[Federal Register Volume 80, Number 19 (Thursday, January 29, 2015)]
[Rules and Regulations]
[Pages 4757-4761]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-01693]



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  Federal Register / Vol. 80, No. 19 / Thursday, January 29, 2015 / 
Rules and Regulations  

[[Page 4757]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2014-0058]
RIN-3150-AJ39


List of Approved Spent Fuel Storage Casks: NAC International 
MAGNASTOR[supreg] System; Certificate of Compliance No. 1031, Amendment 
No. 4

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its 
spent fuel storage regulations to add Amendment No. 4 to the 
Certificate of Compliance (CoC) No. 1031 for the NAC International 
MAGNASTOR[supreg] System. Amendment No. 4 changes a limiting condition 
for operation (LCO) in the technical specifications for transportable 
storage canister (TSC) vacuum drying and helium backfill times, and 
corrects a typographical error. The NRC approval of this Amendment 
would not authorize transportation.

DATES: The direct final rule is effective April 14, 2015, unless 
significant adverse comments are received by March 2, 2015. If the 
direct final rule is withdrawn as a result of such comments, timely 
notice of the withdrawal will be published in the Federal Register. 
Comments received after this date will be considered if it is practical 
to do so, but the NRC staff is able to ensure consideration only for 
comments received on or before this date.

ADDRESSES: Please refer to Docket ID NRC-2014-0058 when contacting the 
NRC about the availability of information for this direct final rule. 
You may access publicly-available information related to this direct 
final rule by any of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0058. Address 
questions about NRC dockets to Carol Gallagher, telephone: 301-287-
3422; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly available documents online in the NRC 
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the 
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's 
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number 
for each document referenced in this notice (if that document is 
available in ADAMS) is provided the first time that a document is 
referenced and in Section XIII, Availability of Documents.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O-1F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Robert D. MacDougall, Office of 
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, telephone: 301-415-5175, email: 
[email protected].

SUPPLEMENTARY INFORMATION:

Table of Contents

I. Procedural Background
II. Background
III. Discussion of Changes
IV. Voluntary Consensus Standards
V. Agreement State Compatibility
VI. Plain Writing
VII. Environmental Assessment and Finding of No Significant 
Environmental Impact
VIII. Paperwork Reduction Act Statement
IX. Regulatory Analysis
X. Regulatory Flexibility Certification
XI. Backfitting and Issue Finality
XII. Congressional Review Act
XIII. Availability of Documents

I. Procedural Background

    This direct final rule is limited to the changes contained in 
Amendment No. 4 to CoC No. 1031 and does not include other aspects of 
the MAGNASTOR[supreg] System design. Because the NRC considers this 
action noncontroversial and routine, the NRC is publishing this direct 
final rule concurrently with a proposed rule in the Rules and 
Regulations section of this issue of the Federal Register. Adequate 
protection of public health and safety continues to be ensured. This 
amendment to the rule will become effective on April 14, 2015. If the 
NRC receives significant adverse comments on this direct final rule by 
March 2, 2015, however, it will publish a document that withdraws the 
direct final rule and notifies the public that the NRC will address the 
comments received in response to these proposed revisions in a 
subsequent final rule. Absent significant modifications to the proposed 
revisions that would require republication, the NRC will not initiate a 
second comment period on this action.
    A significant adverse comment is one in which the commenter 
explains why the rule would be inappropriate. This could include 
challenging the rule's underlying premise or approach, or explaining 
why the rule would be ineffective or unacceptable without a change. A 
comment is adverse and significant if:
    (1) The comment opposes the rule and provides a reason sufficient 
to require a substantive response in a notice-and-comment process. For 
example, a substantive response is required when:
    (a) The comment causes the NRC staff to reevaluate its position or 
conduct additional analysis;
    (b) The comment raises an issue serious enough to warrant a 
substantive response to clarify or complete the record; or
    (c) The comment raises a relevant issue that was not previously 
addressed or considered by the NRC staff.
    (2) The comment proposes a change or an addition to the rule, and 
it is apparent that the rule would be ineffective or unacceptable 
without incorporation of the change or addition.
    (3) The comment causes the NRC staff to make a change (other than 
editorial) to the rule, CoC, or technical specifications.
    For detailed instructions on submitting comments, please see the 
companion proposed rule published in the Proposed Rule section of this 
issue of the Federal Register.

[[Page 4758]]

II. Background

    Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as 
amended, requires that ``the Secretary [of the U.S. Department of 
Energy] shall establish a demonstration program, in cooperation with 
the private sector, for the dry storage of spent nuclear fuel at 
civilian nuclear power reactor sites, with the objective of 
establishing one or more technologies that the [U.S. Nuclear 
Regulatory] Commission may, by rule, approve for use at the sites of 
civilian nuclear power reactors without, to the maximum extent 
practicable, the need for additional site-specific approvals by the 
Commission.'' Section 133 of the NWPA states, in part, that ``[the 
Commission] shall, by rule, establish procedures for the licensing of 
any technology approved by the Commission under Section 219(a) [sic: 
218(a)] for use at the site of any civilian nuclear power reactor.''
    To implement this mandate, the Commission approved dry storage of 
spent nuclear fuel in NRC-approved casks under a general license by 
publishing a final rule in part 72 of Title 10 of the Code of Federal 
Regulations (10 CFR), ``Licensing Requirements for the Independent 
Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and 
Reactor-Related Greater Than Class C Waste,'' which added a new subpart 
K within 10 CFR part 72 entitled, ``General License for Storage of 
Spent Fuel at Power Reactor Sites'' (55 FR 29181; July 18, 1990). This 
rule also established a new subpart L within 10 CFR part 72 entitled, 
``Approval of Spent Fuel Storage Casks,'' which contains procedures and 
criteria for obtaining NRC approval of spent fuel storage cask designs. 
The NRC subsequently issued a final rule (73 FR 70587; November 21, 
2008) that approved the MAGNASTOR[supreg] System design and added it to 
the list of NRC-approved cask designs in 10 CFR 72.214, ``List of 
approved spent fuel storage casks,'' as CoC No.1031.

III. Discussion of Changes

    By letter dated June 18, 2013 (ADAMS Accession No. ML13171A031), as 
supplemented September 6, 2013 (ADAMS Accession No. ML13261A278), 
September 19, 2013 (ADAMS Accession No. ML13268A051 proprietary 
information--not for public disclosure), June 13, 2014 (ADAMS Accession 
No. ML14170A063), June 17, 2014 (ADAMS Accession No. ML14170A022), and 
July 17, 2014 (ADAMS Accession No. ML14199A501), NAC International 
(NAC) submitted an application for Amendment No. 4 of CoC No. 1031. The 
amendment makes changes to LCO 3.1.1 in Technical Specification 
Appendix A (ADAMS Accession No. ML14272A479). Specifically, in the 
first table in section 1 of LCO 3.1.1:
     The table title is revised from ``PWR Drying with 8 Hours 
TSC Transfer'' to ``PWR TSC Transfer with Reduced Helium Backfill 
Time;''
     In row 1, 4th column, the cask transfer time is changed 
from 8 to 600 hours;
     In row 2, 3rd column, the helium backfill time is changed 
from 0 to 7 hours; and
     In row 2, 4th column, the cask transfer time is changed 
from 8 to 70.5 hours.
    Amendment No. 4 also corrects a typographical error in two required 
minimum actual areal boron densities in Technical Specification 
Appendix A, Section 4.1.1(a). In addition, Technical Specification 
Appendix B (ADAMS Accession No. ML14272A484), Table B2-5, provides new 
minimum additional decay times required before loading when the spent 
fuel contains nonfuel hardware. The revised technical specifications 
are identified in the preliminary Safety Evaluation Report (SER) (ADAMS 
Accession No. ML14272A487).
    As documented in the preliminary SER, the NRC staff performed a 
detailed safety evaluation of the proposed CoC amendment request. There 
are no significant changes to cask design requirements in the proposed 
CoC amendment. Considering the specific design requirements for each 
accident condition, the design of the cask would prevent loss of 
containment, shielding, and criticality control. If there is no loss of 
containment, shielding, or criticality control, the environmental 
impacts would be insignificant. This amendment does not reflect a 
significant change in design or fabrication of the cask. In addition, 
any resulting occupational exposure or offsite dose rates from the 
implementation of Amendment No. 4 would remain well within the 
applicable limits of 10 CFR part 20, ``Standards for Protection Against 
Radiation.'' Therefore, the proposed CoC changes will not result in any 
radiological or non-radiological environmental impacts that 
significantly differ from the environmental impacts evaluated in the 
environmental assessment supporting the July 18, 1990, final rule (55 
FR 29181) that amended 10 CFR part 72 to provide for the storage of 
spent fuel under a general license in cask designs approved by the NRC. 
There will be no significant change in the types or amounts of any 
effluent released, no significant increase in individual or cumulative 
radiation exposure, and no significant increase in the potential for or 
consequences of radiological accidents from those analyzed in that 
environmental assessment.
    This direct final rule revises the MAGNASTOR[supreg] System listing 
in 10 CFR 72.214 by adding Amendment No. 4 to CoC No. 1031. The 
amendment consists of the changes previously described, as set forth in 
the revised CoC and technical specifications. The revised technical 
specifications are identified in the preliminary SER.
    The amended MAGNASTOR[supreg] System design, when used under the 
conditions specified in the CoC, the technical specifications, and the 
NRC's regulations, will meet the requirements of 10 CFR part 72; 
therefore, adequate protection of public health and safety will 
continue to be ensured. When this direct final rule becomes effective, 
persons who hold a general license under 10 CFR 72.210, ``General 
license issued,'' may load spent nuclear fuel into MAGNASTOR[supreg] 
Storage Systems that meet the criteria of Amendment No. 4 to CoC No. 
1031 under 10 CFR 72.212, ``Conditions of general license issued under 
Sec.  72.212.''

IV. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995 (Pub. 
L. 104-113) requires that Federal agencies use technical standards 
developed or adopted by voluntary consensus standards bodies, unless 
the use of such a standard is inconsistent with applicable law or 
otherwise impractical. In this direct final rule, the NRC will revise 
the MAGNASTOR[supreg] System design listed in 10 CFR 72.214. This 
action does not constitute the establishment of a standard subject to 
Public Law 104-113.

V. Agreement State Compatibility

    Under the ``Policy Statement on Adequacy and Compatibility of 
Agreement State Programs'' approved by the Commission on June 30, 1997, 
and published in the Federal Register on September 3, 1997 (62 FR 
46517), this direct final rule is classified as Compatibility Category 
``NRC.'' Compatibility is not required for Category ``NRC'' 
regulations. The NRC program elements in this category are those that 
relate directly to areas of regulation reserved to the NRC by the 
Atomic Energy Act of 1954, as amended, or the provisions of 10 CFR. 
Although an Agreement State may not adopt program elements reserved to 
the NRC, it may wish to inform its licensees of certain requirements 
via a mechanism

[[Page 4759]]

that is consistent with the particular State's administrative procedure 
laws, but does not confer regulatory authority on the State.

VI. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal 
agencies to write documents in a clear, concise, and well-organized 
manner. The NRC has written this document to be consistent with the 
Plain Writing Act as well as the Presidential Memorandum, ``Plain 
Language in Government Writing,'' published June 10, 1998 (63 FR 
31883).

VII. Environmental Assessment and Finding of No Significant 
Environmental Impact: Availability

A. The Action

    The action is to amend 10 CFR 72.214 to revise the NAC 
International, Inc. MAGNASTOR[supreg] System listing within the ``List 
of Approved Spent Fuel Storage Casks'' to include Amendment No. 4 to 
CoC No. 1031. Under the National Environmental Policy Act of 1969, as 
amended, and the NRC's regulations in subpart A of 10 CFR part 51, 
``Environmental Protection Regulations for Domestic Licensing and 
Related Regulatory Functions,'' the NRC has determined that this rule, 
if adopted, would not be a major Federal action significantly affecting 
the quality of the human environment. An environmental impact statement 
is therefore not required. The NRC has made a finding of no significant 
impact on the basis of this environmental assessment.

B. The Need for the Action

    This direct final rule amends the CoC for the NAC International, 
Inc. MAGNASTOR[supreg] System design within the list of approved spent 
fuel storage casks that power reactor licensees can use to store spent 
fuel at reactor sites under a general license. Specifically, Amendment 
No. 4 changes the LCOs in the technical specifications for canister 
vacuum drying and helium backfill times. Amendment No. 4 also corrects 
a typographical error in two required minimum actual areal boron 
densities in Technical Specification Appendix A, Section 4.1.1(a). In 
addition, Technical Specification Appendix B, Table B2-5, provides new 
minimum additional decay times required before loading when the spent 
fuel contains nonfuel hardware. The revised technical specifications 
are identified in the preliminary SER.

C. Environmental Impacts of the Action

    On July 18,1990 (55 FR 29181), the NRC issued an amendment to 10 
CFR part 72 to provide for the storage of spent fuel under a general 
license in cask designs approved by the NRC. The potential 
environmental impact of using NRC-approved storage casks was initially 
analyzed in the environmental assessment for the 1990 final rule. The 
environmental assessment for this Amendment No. 4 tiers off of the 
environmental assessment for the July 18, 1990, final rule.
    The MAGNASTOR[supreg] System is designed to mitigate the effects of 
design basis accidents that could occur during storage. Design basis 
accidents account for human-induced events and the most severe natural 
phenomena reported for the site and surrounding area. Postulated 
accidents analyzed for an Independent Spent Fuel Storage Installation, 
the type of facility at which a holder of a power reactor operating 
license would store spent fuel in casks in accordance with 10 CFR part 
72, include tornado winds and tornado-generated missiles, a design 
basis earthquake, a design basis flood, an accidental cask drop, 
lightning effects, fires, explosions, and other incidents.
    Considering the specific design requirements for each accident 
condition, the design of the cask would prevent loss of containment, 
shielding, and criticality control. If there is no loss of confinement, 
shielding, or criticality control, the environmental impacts would be 
insignificant.
    This amendment does not reflect a significant change in design or 
fabrication of the cask. There are no significant changes to cask 
design requirements in the proposed CoC amendment. In addition, because 
there are no significant process changes, any resulting occupational 
exposures or offsite dose rates from the implementation of Amendment 
No. 4 would remain well within 10 CFR part 20 radiation safety limits. 
Therefore, the proposed CoC changes will not result in either 
radiological or non-radiological environmental impacts that differ 
significantly from the environmental impacts evaluated in the 
environmental assessment supporting the July 18, 1990, final rule. 
There will be no significant change in the types or amounts of any 
effluent released, no significant increase in individual or cumulative 
radiation exposures, and no significant increase in the potential for 
or consequences of radiological accidents. The staff documented these 
safety findings in the preliminary SER for this amendment.

D. Alternative to the Action

    The alternative to this action is to deny approval of Amendment No. 
4 and end the direct final rule. Consequently, any 10 CFR part 72 
general licensee that seeks to load spent nuclear fuel into 
MAGNASTOR[supreg] System casks in accordance with the changes described 
in proposed Amendment No. 4 would have to request an exemption from the 
requirements of 10 CFR 72.212 and 72.214. Under this alternative, 
interested licensees would have to prepare, and the NRC would have to 
review, a separate exemption request, thereby increasing the 
administrative burden on the NRC and the cost to each licensee. Because 
licensees could still receive approval for use of this cask through a 
different and more burdensome administrative process, environmental 
impacts of the proposed action would be the same as or less than the 
no-action alternative.

E. Alternative Use of Resources

    Approval of Amendment No. 4 to CoC No. 1031 would result in no 
significant irreversible commitments of resources.

F. Agencies and Persons Contacted

    No agencies or persons outside the NRC were contacted in connection 
with the preparation of this environmental assessment.

G. Finding of No Significant Impact

    The environmental impacts of the action have been reviewed under 
the requirements of 10 CFR part 51. Based on the foregoing 
environmental assessment, the NRC concludes that this direct final rule 
entitled, ``List of Approved Spent Fuel Storage Casks: NAC 
International MAGNASTOR[supreg] System; Certificate of Compliance No. 
1031, Amendment No. 4,'' will not have a significant effect on the 
quality of the human environment. The NRC has therefore determined that 
an environmental impact statement for this direct final rule is not 
necessary.

VIII. Paperwork Reduction Act Statement

    This direct final rule does not contain any information collection 
requirements, and is therefore not subject to the Paperwork Reduction 
Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were 
approved by the Office of Management and Budget (OMB), Approval Number 
3150-0132.

Public Protection Notification

    The NRC may not conduct or sponsor, and a person is not required to 
respond to, a request for information or an information collection 
requirement, unless the requesting document displays a currently valid 
OMB control number.

[[Page 4760]]

IX. Regulatory Analysis

    On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10 
CFR part 72 to provide for the storage of spent nuclear fuel under a 
general license in casks with designs approved by the NRC. Any nuclear 
power reactor licensee can use casks with NRC-approved designs to store 
spent nuclear fuel if the licensee notifies the NRC in advance, the 
spent fuel is stored under the conditions specified in the cask's CoC, 
and the conditions of the general license are met. A list of NRC-
approved cask designs is codified in 10 CFR 72.214. The NRC issued a 
final rule (73 FR 70687; November 21, 2008) that approved the 
MAGNASTOR[supreg] System design and added it to the list of NRC-
approved cask designs in 10 CFR 72.214 ``List of approved spent fuel 
storage casks,'' as CoC No. 1031.
    On June 18, 2013, and as supplemented on September 6, 2013, June 
13, 2014, June 17, 2014, and July 17, 2014, NAC International, Inc. 
submitted an application to amend the MAGNASTOR[supreg] Cask System as 
described in Section III, ``Discussion of Changes,'' of this document.
    The alternative to this action is to withhold approval of Amendment 
No. 4 and to require any 10 CFR part 72 general licensee seeking to 
load spent nuclear fuel into the MAGNASTOR[supreg] System cask under 
the changes described in Amendment No. 4 to request an exemption from 
the requirements of 10 CFR 72.212 and 72.214. Under this alternative, 
each interested 10 CFR part 72 licensee would have to prepare, and the 
NRC would have to review, a separate exemption request, thereby 
increasing the administrative burden on the NRC and the costs to each 
interested licensee.
    Issuance of this direct final rule is consistent with previous NRC 
actions. Further, as documented in the preliminary SER and the 
environmental assessment, the direct final rule will ensure protection 
of public health and safety, and have no significant impact on the 
environment. This direct final rule has no significant identifiable 
impact or benefit on other Government agencies. Based on this 
regulatory analysis, the NRC concludes that the requirements of the 
direct final rule are commensurate with the NRC's responsibilities for 
public health and safety and the common defense and security. No other 
available alternative is believed to be as satisfactory, and therefore, 
this action is recommended.

X. Regulatory Flexibility Certification

    Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the 
NRC certifies that this direct final rule will not, if issued, have a 
significant economic impact on a substantial number of small entities. 
This direct final rule affects only nuclear power plant licensees and 
NAC International, Inc. These entities do not fall within the 
definition of small entities set forth in the Regulatory Flexibility 
Act or the size standards established by the NRC (10 CFR 2.810).

XI. Backfitting and Issue Finality

    The NRC has determined that the backfit rule (10 CFR 72.62) does 
not apply to this direct final rule. Therefore, a backfit analysis is 
not required. This direct final rule revises the CoC No. 1031 for the 
NAC International MAGNASTOR[supreg] System, as currently listed in 10 
CFR 72.214, ``List of Approved Spent Fuel Storage Casks.'' The revision 
consists of Amendment No. 4, which changes the title and specified 
numerical values of LCO 3.1.1, Section 1, first table entitled ``PWR 
Drying with 8 Hours TSC Transfer.'' Amendment No. 4 also corrects a 
typographical error in two required minimum actual areal boron 
densities in Technical Specification Appendix A, Section 4.1.1(a). In 
addition, Technical Specification Appendix B, Table B2-5, provides new 
minimum additional decay times required before loading when the spent 
fuel contains nonfuel hardware. The revised technical specifications 
are identified in the preliminary SER.
    Amendment No. 4 to CoC No. 1031 for the MAGNASTOR[supreg] System 
was initiated by NAC International and was not submitted in response to 
new NRC requirements, or an NRC request for amendment. Amendment No. 4 
applies only to new casks fabricated and used under Amendment No. 4. 
These changes do not affect existing users of the NAC International 
MAGNASTOR[supreg] System, and the current Amendment No. 3 continues to 
be effective for existing users. While current CoC users may comply 
with the new requirements in Amendment No. 4, this would be a voluntary 
decision on their part. For these reasons, Amendment No. 4 to CoC No. 
1031 does not constitute backfitting under 10 CFR 72.62 or 10 CFR 
50.109(a)(1), or otherwise represent an inconsistency with the issue 
finality provisions applicable to combined licenses in 10 CFR part 52. 
Accordingly, no backfit analysis or additional documentation addressing 
the issue finality criteria in 10 CFR part 52 has been prepared by the 
staff.

XII. Congressional Review Act

    The Office of Management and Budget has not found this to be a 
major rule as defined in the Congressional Review Act.

XIII. Availability of Documents

    The documents referenced in this direct final rule are available in 
the NRC's Agencywide Documents Access and Management System (ADAMS) 
using the Main Library (ML) accession numbers for the documents listed 
in the table below:

                                 Table 1
------------------------------------------------------------------------
             Document title                     ADAMS Accession No.
------------------------------------------------------------------------
Proposed CoC (for Certificate of          ML14272A472
 Compliance #1031).
Technical Specifications Appendix A.....  ML14272A479
Technical Specifications Appendix B.....  ML14272A484
Preliminary Safety Evaluation Report      ML14272A487
 (SER).
``Submission of a Request to Amend the    ML13171A031
 NRC Certificate of Compliance No. 1031
 for the NAC International MAGNASTOR
 Cask System,'' June 18, 2013.
``Submission of NAC's Response to the     ML13261A278
 U.S. Nuclear Regulatory Commission's
 Request for Supplemental Information
 for NAC's Request to Amend the
 Certificate of Compliance No. 1031 for
 the NAC International MAGNASTOR Cask
 System,'' September 6, 2013.
``Final Safety Analysis Report Amendment  ML13268A051
 4 Application Supplement, Rev. 13C,''
 September 19, 2013. (Proprietary
 information--not for public
 disclosure)..
``Submission of a Supplement to NAC's     ML14170A063
 Request to Amend the U.S. Nuclear
 Regulatory Commission Certificate of
 Compliance No. 1031 for the NAC
 International MAGNASTOR Cask System,''
 June 13, 2014.

[[Page 4761]]

 
``Submission of a Supplement to NAC's     ML14170A022
 Request to Amend the U.S. Nuclear
 Regulatory Commission Certificate of
 Compliance No. 1031 for the NAC
 International MAGNASTOR Cask System,''
 June 17, 2014.
``Submission of a Supplement to NAC's     ML14199A501
 Request to Amend the U.S. Nuclear
 Regulatory Commission Certificate of
 Compliance No. 1031 for the NAC
 International MAGNASTOR Cask System,''
 July 17, 2014.
------------------------------------------------------------------------

List of Subjects in 10 CFR Part 72

    Administrative practice and procedure, Criminal penalties, Manpower 
training programs, Nuclear materials, Occupational safety and health, 
Penalties, Radiation protection, Reporting and recordkeeping 
requirements, Security measures, Spent fuel, Whistleblowing.

    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; the Nuclear Waste Policy Act of 1982, as 
amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following 
amendments to 10 CFR part 72.

PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF 
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE AND REACTOR-
RELATED GREATER THAN CLASS C WASTE

0
1. The authority citation for part 72 continues to read as follows:

    Authority:  Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69, 
81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 
2234, 2236, 2237, 2239, 2273, 2282, 2021); Energy Reorganization Act 
secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); 
National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear 
Waste Policy Act secs. 131, 132, 133, 135, 137, 141, 148 (42 U.S.C. 
10151, 10152, 10153, 10155, 10157, 10161, 10168); Government 
Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy 
Policy Act of 2005, Pub. L. 109-58, 119 Stat. 549 (2005).
    Section 72.44(g) also issued under Nuclear Waste Policy Act 
secs. 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)). 
Section 72.46 also issued under Atomic Energy Act sec. 189 (42 
U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154). 
Section 72.96(d) also issued under Nuclear Waste Policy Act sec. 
145(g) (42 U.S.C. 10165(g)). Subpart J also issued under Nuclear 
Waste Policy Act secs. 117(a), 141(h) (42 U.S.C. 10137(a), 
10161(h)). Subpart K also issued under Nuclear Waste Policy Act sec. 
218(a) (42 U.S.C. 10198).


0
2. In Sec.  72.214, Certificate of Compliance No. 1031 is revised to 
read as follows:


Sec.  72.214  List of approved spent fuel storage casks.

* * * * *
    Certificate Number: 1031.
    Initial Certificate Effective Date: February 4, 2009.
    Amendment Number 1 Effective Date: August 30, 2010.
    Amendment Number 2 Effective Date: January 30, 2012.
    Amendment Number 3 Effective date: July 25, 2013.
    Amendment Number 4 Effective Date: April 14, 2015.
    SAR Submitted by: NAC International, Inc.
    SAR Title: Final Safety Analysis Report for the MAGNASTOR[supreg] 
System.
    Docket Number: 72-1031.
    Certificate Expiration Date: February 4, 2029. Model Number: 
MAGNASTOR[supreg].

    Dated at Rockville, Maryland, this 15th day of January 2015.

    For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2015-01693 Filed 1-28-15; 8:45 am]
BILLING CODE 7590-01-P