[Federal Register Volume 89, Number 172 (Thursday, September 5, 2024)]
[Rules and Regulations]
[Pages 72299-72304]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-19894]
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Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
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Federal Register / Vol. 89, No. 172 / Thursday, September 5, 2024 /
Rules and Regulations
[[Page 72299]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2024-0120]
RIN 3150-AL19
List of Approved Spent Fuel Storage Casks: NAC International,
Inc. MAGNASTOR[supreg] Storage System, Certificate of Compliance No.
1031, Amendment No. 13
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the NAC International, Inc.
MAGNASTOR[supreg] Storage System listing within the ``List of approved
spent fuel storage casks'' to include Amendment No. 13 to Certificate
of Compliance No. 1031. Amendment No. 13 revises the certificate of
compliance to add a new type of radioactive contents to be stored
inside the MAGNASTOR[supreg] transportable storage canister, add a new
design configuration for the canister to accommodate the fuel bearing
material and new canister components, and use an alternate compressive
strength for concrete cask no. 6 of 6,000 psi.
DATES: This direct final rule is effective November 19, 2024, unless
significant adverse comments are received by October 7, 2024. If this
direct final rule is withdrawn as a result of such comments, timely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 is able to ensure consideration only for comments
received on or before this date. Comments received on this direct final
rule will also be considered to be comments on a companion proposed
rule published in the Proposed Rules section of this issue of the
Federal Register.
ADDRESSES: Submit your comments, identified by Docket ID NRC-2024-0120,
at https://www.regulations.gov. If your material cannot be submitted
using https://www.regulations.gov, call or email the individuals listed
in the FOR FURTHER INFORMATION CONTACT section of this document for
alternate instructions.
You can read a plain language description of this direct final rule
at https://www.regulations.gov/docket/NRC-2024-0120. For additional
direction on obtaining information and submitting comments, see
``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY
INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: George Tartal, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-0016, email:
[email protected] and Nishka Devaser, telephone: 301-415-5196,
email: [email protected]. Both are staff of the U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
Table of Contents:
I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
III. Background
IV. Discussion of Changes
V. Voluntary Consensus Standards
VI. Agreement State Compatibility
VII. Plain Writing
VIII. Environmental Assessment and Finding of No Significant Impact
IX. Paperwork Reduction Act Statement
X. Regulatory Flexibility Certification
XI. Regulatory Analysis
XII. Backfitting and Issue Finality
XIII. Congressional Review Act
XIV. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2024-0120 when contacting the NRC
about the availability of information for this action. You may obtain
publicly available information related to this action by any of the
following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0120. Address
questions about NRC dockets to Helen Chang, telephone: 301-415-3228,
email: [email protected]. For technical questions contact the
individuals listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, 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]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time, Monday through Friday, except Federal
holidays.
B. Submitting Comments
The NRC encourages electronic comment submission through the
Federal rulemaking website (https://www.regulations.gov). Please
include Docket ID NRC-2024-0120 in your comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at
https://www.regulations.gov as well as enter the comment submissions
into ADAMS. The NRC does not routinely edit comment submissions to
remove identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
[[Page 72300]]
II. Rulemaking Procedure
This rule is limited to the changes contained in Amendment No. 13
to Certificate of Compliance No. 1031 and does not include other
aspects of the NAC International, Inc. MAGNASTOR[supreg] Storage System
design. The NRC is using the ``direct final rule procedure'' to issue
this amendment because it represents a limited and routine change to an
existing certificate of compliance that is expected to be non-
controversial. Adequate protection of public health and safety
continues to be reasonably assured. The amendment to the rule will
become effective on November 19, 2024. However, if the NRC receives any
significant adverse comment on this direct final rule by October 7,
2024, then the NRC will publish a document that withdraws this action
and will subsequently address the comments received in a final rule as
a response to the companion proposed rule published in the Proposed
Rules section of this issue of the Federal Register or as otherwise
appropriate. In general, absent significant modifications to the
proposed revisions requiring republication, the NRC will not initiate a
second comment period on this action.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or 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 to reevaluate (or reconsider) 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.
(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 to make a change (other than
editorial) to the rule, certificate of compliance, or technical
specifications.
III. Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended,
requires that ``[t]he Secretary [of the 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 [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 Nuclear
Waste Policy Act states, in part, that ``[t]he 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 that added a new subpart K in part 72 of title
10 of the Code of Federal Regulations (10 CFR) 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 in 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 on
November 21, 2008 (73 FR 70587), that approved the NAC International,
Inc. MAGNASTOR[supreg] Storage System design and added it to the list
of NRC-approved cask designs in Sec. 72.214 as Certificate of
Compliance No. 1031.
IV. Discussion of Changes
On July 13, 2022, NAC International, Inc. submitted a request to
the NRC to amend Certificate of Compliance No. 1031. NAC International,
Inc. and supplemented its request on the following dates: October 13,
2022, November 30, 2022, June 27, 2023, August 17, 2023, and September
15, 2023 (ADAMS Accession Nos. ML22287A038, ML22321A269, ML23178A225,
ML23229A481, and ML23258A233, respectively).
Amendment No. 13 revises the certificate of compliance to add a new
type of radioactive contents (fuel bearing material (FBM) from the
damaged Three Mile Island Unit 2 reactor) to be stored inside the
MAGNASTOR[supreg] transportable storage canister (TSC) and to include
concrete with a compressive strength of 6,000 psi for concrete cask
number 6 as an alternate to the previously approved 8,000 psi
compressive strength. Additionally, Amendment No. 13 adds a new design
configuration of the TSC (the FBM TSC) to accommodate the FBM and the
TSC internal components. The new configuration includes: (1) reducing
closure lid assembly thickness of the TSC and removing the hydrostatic
pressure test; (2) adding a new waste basket liner (WBL) (based on the
Greater-Than-Class C Waste WBL) made from stainless steel in lieu of
the fuel basket for the storage of FBM inside the FBM TSC; (3) adding a
new debris material container to be used as an operational device to
handle and house finer debris; and (4) adding a new segmented tube
assembly to define cells for loading.
As documented in the preliminary safety evaluation report, the NRC
performed a safety evaluation of the proposed certificate of compliance
amendment request. The NRC determined that this amendment does not
reflect a significant change in design or fabrication of the cask.
Specifically, the NRC determined that the design of the cask would
continue to maintain confinement, shielding, and criticality control in
the event of each evaluated accident condition. In addition, any
resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 13 would remain well within the limits
specified by 10 CFR part 20, ``Standards for Protection Against
Radiation.'' Therefore, the NRC found there will be no significant
change in the types or amounts of any effluent released, no significant
increase in the individual or cumulative radiation exposure, and no
significant increase in the potential for or consequences from
radiological accidents.
The NRC staff determined that the amended NAC International, Inc.
MAGNASTOR[supreg] Storage cask design, when used under the conditions
specified in the certificate of compliance, 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 reasonably assured. When this direct final
rule becomes effective, persons who hold a general license under Sec.
72.210 may, consistent with the license conditions under Sec. 72.212,
load spent nuclear fuel, in the form of FBM, into NAC International,
Inc. MAGNASTOR[supreg] Storage System cask design that meet the
criteria of Amendment No. 13 to Certificate of Compliance No. 1031.
The NRC is clarifying that Amendment 13 to Certificate of
Compliance No. 1031 does not involve
[[Page 72301]]
storage of spent fuel assemblies as is the case for most certificate of
compliance applications. Rather, this amendment involves storage of
FBM, which includes components associated with deposited fuel and
fission products from the damaged Three Mile Island Unit 2 reactor,
inside the transportable storage canister. This amendment also involves
adding a new design configuration of the transportable storage canister
to accommodate the FBM and the new transportable storage canister
internal components. A waste basket liner is proposed to replace the
fuel basket structure for storage of FBM. Because this configuration
involves only deposited fuel and fission products rather than entire
spent fuel assemblies, the storage of the materials is of lower risk
significance than that of the storage of spent fuel assemblies. The
NRC's safety evaluation considered the design changes proposed for this
amendment and concluded that they meet the requirements of 10 CFR part
72.
V. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal agencies use technical standards that
are 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 revises the
NAC International, Inc. MAGNASTOR[supreg] Storage Cask System design
listed in Sec. 72.214, ``List of approved spent fuel storage casks.''
This action does not constitute the establishment of a standard that
contains generally applicable requirements.
VI. Agreement State Compatibility
Under the ``Agreement State Program Policy Statement'' approved by
the Commission on October 2, 2017, and published in the Federal
Register on October 18, 2017 (82 FR 48535), this rule is classified as
Compatibility Category NRC--Areas of Exclusive NRC Regulatory
Authority. 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
chapter I. Therefore, compatibility is not required for program
elements in this category.
VII. 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
31885).
VIII. Environmental Assessment and Finding of No Significant Impact
Under the National Environmental Policy Act of 1969, as amended,
and the NRC's regulations in 10 CFR part 51, ``Environmental Protection
Regulations for Domestic Licensing and Related Regulatory Functions,''
the NRC has determined that this direct final rule, if adopted, would
not be a major Federal action significantly affecting the quality of
the human environment and, therefore, an environmental impact statement
is not required. The NRC has made a finding of no significant impact on
the basis of this environmental assessment.
A. The Action
The action is to amend Sec. 72.214 to revise the NAC
International, Inc. MAGNASTOR[supreg] Storage System listing within the
``List of approved spent fuel storage casks'' to include Amendment No.
13 to Certificate of Compliance No. 1031.
B. The Need for the Action
This direct final rule amends the certificate of compliance for the
NAC International, Inc. MAGNASTOR[supreg] Storage System design within
the list of approved spent fuel storage casks to allow power reactor
licensees to store spent fuel, in the form of FBM, at reactor sites in
casks with the approved modifications under a general license.
Specifically, Amendment No. 13 revises the certificate of compliance to
add a new type of radioactive contents (FBM from the damaged Three Mile
Island Unit 2 reactor) to be stored inside the MAGNASTOR[supreg]
transportable storage canister (TSC) and to include concrete with a
compressive strength of 6,000 psi for concrete cask number 6 as an
alternate to the previously approved 8,000 psi compressive strength.
Additionally, Amendment No. 13 adds a new design configuration of the
TSC (the FBM TSC) to accommodate the FBM and the TSC internal
components. The new configuration includes: (1) reducing closure lid
assembly thickness of the TSC and removing the hydrostatic pressure
test; (2) adding a new waste basket liner (WBL) (based on the Greater-
Than-Class C Waste WBL) made from stainless steel in lieu of the fuel
basket, for the storage of FBM inside the FBM TSC; (3) adding a new
debris material container to be used as an operational device to handle
and house finer debris; and (4) adding a new segmented tube assembly to
define cells for loading.
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 analyzed
in the environmental assessment for the 1990 final rule. The
environmental assessment for Amendment No. 13 tiers off of the
environmental assessment for the July 18, 1990, final rule. Tiering on
past environmental assessments is a standard process under the National
Environmental Policy Act of 1969, as amended.
The NAC International, Inc. MAGNASTOR[supreg] Storage 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, can include tornado winds and tornado-
generated missiles, a design basis earthquake, a design basis flood, an
accidental cask drop, lightning effects, fire, explosions, and other
incidents.
This amendment does not reflect a significant change in design or
fabrication of the cask. Because there are no significant design or
process changes, any resulting occupational exposure or offsite dose
rates from the implementation of Amendment No. 13 would remain well
within the 10 CFR part 20 limits. The NRC has also determined that the
design of the cask as modified by this rule would maintain confinement,
shielding, and criticality control in the event of an accident.
Therefore, the proposed 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. There will be no significant
change in the types or significant revisions in the amounts of any
effluent released, no significant increase in the individual or
cumulative radiation exposures, and no significant increase in the
potential for, or consequences from, radiological accidents. The NRC
documented its
[[Page 72302]]
safety findings in the preliminary safety evaluation report.
D. Alternative to the Action
The alternative to this action is to deny approval of Amendment No.
13 and not issue the direct final rule. Consequently, any 10 CFR part
72 general licensee that seeks to load spent nuclear fuel, in the form
of FBM, into NAC International, Inc. MAGNASTOR[supreg] Storage System
in accordance with the changes described in proposed Amendment No. 13
would have to request an exemption from the requirements of Sec. Sec.
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 upon the NRC and
the costs to each licensee. The environmental impacts would be the same
as the proposed action.
E. Alternative Use of Resources
Approval of Amendment No. 13 to Certificate of Compliance No. 1031
would result in no irreversible commitment 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 in 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.'' Based on the foregoing environmental
assessment, the NRC concludes that this direct final rule, ``List of
Approved Spent Fuel Storage Casks: NAC International, Inc.
MAGNASTOR[supreg] Storage System Certificate of Compliance No. 1031,
Amendment No. 13'' will not have a significant effect on the human
environment. Therefore, the NRC has determined that an environmental
impact statement is not necessary for this direct final rule.
IX. Paperwork Reduction Act Statement
This direct final rule does not contain any new or amended
collections of information subject to the Paperwork Reduction Act of
1995 (44 U.S.C. 3501 et seq.). Existing collections of information were
approved by the Office of Management and Budget, 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
Office of Management and Budget control number.
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 scope of
the definition of small entities set forth in the Regulatory
Flexibility Act or the size standards established by the NRC (Sec.
2.810).
XI. 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 cask designs approved by the NRC. Any nuclear power
reactor licensee can use NRC-approved cask designs to store spent
nuclear fuel if (1) it notifies the NRC in advance; (2) the spent fuel
is stored under the conditions specified in the cask's certificate of
compliance; and (3) the conditions of the general license are met. A
list of NRC-approved cask designs is contained in Sec. 72.214. On
November 21, 2008 (73 FR 70587), the NRC issued an amendment to 10 CFR
part 72 that approved the NAC International, Inc. MAGNASTOR[supreg]
Storage System design by adding it to the list of NRC-approved cask
designs in Sec. 72.214.
On July 13, 2022, NAC International, Inc. submitted a request to
amend Certificate of Compliance No. 1031. NAC International, Inc. and
supplemented its request on the following dates: October 13, 2022,
November 30, 2022, June 27, 2023, August 17, 2023, and September 15,
2023 (ADAMS Accession Nos. ML22287A038, ML22321A269, ML23178A225,
ML23229A481, and ML23258A233, respectively) as described in Section IV
``Discussion of Changes,'' of this document.
The alternative to this action is to withhold approval of Amendment
No. 13 and to require any 10 CFR part 72 general licensee seeking to
load spent nuclear fuel, including FBM, into the NAC International,
Inc. MAGNASTOR[supreg] Storage System under the changes described in
Amendment No. 13 to request an exemption from the requirements of
Sec. Sec. 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 upon the NRC and the costs to each licensee.
Approval of this direct final rule is consistent with previous NRC
actions. Further, as documented in the preliminary safety evaluation
report and environmental assessment, this direct final rule will have
no adverse effect on public health and safety or 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 this 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; therefore, this action
is recommended.
XII. Backfitting and Issue Finality
The NRC has determined that the backfit rule (Sec. 72.62) does not
apply to this direct final rule. Therefore, a backfit analysis is not
required. This direct final rule revises Certificate of Compliance No.
1031 for the NAC International, Inc. MAGNASTOR[supreg] Storage System,
as currently listed in Sec. 72.214. The revision consists of the
changes in Amendment No. 13 previously described, as set forth in the
revised certificate of compliance and technical specifications.
Amendment No. 13 to Certificate of Compliance No. 1031 for the NAC
International, Inc. MAGNASTOR[supreg] Storage System was initiated by
NAC International, Inc. and was not submitted in response to new NRC
requirements, or an NRC request for amendment. Amendment No. 13 applies
only to new casks fabricated and used under Amendment No. 13. These
changes do not affect existing users of the NAC International, Inc.
MAGNASTOR[supreg] Storage System, and the current Amendment No. 12
continues to be effective for existing users. While current users of
this storage system may comply with the new requirements in Amendment
No. 13, this would be a voluntary decision on the part of current
users.
For these reasons, Amendment No. 13 to Certificate of Compliance
No. 1031 does not constitute backfitting under Sec. 72.62 or Sec.
50.109(a)(1), or otherwise
[[Page 72303]]
represent an inconsistency with the issue finality provisions
applicable to combined licenses in 10 CFR part 52. Accordingly, the NRC
has not prepared a backfit analysis for this rulemaking.
XIII. Congressional Review Act
This direct final rule is not a rule as defined in the
Congressional Review Act.
XIV. Availability of Documents
The documents identified in the following table are available to
interested persons as indicated.
----------------------------------------------------------------------------------------------------------------
ADAMS accession No./web link/Federal Register
Document citation
----------------------------------------------------------------------------------------------------------------
Proposed Renewed Certificate of Compliance and Proposed Technical Specifications
----------------------------------------------------------------------------------------------------------------
Memorandum to REFS for Issuance of Amendment No. 13........ ML24075A113 (Package).
Preliminary Safety Evaluation Report for CoC 1031 Amendment ML24075A118.
13.
Proposed Certificate of Compliance No. 1031 Amendment 13... ML24075A115.
Proposed CoC 1031 Amendment 13 TS Appendix A............... ML24075A116.
Proposed CoC 1031 Amendment 13 TS Appendix B............... ML24075A117.
Enclosure 2--Safety Evaluation Report, NAC International, ML090350589.
Inc.
----------------------------------------------------------------------------------------------------------------
NAC International, Inc. MAGNASTOR[supreg] Storage System Amendment No. 13 Request Documents
----------------------------------------------------------------------------------------------------------------
NAC, Submittal of an Amendment Request for the NAC ML22194A908.
International MAGNASTOR[supreg] Cask System, Amendment No.
13.
Supplement to the Submission of an Amendment Request for ML22287A038.
the NAC International MAGNASTOR[supreg] Cask System,
Amendment No. 13.
Enclosure 1--List of Changes for MAGNASTOR FSAR Amendment ML22321A269.
13, Supplement 02, Revision 22D.
Submittal of Supplemental Responses to the Nuclear ML23178A480 (Package).
Regulatory Commission's (NRC) Request for Additional
Information for the NAC International MAGNASTOR[supreg]
Cask System, Amendment No. 13.
Submission of Replacement Pages for Supplemental Responses ML23258A233.
to the Nuclear Regulatory Commission's (NRC) Request for
Additional Information for the NAC International
MAGNASTOR[supreg] Cask System, Amendment No. 13.
Submission of Responses to the Nuclear Regulatory ML23178A224 (Package).
Commission's (NRC) Request for Additional Information for
the NAC International MAGNASTOR[supreg] Cask System,
Amendment No. 13.
Three Mile Island Nuclear Station, Unit 2 (TMI-2), License ML22276A024.
Amendment Request--Decommissioning Technical
Specifications, Response to Request for Additional
Information.
Forwards amend 48 to license DPR-73 & safety evaluation. ML20059D154.
Amend extensively modifies App A & B TSs consistent w/
plans for post defueling monitoring storage of facility.
----------------------------------------------------------------------------------------------------------------
Other Documents
----------------------------------------------------------------------------------------------------------------
NUREG-2215 ``Standard Review Plan for Spent Fuel Dry ML20121A190.
Storage Systems and Facilities'' Final Report.
Issuance of Amendment No. 12............................... ML23328A396 (Package).
----------------------------------------------------------------------------------------------------------------
The NRC may post materials related to this document, including
public comments, on the Federal rulemaking website at https://www.regulations.gov under Docket ID NRC-2024-0120. In addition, the
Federal rulemaking website allows members of the public to receive
alerts when changes or additions occur in a docket folder. To
subscribe: (1) navigate to the docket folder (NRC-2024-0120); (2) click
the ``Subscribe'' link; and (3) enter an email address and click on the
``Subscribe'' link.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Indians,
Intergovernmental relations, Nuclear energy, 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 of 1954, secs. 51, 53, 57, 62, 63,
65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42
U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2210e,
2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C.
5841, 5842, 5846, 5851); National Environmental Policy Act of 1969
(42 U.S.C. 4332); Nuclear Waste Policy Act of 1982, secs. 117(a),
132, 133, 134, 135, 137, 141, 145(g), 148, 218(a) (42 U.S.C.
10137(a), 10152, 10153, 10154, 10155, 10157, 10161, 10165(g), 10168,
10198(a)); 44 U.S.C. 3504 note.
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, superseded by
Initial Certificate, Revision 1, on February 1, 2016, superseded by
Initial Certificate, Revision 2 on October 16, 2023.
Amendment Number 1 Effective Date: August 30, 2010, superseded by
Amendment Number 1, Revision 1, on February 1, 2016, superseded by
Amendment Number 1, Revision 2, on October 16, 2023.
Amendment Number 2 Effective Date: January 30, 2012, superseded by
Amendment Number 2, Revision 1, on February 1, 2016, superseded by
Amendment Number 2, Revision 2 on October 16, 2023.
Amendment Number 3 Effective Date: July 25, 2013, superseded by
Amendment Number 3, Revision 1, on February 1, 2016, superseded by
[[Page 72304]]
Amendment Number 3, Revision 2 on October 16, 2023.
Amendment Number 4 Effective Date: April 14, 2015, superseded by
Amendment Number 4, Revision 1, on October 16, 2023.
Amendment Number 5 Effective Date: June 29, 2015, superseded by
Amendment Number 5, Revision 1, on October 16, 2023.
Amendment Number 6 Effective Date: December 21, 2016, superseded by
Amendment Number 6, Revision 1, on October 16, 2023.
Amendment Number 7 Effective Date: August 21, 2017, as corrected
(ADAMS Accession No. ML19045A346), superseded by Amendment Number 7,
Revision 1, on October 16, 2023.
Amendment Number 8, Effective Date: March 24, 2020, superseded by
Amendment Number 8, Revision 1, on October 16, 2023.
Amendment Number 9, Effective Date: December 7, 2020, superseded by
Amendment Number 9, Revision 1, on October 16, 2023.
Amendment Number 10, Effective Date: January 18, 2023.
Amendment Number 11, Effective Date: October 16, 2023.
Amendment Number 12, Effective Date: October 16, 2023.
Amendment Number 13 Effective Date: November 19, 2024.
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: August 21, 2024.
For the Nuclear Regulatory Commission.
Mirela Gavrilas,
Executive Director for Operations.
[FR Doc. 2024-19894 Filed 9-4-24; 8:45 am]
BILLING CODE 7590-01-P