[Federal Register Volume 90, Number 22 (Tuesday, February 4, 2025)]
[Rules and Regulations]
[Pages 8861-8865]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2025-02208]
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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. 90, No. 22 / Tuesday, February 4, 2025 /
Rules and Regulations
[[Page 8861]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2024-0182]
RIN 3150-AL22
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM UMAX Canister Storage System, Certificate of Compliance No.
1040, Revision 1 to Amendment Nos. 0 Through 2
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International HI-
STORM UMAX Canister Storage System listing within the ``List of
approved spent fuel storage casks'' to include Revision 1 to Amendment
Nos. 0 through 2 to Certificate of Compliance (CoC) No. 1040. Revision
1 to Amendment Nos. 0 through 2 updates the CoC appendix A technical
specifications for radiation protection and the associated bases
information to clearly articulate the basis for the dose rate limits
for the closure lids, modify the dose rate limit values and the
description of the location of the dose rate measurements, and make
other editorial changes.
DATES: This direct final rule is effective April 21, 2025, unless
significant adverse comments are received by March 6, 2025. 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direct final rule is withdrawn as a result of such comments, timely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-2024-0182,
at https://www.regulations.gov. If your material cannot be submitted
using https://www.regulations.gov, call or email the individual 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-2024-0182. 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
Materials Safety and Safeguards, telephone: 301-415-0016, email:
[email protected] and Kristina Banovac, Office of Nuclear Materials
Safety and Safeguards, telephone: 301-415-7116, 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-2024-0182 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-2024-0182. Address
questions about NRC dockets to Helen Chang, telephone: 301-415-3228,
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 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-2024-0182 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
[[Page 8862]]
before making the comment submissions available to the public or
entering the comment into ADAMS.
II. Rulemaking Procedure
This rule is limited to the changes contained in Revision 1 to
Amendment Nos. 0 through 2 to CoC No. 1040 and does not include other
aspects of the Holtec International HI-STORM UMAX Canister Storage
System design. The NRC is using the ``direct final rule procedure'' to
issue this revision because it represents a limited and routine change
to an existing CoC 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 April 21,
2025. However, if the NRC receives any significant adverse comment on
this direct final rule by March 6, 2025, 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, CoC, 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
March 6, 2015 (80 FR 12073), as corrected (80 FR 15679; March 25,
2015), that approved the Holtec International HI-STORM UMAX Canister
Storage System design and added it to the list of NRC-approved cask
designs in Sec. 72.214 as CoC No. 1040.
IV. Discussion of Changes
On May 5, 2023, Holtec International (Holtec) submitted a request
to the NRC to revise CoC No. 1040 Amendment Nos. 0 through 2. Holtec
supplemented its request on the following dates: January 31, 2024,
March 4, 2024, and June 26, 2024. Revision 1 to Amendment Nos. 0
through 2 updates CoC No. 1040 appendix A technical specifications for
radiation protection and the associated bases information to clearly
articulate the basis for the dose rate limits for the closure lids, and
to modify the dose rate limit values and the description of the
location of the dose rate measurements. This revision also makes other
editorial changes. The changes to the aforementioned documents are
identified with revision bars in the margin of each document.
As documented in the preliminary safety evaluation report, the NRC
performed a safety evaluation of the proposed CoC revision request. The
NRC determined that this revision 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 Revision 1 to Amendment
Nos. 0 through 2 would remain well within the limits specified by 10
CFR part 20, ``Standards for Protection Against Radiation.'' Thus, 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 determined that the revised HI-STORM UMAX Canister Storage
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 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 into Holtec International
HI-STORM UMAX Canister Storage System casks that meet the criteria of
Revision 1 to Amendment Nos. 0 through 2 to CoC No. 1040.
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
Holtec International HI-STORM UMAX Canister Storage 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.
[[Page 8863]]
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 Holtec
International HI-STORM UMAX Canister Storage System listing within the
``List of approved spent fuel storage casks'' to include Revision 1 to
Amendment Nos. 0 through 2 to CoC No. 1040.
B. The Need for the Action
This direct final rule revises the CoC for the Holtec International
HI-STORM UMAX Canister Storage System design within the list of
approved spent fuel storage casks to allow power reactor licensees to
store spent fuel at reactor sites in casks with the approved
modifications under a general license. Specifically, Revision 1 to
Amendment Nos. 0 through 2 revises the CoC to update the CoC appendix A
technical specifications for radiation protection and the associated
bases information to clearly articulate the basis for the dose rate
limits for the closure lids, modify the dose rate limit values and the
description of the location of the dose rate measurements, and make
other editorial changes.
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 this Revision 1 to Amendment Nos. 0
through 2 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 Holtec International HI-STORM UMAX Canister 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 revision 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 Revision 1 to Amendment Nos. 0 through
2 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 safety findings in the
preliminary safety evaluation report.
D. Alternative to the Action
The alternative to this action is to deny approval of Revision 1 to
Amendment Nos. 0 through 2 and not issue the direct final rule.
Consequently, any 10 CFR part 72 general licensee that seeks to load
spent nuclear fuel into the Holtec International HI-STORM UMAX Canister
Storage System in accordance with the changes described in proposed
Revision 1 to Amendment Nos. 0 through 2 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 Revision 1 to Amendment Nos. 0 through 2 to CoC No.
1040 would result in no irreversible and irretrievable commitments of
Federal 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: Holtec International HI-STORM UMAX
Canister Storage System, Certificate of Compliance No. 1040, Revision 1
to Amendment Nos. 0 through 2,'' 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.
[[Page 8864]]
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
Holtec. 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 CoC; and (3) the
conditions of the general license are met. A list of NRC-approved cask
designs is contained in Sec. 72.214. On March 6, 2015 (80 FR 12073),
as corrected (80 FR 15679; March 25, 2015), the NRC issued an amendment
to 10 CFR part 72 that approved the Holtec International HI-STORM UMAX
Canister Storage System by adding it to the list of NRC-approved cask
designs in Sec. 72.214.
On May 5, 2023, and as supplemented on January 31, 2024, March 4,
2024, and June 26, 2024, Holtec submitted a request to revise the HI-
STORM UMAX Canister Storage System as described in Section IV,
``Discussion of Changes,'' of this document.
The alternative to this action is to withhold approval of Revision
1 to Amendment Nos. 0 through 2 and to require any 10 CFR part 72
general licensee seeking to load spent nuclear fuel into Holtec
International HI-STORM UMAX Canister Storage System under the changes
described in Revision 1 to Amendment Nos. 0 through 2 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
General licensees using CoC amendments that are being revised are
required to meet the conditions of the revised CoC. The NRC added a
condition to the revised CoC No. 1040 that requires the general
licensee to implement the revised CoC within six months and perform
written evaluations in accordance with 10 CFR 72.212(b)(5), which
establish that the cask will conform to the terms, conditions, and
specifications of the revised CoC. The six-month timeframe in the
condition is considered a standard timeframe for implementation,
consistent with the information in Regulatory Issue Summary 2017-05,
``Administration of 10 CFR part 72 Certificate of Compliance
Corrections and Revisions.'' Additionally, the implementation timeframe
was recognized by the applicant and the general licensee using this
amendment (ML24178A111).
For the following reasons, the NRC has determined that this direct
final rule does not constitute backfitting under 10 CFR 72.62,
``Backfitting.'' This direct final rule revises Amendment Nos. 0, 1,
and 2 of CoC No. 1040 for the HI-STORM UMAX Canister Storage System, as
currently listed in 10 CFR 72.214, ``List of approved spent fuel
storage casks.'' Revision 1 to Amendment Nos. 0, 1, and 2 includes
changes to CoC appendix A technical specifications for radiation
protection and the associated bases information to clearly articulate
the basis for the dose rate limits for the closure lids and modify the
dose rate limit values and the description of the location of the dose
rate measurements.
Holtec has manufactured casks under existing CoC No. 1040,
Amendment Nos. 0, 1, or 2, that are being revised by this final rule.
As the vendor, Holtec is not within the scope of the backfitting
provisions in 10 CFR 72.62.
Under 10 CFR 72.62, general licensees are entities that are within
the scope of the backfitting regulations. However, according to Holtec
(ML24178A112), no general licensees are currently storing UMAX systems
under CoC No. 1040, Amendment Nos. 1 and 2, which are, in part, the
subject of these revisions. Therefore, because CoC No. 1040, Amendment
Nos. 1 and 2 are not in use by a licensee, the changes in the revision
to CoC No. 1040, Amendment Nos. 1 and 2, which are approved in this
direct final rule do not fall within the definition of backfitting
under 10 CFR 72.62.
Ameren Missouri at its Callaway Energy Center Independent Spent
Fuel Storage Installation is the only general licensee using Amendment
No. 0 that could be affected by the issuance of Revision 1 to Amendment
No. 0. In its letters to Holtec (ML23125A246 and ML24178A113), Ameren
Missouri stated that it intends to adopt and implement Revision 1 to
Amendment No. 0. Because the licensee voluntarily intends to implement
the revision, the issuance of Revision 1 to Amendment No. 0 does not
fall within the definition of backfitting under 10 CFR 72.62.
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.
[[Page 8865]]
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Document ADAMS accession No.
------------------------------------------------------------------------
Proposed Certificate of Compliance and Technical Specifications
Documents
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User Need Memo for Revision to Amendment ML24179A273
Nos. 0, 1, and 2 of the Certificate of
Compliance No. 1040 for the HI-STORM
UMAX Canister Storage System.
Preliminary Safety Evaluation Report for ML24179A263
HI-STORM UMAX, CoC No. 1040, Revision
to Amendment Nos. 0, 1, and 2.
Proposed CoC No. 1040, Amendment No. 0, ML24179A266
Revision 1.
Proposed CoC No. 1040, Amendment No. 0, ML24179A264
Revision 1, Appendix A.
Proposed CoC No. 1040, Amendment No. 0, ML24179A265
Revision 1, Appendix B.
Proposed CoC No. 1040, Amendment No. 1, ML24179A269
Revision 1.
Proposed CoC No. 1040, Amendment No. 1, ML24179A267
Revision 1, Appendix A.
Proposed CoC No. 1040, Amendment No. 1, ML24179A268
Revision 1, Appendix B.
Proposed CoC No. 1040, Amendment No. 2, ML24179A272
Revision 1.
Proposed CoC No. 1040, Amendment No. 2, ML24179A270
Revision 1, Appendix A.
Proposed CoC No. 1040, Amendment No. 2, ML24179A271
Revision 1, Appendix B.
------------------------------------------------------------------------
Holtec International, Inc. HI-STORM UMAX Canister Storage System
Revision 1 to Amendment Nos. 0 through 2 Request Documents
------------------------------------------------------------------------
Letter, ``Holtec International-- ML23125A237
Submittal of Application for Revision
to HI-STORM UMAX CoC Amendments 0, 1,
and 2,'' dated May 5, 2023.
Letter, ``Holtec International, ML24031A659
Submittal of RSI Responses for Revision
to HI-STORM UMAX CoC Amendments 0, 1,
and 2,'' dated January 31, 2024.
Letter, ``Holtec International, ML24072A501
Submittal of RSI Supplemental
Information for Revision to HI-STORM
UMAX CoC Amendments 0, 1, and 2,''
dated March 4, 2024.
Letter, ``Supplement to Application for ML24178A111
Revision to Amendment Nos. 0, 1, and 2
of Certificate of Compliance No. 1040
for HI-STORM UMAX,'' dated June 26,
2024.
Ameren Missouri letter to Holtec, ML23125A246
``Attachment 8--General Licensee
Letters Regarding Revisions,'' dated
March 1, 2023.
Ameren Missouri letter to Holtec, ML24178A113
``Ameren Missouri's Intent to Adopt
Revision 1 to Amendment 0 of
Certificate of Compliance No. 1040 as
applicable to the ISFSI at the Callaway
Plant Site,'' dated June 6, 2024.
Email Re: Supplement to Application for ML24178A112
Revision to Amendment Nos. 0, 1, and 2
of CoC No. 1040 for HI-STORM UMAX,
dated June 26, 2024.
------------------------------------------------------------------------
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-2024-0182. 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-2024-0182); (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. 1040 is revised to
read as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1040.
Initial Certificate Effective Date: April 6, 2015, superseded by
Initial Certificate, Revision 1 Effective Date: April 21, 2025.
Amendment Number 1 Effective Date: September 8, 2015, superseded by
Amendment Number 1, Revision 1 Effective Date: April 21, 2025.
Amendment Number 2 Effective Date: January 9, 2017, superseded by
Amendment Number 2, Revision 1 Effective Date: April 21, 2025.
Amendment Number 3 [Reserved]
Amendment Number 4 Effective Date: January 25, 2021.
SAR Submitted by: Holtec International, Inc.
SAR Title: Final Safety Analysis Report for the Holtec
International HI-STORM UMAX Canister Storage System.
Docket Number: 72-1040.
Certificate Expiration Date: April 6, 2035.
Model Number: MPC-37, MPC-89.
* * * * *
Dated: January 16, 2025.
For the Nuclear Regulatory Commission.
Mirela Gavrilas,
Executive Director for Operations.
[FR Doc. 2025-02208 Filed 2-3-25; 8:45 am]
BILLING CODE 7590-01-P