ML24138A122

Direct Final Rule: List of Approved Spent Fuel Storage Casks: Holtec International, HI-STORM Flood/Wind System, Certificate of Compliance No. 1032, Amendment No. 7

ML24138A122
Person / Time
Issue date:	06/26/2024
From:	Raymond Furstenau NRC/EDO
To:
References
RIN 3150-AL17, NRC-2024-0096, 89 FR 57064
Download: ML24138A122 (23)

Text

[7590-01-P]

NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2024-0096]

RIN 3150-AL17

List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM FW

System, Certificate of Compliance No. 1032, Amendment No. 7

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 Flood/Wind Multi-

purpose Canister Storage System listing within the List of approved spent fuel storage

casks to include Amendment No. 7 to Certificate of Compliance No. 1032. Amendment

No. 7 revises the certificate of compliance to add a new overpack, add new multi-

purpose canisters MPC-44 and MPC-37P, and add new fuel type 10x10J to approved

content. Amendment No. 7 also incorporates other technical changes and several

editorial changes.

DATES: This direct final rule is effective September 25, 2024, unless significant adverse

comments are received by August 12, 2024. If this direct final rule is withdrawn as a

result of such comments, timely notice of the withdrawal will be published in the Federal

Register. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this

date. Comments received on this direct final rule will also be considered to be comments

on a companion proposed rule published in the Proposed Rules section of this issue of

the Federal Register.

ADDRESSES: Submit your comments, identified by Docket ID NRC-2024-0096

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-2024-0096. For additional direction on

obtaining information and submitting co mments, see Obtaining Information and

Submitting Comments in the SUPPLEMENTARY INFORMATION section of this

document.

FOR FURTHER INFORMATION CONTACT: Caylee Kenny, Office of Nuclear Material

Safety and Safeguards, telephone: 301-415-7150, email: Caylee.Kenny@nrc.gov; and

Yen-Ju Chen, Office of Nuclear Material Safety and Safeguards, telephone: 301-415-

1018, email: Yen-Ju.Chen@nrc.gov. Both are staff of the U.S. Nuclear Regulatory

Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION:

TABLE OF CONTENTS:

2 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-2024-0096 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-2024-0096. Address questions about NRC dockets to Dawn

Forder, telephone: 301-415-3407, email: Dawn.Forder@nrc.gov. For technical questions

contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of

this document.

• NRCs 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 NRCs 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

3 reader, instructions about obtaining materials referenced in this document are provided

in the Availability of Documents section.

• NRCs 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-

0096 in your comment submission.

The NRC cautions you not to include identif ying or contact information that you

do not want to be publicly disclosed in y our comment submission. The NRC will post all

comment submissions at https://www.regulat ions.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 w ant to be publicly disclosed in their comment

submission. Your request should state that the NRC does not routinely edit comment

submissions to remove such information before making the comment submissions

available to the public or entering the comment into ADAMS.

II. Rulemaking Procedure

4 This rule is limited to the changes contained in Amendment No. 7 to Certificate of

Compliance (CoC) No. 1032 and does not include other aspects of the HI-STORM

Flood/Wind Multi-purpose Canister Storage Sy stem (HI-STORM FW System) design.

The NRC is using the direct final rule proc edure to issue this amendment 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 ru le will become effective on September 25,

2024. However, if the NRC receives any signific ant adverse comment on this direct final

rule by August 12, 2024, then the NRC will publish a document that withdraws this action

and will subsequently address the comments received in a final rule as a response to the

companion proposed rule published in the Proposed Rules section of this issue of the

Federal Register or as otherwise appropriate. In general, absent significant modifications

to the proposed revisions requiring republic ation, 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 rules 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

5 response to clarify or complete the record; or

c) The comment raises a relevant iss ue 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 te chnology 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

6 (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 June 8, 2011 (76 FR 33121), that approved the

Holtec International HI-STORM FW Syst em design and added it to the list of NRC-

approved cask designs in § 72.214 as Certificate of Compliance No. 1032.

IV. Discussion of Changes

On May 6, 2021, Holtec International submitted a request to the NRC to amend

Certificate of Compliance No. 1032. Holtec International supplemented its request on

October 15, 2021; February 17, 2022; July 11, 2022; July 13, 2022; July 29, 2022;

September 15, 2022; October 3, 2022; December 1, 2022; January 6, 2023; May 8,

2023; June 30, 2023; July 11, 2023; August 15, 2023; November 17, 2023; February 16,

2024; and April 8, 2024. Amendment No. 7 revises the CoC as follows:

1. Adds a new unventilated high density (UVH) overpack, HI-STORM 100 UVH,

which includes high density concrete for shielding. The UVH is to be used with

MPC-37, MPC-89, and the new MPC-44.

2. Modifies vent and drain penetrations to include the option of a second port

cover plate.

3. Allows automated equipment to perform leak test of the MPC materials and

welds in the fabrication shop.

4. Changes the hydrostatic pressure test of the MPC acceptance criteria to be

examination for leakage only and removes post hydrostatic test liquid penetrant

and magnetic particle examination.

7

5. Includes the ability to use computational fluid dynamics analysis to evaluate

site-specific fire accident scenarios.

6. Uses updated methodology for tornado missile stability calculations for

freestanding HI-STORMs and HI-TRACs (transfer casks) and clarifies the

weights to be used for varying heights of HI-TRACs.

7. Adds the new MPC-44, with continuous basket shim (CBS) and to hold 44

pressurized-water reactor fuel assemblies of certain 14x14 fuel class. It is to be

used with HI-STORM FW System Version E and UVH overpacks.

8. Adds the new MPC-37P, with CBS and to hold 37 pressurized-water reactor

fuel assemblies of certain 15x15 fuel class. It is to be used with Version E

overpack.

9. Adds HI-DRIP ancillary system, which is an optional ancillary system designed

to prevent water within the MPC while loaded in the HI-TRAC from boiling during

loading and unloading operations.

10. Includes the ability to use computational fluid dynamics analysis to evaluate

site-specific burial-under-debris accident scenarios.

11. Includes the ability to use water without glycol in the HI-TRAC water jacket

during transfer operations below 32°F based on the site specific MPC total heat

loads.

12. Adds new 10x10J fuel type to approved content in the HI-STORM FW

System.

13. Updates bounding fuel variables for 8x8F and 11x11A boiling-water reactor

fuel types in CoC appendix B.

14. Adopts a stress-based structural design criterion.

8

15. Establishes specific criteria on allowable interference due to differential thermal

expansion.

This amendment also makes the following editorial changes:

1. Revises the description of the HI-STORM FW System in the CoC to clearly

indicate that only the portions of the components that come into contact with the

pool water need to be made of stainless steel or aluminum. This change was

previously approved in HI-STORM FW System Amendment No. 8.

2. Revises the statements in final safety analysis report (FSAR) Section 3.2

related to center of gravity eccentriciti es in the evaluation of lifting devices.

3. Revises the FSAR by deleting Appendices 3.A to 3.C and adding references to

calculation packages [3.4.13] and [3.4.15], where applicable.

4. Revises CoC Appendix B Section 2.5 to clarify that the equation burn up and

cooling time qualification requirements only apply to specific alternative loading

patterns.

5. Revises the FSAR by adding discussions related to short-term operations in

the event of environmental phenomena to provide clarity and guidance on

required site-specific analyses.

6. Revises the FSAR by adding discussions related to site-specific analyses and

adds references to a series of analysis methodologies for standardization.

The changes to the aforementioned documents are identified with revisions bars

in the margin of each document.

In a final rule effective July 14, 2020 (85 FR 43419), the NRC approved Holtec

International HI-STORM FW System Certificate of Compliance No. 1032, Amendment

9 No. 4 but did not include the model number. The NRC is correcting the list of model

numbers to include MPC-32ML.

As documented in the preliminary safety evaluation report, the NRC performed a

safety evaluation of the proposed CoC amendment request. The NRC determined that

this amendment does not reflect a significant change in design or fabrication of the cask.

Specifically, the NRC determined that the design of the cask would continue to maintain

confinement, shielding, and criticality control in the event of each evaluated accident

condition. In addition, any resulting occupational exposure or offsite dose rates from the

implementation of Amendment No. 7 would rema in 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 amended HI-STORM FW System cask design,

when used under the conditions specified in the CoC, the technical specifications, and

the NRCs 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 HI-STORM FW System casks that meet the criteria of Amendment No. 7 to

Certificate of Compliance No. 1032.

V. Voluntary Consensus Standards

The National Technology Transfer and Advancement Act of 1995 (Pub. L. 104-

10 113) 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 im practical. In this direct final rule, the NRC

revises the HI-STORM FW System design list ed 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.

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).

11 VIII. Environmental Assessment and Finding of No Significant Impact

Under the National Environmental Policy Act of 1969, as amended, and the

NRCs 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, ther efore, 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 FW

System listing within the List of approved spent fuel storage casks to include

Amendment No. 7 to Certificate of Compliance No. 1032.

B. The Need for the Action

This direct final rule amends the CoC for the Holtec International HI-STORM FW

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, Amendment No. 7 revises the CoC to add a new

unventilated high density (UVH) overpack, modify vent and drain penetrations, allow

automated equipment to perform leak test, change the hydrostatic pressure test

acceptance criteria, include the ability to us e computational fluid dynamics analysis to

evaluate site-specific fire accident scenario, use updated methodology for tornado

missile stability calculations, add the new MPC-44, add the new MPC-37P, add HI-DRIP

12 ancillary system, include the ability to use computational fluid dynamics analysis to

evaluate site-specific burial-under-debris accident scenario, include the ability to use

water without glycol in the HI-TRAC water jacket, add new 10x10J fuel type to approved

content, update bounding fuel variables for specific fuel types, adopt a stress-based

structural design criterion, establish specific criteria on allowable interference due to

differential thermal expansion, and 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 Amendment No. 7 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 FW System is designed to mitigate the

effects of design basis accidents that could occur during storage. Design basis accidents

account for human-induced events and the most severe natural phenomena reported for

the site and surrounding area. Postulated accidents analyzed for an independent spent

fuel storage installation, the type of facility at which a holder of a power reactor operating

license would store spent fuel in casks in accordance with 10 CFR part 72, can include

tornado winds and tornado-generated missiles, a design basis earthquake, a design

basis flood, an accidental cask drop, lightning effects, fire, explosions, and other

incidents.

This amendment does not reflect a significant change in design or fabrication of

13 the cask. Because there are no significant design or process changes, any resulting

occupational exposure or offsite dose rates from the implementation of Amendment No.

7 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-radiologi cal environmental impacts that significantly

differ from the environmental impacts ev aluated 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, r adiological 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 Amendment No. 7 and not

issue the direct final rule. Consequently, any 10 CFR part 72 general licensee that seeks

to load spent nuclear fuel into a Holtec International HI-STORM FW System in

accordance with the changes described in proposed Amendment No. 7 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, ther eby 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

14 Approval of Amendment No. 7 to Certificate of Compliance No. 1032 would result

in no irreversible commitment of resources.

F. Agencies and Persons Contacted

No agencies or persons outside the NRC were contacted in connection with the

preparation of this environmental assessment.

G. Finding of No Significant Impact

The environmental impacts of the action have been reviewed under the

requirements in the National Environmental Policy Act of 1969, as amended, and the

NRCs 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 concl udes that this direct final rule, List

of Approved Spent Fuel Storage Casks: Holt ec International HI-STORM FW System

Certificate of Compliance No. 1032, Amendment No. 7, will not have a significant effect

on the human environment. Therefore, the NRC has determined that an environmental

impact statement is not necessary for this direct final rule.

IX. Paperwork Reduction Act Statement

This direct final rule does not contain any new or amended collections of

information subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

Existing collections of information were approved by the Office of Management and

Budget, approval number 3150-0132.

15 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 International. 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 casks CoC; and 3) the

conditions of the general license are met. A list of NRC-approved cask designs is

contained in § 72.214. On June 8, 2011 (76 FR 33121), the NRC issued an amendment

16 to 10 CFR part 72 that approved the HI-STORM FW System by adding it to the list of

NRC-approved cask designs in § 72.214.

On May 6, 2021, and as supplemented on October 15, 2021, February 17, 2022,

July 11, 2022, July 13, 2022, July 29, 2022, September 15, 2022, October 3, 2022,

December 1, 2022, January 6, 2023, May 8, 2023, June 30, 2023, July 11, 2023, August

15, 2023, November 17, 2023, February 16, 2024, and April 8, 2024, Holtec International

submitted a request to amend the HI-STORM FW System as described in Section IV,

Discussion of Changes, of this document.

The alternative to this action is to withhold approval of Amendment No. 7 and to

require any 10 CFR part 72 general licensee seeking to load spent nuclear fuel into the

Holtec International HI-STORM FW System under the changes described in Amendment

No. 7 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 safe ty 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.

17 XII. Backfitting and Issue Finality

The NRC has determined that the backfit rule (§ 72.62) does not apply to this

direct final rule. Therefore, a backfit analysis is not required. This direct final rule revises

Certificate of Compliance No. 1032 for the Holtec International HI-STORM FW System

as currently listed in § 72.214. The revision consists of the changes in Amendment No. 7

previously described, as set forth in the revised CoC and technical specifications.

Amendment No. 7 to Certificate of Compliance No. 1032 for the Holtec

International HI-STORM FW System was initiated by Holtec International and was not

submitted in response to new NRC requirements, or an NRC request for amendment.

Amendment No. 7 applies only to new casks fabricated and used under Amendment No.

7. These changes do not affect existing users of the Holtec International HI-STORM FW

System and the current Amendment Nos. 6 and 8 continue to be effective for existing

users. While current users of this storage system may comply with the new requirements

in Amendment No. 7, this would be a voluntary decision on the part of current users.

For these reasons, Amendment No. 7 to Certificate of Compliance No. 1032

does not constitute backfitting under § 72.62 or § 50.109(a)(1), or otherwise represent

an inconsistency with the issue finality pr ovisions applicable to combined licenses in

10 CFR part 52. Accordingly, the NRC has not prepared a backfit analysis for this

rulemaking.

XIII. Congressional Review Act

This direct final rule is not a rule as defined in the Congressional Review Act.

18 XIV. Availability of Documents

The documents identified in the following table are available to interested

persons as indicated.

DOCUMENT ADAMS ACCESSION NO. / WEB LINK / FEDERAL REGISTER CITATION Proposed Certificate of Compliance and Proposed Technical Specifications

Certificate of Compliance No.1032, ML23030B793 Amendment No. 7 Certificate of Compliance No. 1032, ML23030B794 Amendment 7, Appendix A: Technical Specifications Certificate of Compliance No. 1032, ML23030B795 Amendment 7, Appendix B: Approved Contents and Design Features Certificate of Compliance No. 1032, ML23030B796 Amendment No. 7, Preliminary Safety Evaluation Report Environmental Documents

Environmental Assessment for Proposed ML051230231 Rule Entitled, "Storage of Spent Nuclear Fuel in NRC-Approved Storage Casks at Nuclear Power Reactor Sites," dated March 8,1989 Environmental Assessment and Finding ML100710441 of No Significant Impact for the Final Rule Amending 10 CFR Part 72 License and Certificate of Compliance Terms, dated May 3, 2010 Generic Environmental Impact Statement ML14198A440 (package) for Continued Storage of Spent Nuclear Fuel: Final Report (NUREG-2157, Volumes 1 and 2), dated September 30, 2014 Storage of Spent Fuel In NRC-Approved 55 FR 29181 Storage Casks at Power Reactor Sites Final Rule, dated July 18, 1990 Holtec International HI-STORM FW Amendment 7 Request Documents

Holtec International - HI-STORM FW ML21126A266 (package)

Amendment 7 Request, dated May 6, 2021 Holtec International HI-STORM FW ML21126A267 Amendment 7 Request 19 - HI-STORM FW Amendment 7 ML21126A268 Summary of Proposed Changes - HI-STORM FW Amendment 7 ML21126A269 Certificate of Compliance - HI-STORM FW Amendment 7 ML21126A270 Certificate of Compliance, Appendix A - HI-STORM FW Amendment 7 ML21126A271 Certificate of Compliance, Appendix B - HI-STORM FW FSAR ML21126A273 Proposed Revision 9 Revised Pages (Non-Proprietary) 9: Affidavit of Kimberly ML21126A297 Manzione in Accordance with 10 CFR 2.390 HOLTEC International HI-STORM FW ML21288A521 (package)

Amendment 7 Responses to Requests for Supplemental Information, dated October 15, 2021 Holtec International, HI-STORM FW ML22048C221 Amendment 9 Request, dated February 17, 2022 Holtec International, HI-STORM FW ML22192A215 (package)

Amendment 7 Responses to Requests for Additional Information Part 1, dated July 11, 2022 Holtec International, HI-STORM FW ML22194A954 Amendment 7 Responses to Requests for Additional Information Part 1 - Additional Supporting Documents, dated July 13, 2022 HI-STORM FW Amendment 7 Responses to ML22210A145 (package)

Requests for Additional Information Part 2, dated July 29, 2022 Holtec International, HI-STORM FW ML22258A250 (package)

Amendment 7 RAI Responses Part 1 Clarification Call Action Items, dated September 15, 2022 HI-STORM FW Amendment 7 Responses to ML22276A281 (package)

Requests for Additional Information Part 3, dated October 3, 2022 HI-STORM FW Amendment 7 RAI 5-2 ML22336A132 (package)

Response Clarification, dated December 1, 2022 Holtec International HI-STORM FW ML23006A263 (package)

Amendment 7 Responses to Requests for Additional Information Part 4, dated January 6, 2023 Holtec International - HI-STORM FW ML23128A302 (package)

Amendment 7 Responses to Requests for Additional Information Part 5, dated May 8, 2023 20 Holtec International HI-STORM FW ML23181A192 (package)

Amendment 7 RAI Responses Part 5 Clarification Call Action Items, dated June 30, 2023 Holtec International, HI-STORM FW ML23192A031 (package)

Amendment 7 RAI Responses Part 5 Clarification Corrected Attachments 4 and 5, dated July 11, 2023 Holtec International, HI-STORM FW ML23227A248 (package)

Amendment 7 RAI 3-10 Response Clarification Call Action Items, dated August 15, 2023 HI-STORM FW Amendment 7 RAI Response ML23321A245 (package)

Clarifications (Part 3), dated November 17, 2023 Holtec International, HI-STORM FW ML24047A323 (package)

Amendment 7 RAI Response Clarifications (Part 4), dated February 16, 2024 HI-STORM FW Amendment 7 RAI Response ML24100A027 (package)

Clarifications (Part 5), dated April 8, 2024 Other Documents

User Need Memo for Rulemaking for the ML23030B792 Holtec HI-STORM Flood/Wind Multi-Purpose Canister Storage System, CoC No. 1032, Amendment 7, dated May 17, 2024 Agreement State Program Policy Statement; 82 FR 48535 Correction, dated October 18, 2017 Plain Language in Government Writing, 63 FR 31885 dated June 10, 1998 Storage of Spent Fuel In NRC-Approved 55 FR 29181 Storage Casks at Power Reactor Sites: Final Rule, dated July 18, 1990 List of Approved Spent Fuel Storage Casks: 76 FR 33121 HI-STORM Flood/Wind Addition, dated June 8, 2011

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-2024-0096. 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-2024-0096); 2) click the Subscribe

link; and 3) enter an email address and click on the Subscribe link.

21 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. 1032 is revised to read as follows:

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§ 72.214 List of approved spent fuel storage casks.

Certificate Number: 1032.

Initial Certificate Effective Date: June 13, 2011, superseded by Amendment Number 0,

Revision 1, on April 25, 2016.

Amendment Number 7 Effective Date: September 25, 2024.

SAR Submitted by: Holtec International

SAR

Title:

Final Safety Analysis Report for the HI-STORM FW System.

Docket Number: 72-1032.

Certificate Expiration Date: June 12, 2031.

Model Number: HI-STORM FW MPC-32ML, MPC-37, MPC-37P, MPC-44, and MPC-89.

Dated: June 26, 2024.

For the Nuclear Regulatory Commission.

/RA/

Raymond Furstenau, Acting Executive Director for Operations.

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