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.

Rules and Regulations Federal Register

8861 

Vol. 90, No. 22 

Tuesday, February 4, 2025 

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is withdrawn as a result of such 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: 

George.Tartal@nrc.gov and Kristina 

Banovac, Office of Nuclear Materials 

Safety and Safeguards, telephone: 301– 

415–7116, email: Kristina.Banovac@

nrc.gov. 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: 

Helen.Chang@nrc.gov. 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 

PDR.Resource@nrc.gov. 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 PDR.Resource@nrc.gov 

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 


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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-andcomment 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 § 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 § 72.210 may, consistent 

with the license conditions under 

§ 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 § 72.214, ‘‘List 

of approved spent fuel storage casks.’’ 

This action does not constitute the 

establishment of a standard that 

contains generally applicable 

requirements. 


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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 § 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 tornadogenerated 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 nonradiological 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 

§§ 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. 


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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 

(§ 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 § 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 

§ 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 §§ 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. 


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Federal Register / Vol. 90, No. 22 / Tuesday, February 4, 2025 / Rules and Regulations 8865 

Document ADAMS 

accession No. 

Proposed Certificate of Compliance and Technical Specifications Documents 

User Need Memo for Revision to Amendment Nos. 0, 1, and 2 of the Certificate of Compliance No. 1040 for the HI–STORM 

UMAX Canister Storage System.

ML24179A273 

Preliminary Safety Evaluation Report for HI–STORM UMAX, CoC No. 1040, Revision to Amendment Nos. 0, 1, and 2 ............ ML24179A263 

Proposed CoC No. 1040, Amendment No. 0, Revision 1 ............................................................................................................... ML24179A266 

Proposed CoC No. 1040, Amendment No. 0, Revision 1, Appendix A ........................................................................................... ML24179A264 

Proposed CoC No. 1040, Amendment No. 0, Revision 1, Appendix B ........................................................................................... ML24179A265 

Proposed CoC No. 1040, Amendment No. 1, Revision 1 ............................................................................................................... ML24179A269 

Proposed CoC No. 1040, Amendment No. 1, Revision 1, Appendix A ........................................................................................... ML24179A267 

Proposed CoC No. 1040, Amendment No. 1, Revision 1, Appendix B ........................................................................................... ML24179A268 

Proposed CoC No. 1040, Amendment No. 2, Revision 1 ............................................................................................................... ML24179A272 

Proposed CoC No. 1040, Amendment No. 2, Revision 1, Appendix A ........................................................................................... ML24179A270 

Proposed CoC No. 1040, Amendment No. 2, Revision 1, Appendix B ........................................................................................... ML24179A271 

Holtec International, Inc. HI–STORM UMAX Canister Storage System Revision 1 to Amendment Nos. 0 through 2 Request Documents 

Letter, ‘‘Holtec International—Submittal of Application for Revision to HI–STORM UMAX CoC Amendments 0, 1, and 2,’’ 

dated May 5, 2023.

ML23125A237 

Letter, ‘‘Holtec International, Submittal of RSI Responses for Revision to HI–STORM UMAX CoC Amendments 0, 1, and 2,’’ 

dated January 31, 2024.

ML24031A659 

Letter, ‘‘Holtec International, Submittal of RSI Supplemental Information for Revision to HI–STORM UMAX CoC Amendments 

0, 1, and 2,’’ dated March 4, 2024.

ML24072A501 

Letter, ‘‘Supplement to Application for Revision to Amendment Nos. 0, 1, and 2 of Certificate of Compliance No. 1040 for HI– 

STORM UMAX,’’ dated June 26, 2024.

ML24178A111 

Ameren Missouri letter to Holtec, ‘‘Attachment 8—General Licensee Letters Regarding Revisions,’’ dated March 1, 2023 ......... ML23125A246 

Ameren Missouri letter to Holtec, ‘‘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.

ML24178A113 

Email Re: Supplement to Application for Revision to Amendment Nos. 0, 1, and 2 of CoC No. 1040 for HI–STORM UMAX, 

dated June 26, 2024.

ML24178A112 

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 

■ 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. 

■ 2. In § 72.214, Certificate of 

Compliance No. 1040 is revised to read 

as follows: 

§ 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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