```

[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]

========================================================================
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. 

========================================================================


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.

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

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direct final rule is withdrawn as a result of such comments, timely 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]]

------------------------------------------------------------------------
                Document                       ADAMS  accession No.
------------------------------------------------------------------------
     Proposed Certificate of Compliance and Technical Specifications
                                Documents
------------------------------------------------------------------------
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
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