[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 Multipurpose 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 multipurpose 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 [INSERT DATE 75 DAYS AFTER DATE OF
PUBLICATION IN THE FEDERAL REGISTER], unless significant adverse comments are
received by [INSERT DATE 30 DAYS AFTER DATE OF PUBLICATION IN THE
FEDERAL REGISTER]. If this direct final rule is withdrawn as a result of such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 comments, 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: 301-4151018, 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:

I.
II.
III.
IV.
V.
VI.

Obtaining Information and Submitting Comments
Rulemaking Procedure
Background
Discussion of Changes
Voluntary Consensus Standards
Agreement State Compatibility

VII.
VIII.
IX.
X.
XI.
XII.
XIII.
XIV.

Plain Writing
Environmental Assessment and Finding of No Significant Impact
Paperwork Reduction Act Statement
Regulatory Flexibility Certification
Regulatory Analysis
Backfitting and Issue Finality
Congressional Review Act
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.
•

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-20240096 in your comment submission.
The NRC cautions you not to include identifying or contact information that you
do not want to be publicly disclosed in your comment submission. The NRC will post all
comment submissions at https://www.regulations.gov as well as enter the comment
submissions into ADAMS. The NRC does not routinely edit comment submissions to
remove identifying or contact information.
If you are requesting or aggregating comments from other persons for
submission to the NRC, then you should inform those persons not to include identifying
or contact information that they do not want to be publicly disclosed in their comment
submission. Your request should state that the NRC does not routinely edit comment
submissions to remove such information before making the comment submissions
available to the public or entering the comment into ADAMS.

II. Rulemaking Procedure

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 System (HI-STORM FW System) design.
The NRC is using the “direct final rule procedure” to issue this amendment because it
represents a limited and routine change to an existing CoC that is expected to be noncontroversial. Adequate protection of public health and safety continues to be
reasonably assured. The amendment to the rule will become effective on [INSERT

DATE 75 DAYS AFTER DATE OF PUBLICATION IN THE FEDERAL REGISTER].
However, if the NRC receives any significant adverse comment on this direct final rule
by [INSERT DATE 30 DAYS AFTER DATE OF PUBLICATION IN THE FEDERAL
REGISTER], 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 June 8, 2011 (76 FR 33121), that approved the
Holtec International HI-STORM FW System design and added it to the list of NRCapproved 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.
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.
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 eccentricities 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
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 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 amended HI-STORM FW System cask 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 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. 104113) 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 HI-STORM FW 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.

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 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 use 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

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
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-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 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, thereby increasing the administrative burden
upon the NRC and the costs to each licensee. The environmental impacts would be the
same as the proposed action.

E. Alternative Use of Resources
Approval of Amendment No. 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
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 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.

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 NRCapproved 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 June 8, 2011 (76 FR 33121), the NRC issued an amendment
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 safety evaluation report and environmental
assessment, this direct final rule will have no adverse effect on public health and safety
or the environment. This direct final rule has no significant identifiable impact or benefit
on other government agencies. Based on this regulatory analysis, the NRC concludes
that the requirements of this direct final rule are commensurate with the NRC's
responsibilities for public health and safety and the common defense and security. No
other available alternative is believed to be as satisfactory; therefore, this action is
recommended.

XII. Backfitting and Issue Finality

The NRC has determined that the backfit rule (§ 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 provisions applicable to combined licenses in
10 CFR part 52. Accordingly, the NRC has not prepared a backfit analysis for this
rulemaking.

XIII. Congressional Review Act

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

XIV. Availability of Documents

The documents identified in the following table are available to interested
persons as indicated.
DOCUMENT

ADAMS ACCESSION NO. / WEB
LINK / FEDERAL REGISTER
CITATION
Proposed Certificate of Compliance and Proposed Technical Specifications
Certificate of Compliance No.1032,
Amendment No. 7
Certificate of Compliance No. 1032,
Amendment 7, Appendix A: Technical
Specifications
Certificate of Compliance No. 1032,
Amendment 7, Appendix B: Approved
Contents and Design Features
Certificate of Compliance No. 1032,
Amendment No. 7, Preliminary Safety
Evaluation Report
Environmental Documents
Environmental Assessment for Proposed
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
of No Significant Impact for the Final Rule
Amending 10 CFR Part 72 License and
Certificate of Compliance Terms,” dated May 3,
ML23030B793
ML23030B794
ML23030B795
ML23030B796

ML051230231

ML100710441

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
Amendment 7 Request, dated May 6, 2021
Holtec International HI-STORM FW
Amendment 7 Request
Attachment 1 - HI-STORM FW Amendment 7
Summary of Proposed Changes
Attachment 2 - HI-STORM FW Amendment 7
Certificate of Compliance
Attachment 3 - HI-STORM FW Amendment 7
Certificate of Compliance, Appendix A
Attachment 4 - HI-STORM FW Amendment 7
Certificate of Compliance, Appendix B
Attachment 6 - HI-STORM FW FSAR
Proposed Revision 9 Revised Pages (NonProprietary)
Attachment 29: Affidavit of Kimberly
Manzione in Accordance with 10 CFR 2.390
HOLTEC International HI-STORM FW
Amendment 7 Responses to Requests for
Supplemental Information, dated October 15,
2021
Holtec International, HI-STORM FW
Amendment 9 Request, dated February 17,
2022
Holtec International, HI-STORM FW
Amendment 7 Responses to Requests for
Additional Information Part 1, dated July 11,
2022
Holtec International, HI-STORM FW
Amendment 7 Responses to Requests for
Additional Information Part 1 – Additional
Supporting Documents, dated July 13, 2022
HI-STORM FW Amendment 7 Responses to
Requests for Additional Information Part 2,
dated July 29, 2022
Holtec International, HI-STORM FW
Amendment 7 RAI Responses Part 1
Clarification Call Action Items, dated
September 15, 2022
HI-STORM FW Amendment 7 Responses to
Requests for Additional Information Part 3,
dated October 3, 2022
HI-STORM FW Amendment 7 RAI 5-2
Response Clarification, dated December 1,
ML21126A266 (package)
ML21126A267
ML21126A268
ML21126A269
ML21126A270
ML21126A271
ML21126A273
ML21126A297
ML21288A521 (package)

ML22048C221
ML22192A215 (package)

ML22194A954

ML22210A145 (package)
ML22258A250 (package)

ML22276A281 (package)
ML22336A132 (package)

Holtec International HI-STORM FW
Amendment 7 Responses to Requests for
Additional Information Part 4, dated January
6, 2023
Holtec International - HI-STORM FW
Amendment 7 Responses to Requests for
Additional Information Part 5, dated May 8,
2023
Holtec International HI-STORM FW
Amendment 7 RAI Responses Part 5
Clarification Call Action Items, dated June 30,
2023
Holtec International, HI-STORM FW
Amendment 7 RAI Responses Part 5
Clarification Corrected Attachments 4 and 5,
dated July 11, 2023
Holtec International, HI-STORM FW
Amendment 7 RAI 3-10 Response
Clarification Call Action Items, dated August
15, 2023
HI-STORM FW Amendment 7 RAI Response
Clarifications (Part 3), dated November 17,
2023
Holtec International, HI-STORM FW
Amendment 7 RAI Response Clarifications
(Part 4), dated February 16, 2024
HI-STORM FW Amendment 7 RAI Response
Clarifications (Part 5), dated April 8, 2024
Other Documents
User Need Memo for Rulemaking for the
Holtec HI-STORM Flood/Wind Multi-Purpose
Canister Storage System, CoC No. 1032,
Amendment 7, dated May 17, 2024
“Agreement State Program Policy Statement;
Correction,” dated October 18, 2017
Plain Language in Government Writing,
dated June 10, 1998
Storage of Spent Fuel In NRC-Approved
Storage Casks at Power Reactor Sites: Final
Rule, dated July 18, 1990
List of Approved Spent Fuel Storage Casks:
HI-STORM Flood/Wind Addition,
dated June 8, 2011

ML23006A263 (package)

ML23128A302 (package)

ML23181A192 (package)

ML23192A031 (package)

ML23227A248 (package)

ML23321A245 (package)
ML24047A323 (package)
ML24100A027 (package)

ML23030B792

82 FR 48535
63 FR 31885
55 FR 29181
76 FR 33121

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.

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 REACTORRELATED 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:

§ 72.214 List of approved spent fuel storage casks.
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Certificate Number: 1032.
Initial Certificate Effective Date: June 13, 2011, superseded by Amendment Number 0,

Revision 1, on April 25, 2016.
Amendment Number 0, Revision 1, Effective Date: April 25, 2016.
Amendment Number 1 Effective Date: December 17, 2014, superseded by Amendment
Number 1, Revision 1, on June 2, 2015.
Amendment Number 1, Revision 1, Effective Date: June 2, 2015.
Amendment Number 2 Effective Date: November 7, 2016.
Amendment Number 3 Effective Date: September 11, 2017.
Amendment Number 4 Effective Date: July 14, 2020.
Amendment Number 5 Effective Date: July 27, 2020.
Amendment Number 6 Effective Date: March 22, 2023.
Amendment Number 7 Effective Date: [INSERT DATE 75 DAYS FROM DATE OF
PUBLICATION IN THE FEDERAL REGISTER].
Amendment Number 8 Effective Date: October 11, 2022.
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.
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Dated: June 26, 2024.

For the Nuclear Regulatory Commission.

Raymond Furstenau,
Acting Executive Director for Operations.
[FR Doc. 2024-15133 Filed: 7/11/2024 8:45 am; Publication Date: 7/12/2024]