------------


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 Secs. 70.51, 74.11, 74.13, 74.15, 74.17. 74.51, 74.53, 
74.55, 74.57, 74.59, 74.81, and 74.82.
    (b) The requirements for physical security for formula quantities 
of strategic special nuclear material (Category I) are contained in 
Secs. 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 quantity of strategic special nuclear material 
(Category I) are contained in Sec. 73.21. Information designated by the 
U.S. Department of Energy as uncontrolled classified Nuclear 
Information must be protected at a level equivalent to that accorded 
Safeguards Information.
    (d) The Corporation may neither transport Category I material 
offsite nor deliver Category I material to a carrier for transport 
offsite.


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 Secs. 70.51, 70.52, 70.53, 70.54, 70.57, 70.58, 
74.11. 74.13, 74.15, 74.17, 74.81, and 74.82 of this chapter.
    (b) The requirements for physical security for special nuclear 
material of moderate strategic significance (Category II) are contained 
in Secs. 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.


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 Secs. 70.51, 74.11, 74.13, 74.15, 74.17, 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. 70.51(d).
    (b) The requirements for physical security for special nuclear 
material of low strategic significance (Category III) are contained in 
Secs. 73.67, 73.71, and 73.74 of this chapter.


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 Center3 within 1 hour after discovery of:
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    \3\The commercial telephone number for the NRC Operations Center 
is (301) 816-5100 or (301) 951-0550, FAX (301) 816-5151.
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    (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 event4 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.
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    (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;
    (ii) Involves a quantity of material greater than five times the 
lowest annual limit on intake specified in appendix B to Secs. 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 
Secs. 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 U.S. 
Nuclear Regulatory Commission, Document Control Desk, Washington, DC 
20555-0001, with a copy to the NRC Region III Office listed in appendix 
D of part 20 of this chapter and the Resident Inspector. 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.


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 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) Title XI of the Energy Policy Act of 1992, as amended;
    (4) 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 1312(e) of the Atomic Energy Act of 
1954, as amended, and Section 206 of the Energy Reorganization Act of 
1974, as amended; and for a violation of Section 206 of the Energy 
Reorganization Act of 1974, as amended.


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: 
Secs. 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.

PART 95--SECURITY FACILITY APPROVAL AND SAFEGUARDING OF NATIONAL 
SECURITY INFORMATION AND RESTRICTED DATA

    20. The authority citation for part 95 is revised to read as 
follows:

    Authority: Secs. 145, 161, 68 Stat. 942, 948, as amended (42 
U.S.C. 2165, 2201); sec. 201, 88 Stat. 1242, as amended, sec. 1701, 
106 Stat. 2951, 2952, 2953 (42 U.S.C. 5841, 2297f); E.O. 10865, as 
amended, 3 CFR 1959-1963 COMP., p. 398 (50 U.S.C. 401, note); E.O. 
12356, 47 FR 14874, April 6, 1982.

    21. Section 95.1 is revised to read as follows:


Sec. 95.1  Purpose.

    The regulations in this part establish procedures for obtaining 
security facility approval and for safeguarding matter revealing Secret 
and Confidential National Security Information and Restricted Data 
received or developed in conjunction with activities licensed or 
regulated by the Commission. This part does not apply to Top Secret 
information since no such information may be forwarded to licensees or 
others within the scope of an NRC license or certificate.
    22. Section 95.3 is revised to read as follows:


Sec. 95.3  Scope.

    The regulations in this part apply to licensees and others 
regulated by the Commission, including, in accordance with 10 CFR 
76.60, persons required to obtain a certificate of compliance or an 
approved compliance plan under part 76 of this chapter, or their 
contractors, who may require access to National Security Information 
and/or Restricted Data used, processed, stored, reproduced, transmitted 
or handled in connection with a license or application for a license or 
in connection with a certificate, application for a certificate or an 
approved compliance plan under part 76 of this chapter.
    23. Section 95.5 is amended by removing the definitions Access 
authorization, ``L'' access authorization, and ``Q'' access 
authorization, and adding the definitions of NRC access authorization, 
NRC ``L'' access authorization, and NRC ``Q'' access authorization, in 
alphabetical order to read as follows:


Sec. 95.5  Definitions.

* * * * *
    NRC 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, and 
licensees of the NRC, or other person designated by the Executive 
Director for Operations, is eligible for a security clearance for 
access to Restricted Data or National Security Information.
    NRC ``L'' access authorization means an access authorization 
granted by the Commission which is normally based on a national agency 
check and credit investigation (NAC&C) or national agency check, 
inquiries and credit investigation (NACIC) conducted by the Office of 
Personnel Management.
    NRC ``Q'' access authorization means an access authorization 
granted by the Commission based on a full field investigation conducted 
by the Office of Personnel Management, the Federal Bureau of 
Investigation, or other U.S. Government agency which conducts personnel 
security investigations.
* * * * *
    24. In Sec. 95.15, paragraphs (a) and (b) are revised to read as 
follows:


Sec. 95.15  Approval for processing licensees and others for security 
facility approval.

    (a) A licensee or other persons subject to part 95 who have a need 
to use, process, store, reproduce, transmit, or handle matter revealing 
National Security Information and/or Restricted Data at any location in 
connection with Commission related activities shall promptly request an 
NRC security facility approval.
    (b) The request must include the following information: The name of 
the facility; the location of the facility; a security plan outlining 
the facility's proposed security procedures and controls for the 
protection of matter revealing National Security Information and/or 
Restricted Data; a floor plan of the area in which the matter is to be 
used, processed, stored, reproduced, transmitted, or handled.
* * * * *
    25. In Sec. 95.25, the introductory text of paragraph (a) and 
paragraphs (a)(1) and (2) are revised to read as follows:


Sec. 95.25  Protection of National Security Information and Restricted 
Data in storage.

    (a) Protection of secret matter. (1) Secret matter while unattended 
or not in actual use must be stored in locked security containers 
protected by an NRC-approved intrusion alarm or by protective 
personnel.
    (2) Protective personnel must be used where matter revealing 
National Security Information or Restricted Data cannot be adequately 
safeguarded during working hours by employees or during nonworking 
hours by an intrusion alarm system. In either case, protective 
personnel must be capable of responding within 15 minutes.
* * * * *
    26. Section 95.31 is revised to read as follows:


Sec. 95.31  Protective personnel.

    Whenever protective personnel are used to protect National Security 
Information and/or Restricted Data, they shall:
    (a) Possess an ``L'' access authorization (or Department of Defense 
or DOE equivalent) if the licensee or other person possesses matter 
classified as Confidential National Security Information, Confidential 
Restricted Data or Secret National Security Information.
    (b) Possess a ``Q'' access authorization (or Department of Defense 
or DOE equivalent) if the licensee or other person possesses matter 
classified as Secret Restricted Data and the protective personnel 
require access as part of their regular duties.
    27. Section 95.33 is revised to read as follows:


Sec. 95.33  Security education.

    A security education program must be established and maintained by 
the licensee or other persons subject to part 95 which employs 
individuals possessing a U.S. Government personnel security access 
authorization. The program must include consideration and coverage of 
personnel access authorization requirements, the physical security 
features of the facilities, the classified nature of the work, and the 
classification and sensitivity of the matter. In addition, the program 
must include an explanation of the contents of the ``Classified 
Information Nondisclosure Agreement'' (SF 312) and the procedures to be 
followed in ascertaining whether other persons to whom they contemplate 
disclosing classified information have been approved for access to such 
information. The procedures include verification of the individual's 
level of access authorization and determining whether the individual to 
whom the information is to be disclosed has an established need-to-
know. Each security education program must provide for the security 
orientation and continuing security education of employees, and for the 
appropriate security instruction of terminating employees. 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.
    28. Section 95.35 is revised to read as follows:


Sec. 95.35  Access to matter classified as National Security 
Information and Restricted Data.

    (a) Except as the Commission may authorize, no person subject to 
the regulations in this part may receive or may permit any individual 
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.
    (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 individual.
    (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.
    29. In Sec. 95.36, the section heading and paragraphs (a) and (e) 
are revised to read as follows:


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 Division 
of Security that an individual is an authorized representative of the 
International Atomic Energy Agency (IAEA), and that the individual is 
authorized to make visits or inspections in accordance with the US/IAEA 
Safeguards Agreement, a licensee or other person subject to part 95 
will permit the individual (upon presentation of the credentials 
specified in Sec. 75.7 of this chapter and any other credentials 
identified in the disclosure authorization) to have access to matter 
which is National Security Information (NSI) which is relevant to the 
conduct of a visit or inspection. A disclosure authorization under this 
section does not authorize a licensee or other persons subject to part 
95 to provide access to Restricted Data.
* * * * *
    (e) Licensees or other persons subject to part 95, with the prior 
concurrence of the NRC's Division of Security, shall take such measures 
as may be necessary to preclude access to classified matter by 
participants of other international agreements unless specifically 
provided for under the terms of a specific agreement.
    30. In Sec. 95.37, the section heading and paragraph (a) are 
revised to read as follows:


Sec. 95.37  Classification and marking of matter.

    (a) Classification. Licensees or other persons subject to part 95 
shall classify and mark classified matter as National Security 
Information or Restricted Data, as appropriate, in accordance with 
classification guidance provided by NRC as part of the security 
facility approval. If a person or facility generates or possesses 
information which is believed to be classified based on guidance 
provided by NRC or by derivation from classified matter, but which no 
authorized classifier has determined to be classified, it must be 
protected and marked with the appropriate classification markings 
pending review and signature of an NRC authorized classifier. This 
final determination should be made within 30 working days. The licensee 
or other person subject to part 95 shall protect the matter as National 
Security Information or Restricted Data of the highest classification 
at issue while awaiting a final determination.
* * * * *
    31. Section 95.41 is revised to read as follows:


Sec. 95.41  Accountability for Secret matter.

    Each licensee or other person subject to part 95 possessing matter 
classified as Secret National Security Information and/or Restricted 
Data shall establish an accountability procedure and shall maintain 
records to show the disposition of such matter. Records reflecting 
accountability and disposition of classified matter must be maintained 
for 3 years after its disposition.
    32. In Sec. 95.45, paragraph (a) is revised to read as follows:


Sec. 95.45  Changes in classification.

    (a) Matter revealing National Security Information and/or 
Restricted Data must be downgraded or declassified as authorized by NRC 
classification guides or as determined by NRC. Requests for downgrading 
or declassifying any National Security Information and/or Restricted 
Data should be forwarded to the NRC Division of Security, Office of 
Administration, Washington, DC 20555. Requests for downgrading or 
declassifying Restricted Data will be coordinated as appropriate by the 
NRC Division of Security with the Department of Energy.
* * * * *
    33. Section 95.47 is revised to read as follows:


Sec. 95.47  Destruction of matter revealing National Security 
Information and/or Restricted Data.

    Matter revealing National Security Information and/or Restricted 
Data may be destroyed by burning, pulping, or another method that 
ensures complete destruction of the information or material which it 
contains. The method of destruction must preclude recognition or 
reconstruction of the classified matter. Any doubts on methods should 
be referred to the NRC Division of Security. If the matter reveals 
Secret National Security Information and/or Restricted Data, a record 
of the subject or title, document number, if any, originator, its date 
or origination, its series designation and copy number, and the date of 
destruction must be signed by the person destroying the document and 
must be maintained in the office of the custodian at the time of 
destruction. These destruction records must be retained for 3 years 
after destruction.
    34. Section 95.51 is revised to read as follows:


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, the licensee or other persons subject to part 95 
shall, upon due notice of such suspension or revocation, retrieve all 
matter revealing National Security Information and Restricted Data 
possessed by the individual and take such action as necessary to 
preclude that individual from having further access to such matter.
    35. In Sec. 95.57, paragraph (c) is revised to read as follows:


Sec. 95.57  Reports.

* * * * * *
    (c) In addition, an authorized classifier of a licensee or other 
persons subject to part 95 shall complete an NRC Form 790 
(Classification Record) whenever matter revealing National Security 
Information and/or Restricted Data is generated, its classification is 
changed, or it is declassified. Notification of declassification is not 
required for any document or material which has an automatic 
declassification date. Completed NRC Form 790 should be submitted to 
the NRC Division of Security, Washington, DC 20555, on a monthly basis.

Appendix A--[Removed]

    36. Appendix A to Part 95 is removed in its entirety.

    Dated at Rockville, Maryland, this 15th day of September, 1994.

    For the Nuclear Regulatory Commission.
John C. Hoyle,
Acting Secretary of the Commission.
[FR Doc. 94-23329 Filed 9-22-94; 8:45 am]
BILLING CODE 7590-01-P