[Federal Register Volume 91, Number 140 (Thursday, July 23, 2026)]
[Rules and Regulations]
[Pages 46243-46248]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2026-14876]
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2026-2476]
RIN 3150-AL71
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM Flood/Wind System, Certificate of Compliance No. 1032,
Amendment No. 10
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International HI-
STORM Flood/Wind (FW) System listing within the ``List of approved
spent fuel storage casks'' to include Amendment No. 10 to Certificate
of Compliance (CoC) No. 1032. Amendment No. 10 revises the CoC for the
HI-STORM FW dry storage system to incorporate several enhancements.
These changes include the introduction of the HI-STORM FW Extended
Configuration, adoption of a methodology for developing site-specific
loading patterns with higher allowable per-canister and per-cell heat-
load limits, incorporation of a radiological fuel-qualification
methodology, reduction of minimum cooling-time requirements for certain
multi-purpose canister models based on updated evaluations, and
refinement of the missile-impact analysis methodology to allow site-
specific credit for the HI-TRAC VW water-jacket shell. The amendment
also includes a minor editorial clarification.
DATES: This direct final rule is effective October 6, 2026, unless
significant adverse comments are received by August 24, 2026. 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direct final rule is withdrawn as a result of such comments, timely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-2026-2476,
at https://www.regulations.gov. If your material cannot be submitted
using https://www.regulations.gov, call or email the individuals listed
in the FOR FURTHER INFORMATION CONTACT section of this document for
alternate instructions.
Do not include any personally identifiable information (such as
name, address, or other contact information) or confidential business
information that you do not want publicly disclosed. All comments are
public records; they are publicly displayed exactly as received, and
will not be deleted, modified, or redacted. Comments may be submitted
anonymously.
Follow the search instructions on https://www.regulations.gov to
view public comments. You can read a plain language description of this
direct final rule at https://www.regulations.gov/docket/ NRC-2026-2476.
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: Denise Edwards, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-7204, email:
[email protected] and John-Chau Nguyen, Office of Nuclear Material
Safety and Safeguards; telephone: 301-415-0262, email: [email protected]. Both are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
III. Background
IV. Discussion of Changes
V. Voluntary Consensus Standards
VI. Agreement State Compatibility
VII. Plain Writing
VIII. Environmental Assessment and Finding of No Significant Impact
IX. Regulatory Planning and Review
X. Paperwork Reduction Act Statement
XI. Regulatory Flexibility Certification
XII. Regulatory Analysis
XIII. Backfitting and Issue Finality
XIV. Congressional Review Act
XV. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2026-2476 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-2026-2476. Address
questions about NRC dockets to Helen
[[Page 46244]]
Chang, telephone: 301-415-3228, email: [email protected]. For
technical questions contact the individuals 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 ADAMS Public Search.''
For problems with ADAMS, please contact the NRC's Public Document Room
(PDR) reference staff at 1-800-397-4209, at 301-415-4737, or by email
to [email protected]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time, Monday through Friday, except Federal
holidays.
B. Submitting Comments
The NRC encourages electronic comment submission through the
Federal rulemaking website (https://www.regulations.gov). Please
include Docket ID NRC-2026-2476 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. 10
to Certificate of Compliance (CoC) No. 1032 and does not include other
aspects of the HI-STORM FW Cask 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 non-controversial. Adequate protection of public health
and safety continues to be reasonably assured. The amendment to the
rule will become effective on October 6, 2026. However, if the NRC
receives any significant adverse comment on this direct final rule by
August 24, 2026, then the NRC will publish a document that withdraws
this action and will subsequently address the comments received in a
final rule as a response to the companion proposed rule published in
the Proposed Rules section of this issue of the Federal Register or as
otherwise appropriate. In general, absent significant modifications to
the proposed revisions requiring republication, the NRC will not
initiate a second comment period on this action.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficient
to require a substantive response in a notice-and-comment process. For
example, a substantive response is required when:
(a) The comment causes the NRC to reevaluate (or reconsider) its
position or conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
(c) The comment raises a relevant issue that was not previously
addressed or considered by the NRC.
(2) The comment proposes a change or an addition to the rule, and
it is apparent that the rule would be ineffective or unacceptable
without incorporation of the change or addition.
(3) The comment causes the NRC to make a change (other than
editorial) to the rule, CoC, or technical specifications.
III. Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended,
requires that ``[t]he Secretary [of the Department of Energy] shall
establish a demonstration program, in cooperation with the private
sector, for the dry storage of spent nuclear fuel at civilian nuclear
power reactor sites, with the objective of establishing one or more
technologies that the [Nuclear Regulatory] Commission may, by rule,
approve for use at the sites of civilian nuclear power reactors
without, to the maximum extent practicable, the need for additional
site-specific approvals by the Commission.'' Section 133 of the Nuclear
Waste Policy Act states, in part, that ``[t]he Commission shall, by
rule, establish procedures for the licensing of any technology approved
by the Commission under Section 219(a) [sic: 218(a)] for use at the
site of any civilian nuclear power reactor.''
To implement this mandate, the Commission approved dry storage of
spent nuclear fuel in NRC-approved casks under a general license by
publishing a final rule that added a new subpart K in part 72 of title
10 of the Code of Federal Regulations (10 CFR) entitled ``General
License for Storage of Spent Fuel at Power Reactor Sites'' (55 FR
29181; July 18, 1990). This rule also established a new subpart L in 10
CFR part 72 entitled ``Approval of Spent Fuel Storage Casks,'' which
contains procedures and criteria for obtaining NRC approval of spent
fuel storage cask designs. The NRC subsequently issued a final rule on
March 28, 2011 (76 FR 17019), that approved the HI-STORM FW System
design and added it to the list of NRC-approved cask designs in Sec.
72.214 as CoC No. 1032.
IV. Discussion of Changes
On March 1, 2024, Holtec International submitted a request to the
NRC to amend CoC No. 1032. Holtec International supplemented its
request on the following dates: September 16, 2024, December 12, 2024,
February 28, 2025, July 28, 2025, September 11, 2025, and January 30,
2026. Amendment No. 10 revises the CoC to:
Introduce the HI-STORM FW Extended Configuration. This
version of the HI-STORM FW system is an anchored configuration that
allows storage of two multi-purpose canisters (MPCs) stored vertically
within a specially designed system of two storage overpacks.
Incorporation of a methodology to develop site-specific
loading patterns in Chapter 4 of the HI-STORM FW final safety analysis
report (FSAR) and inclusion of higher maximum per canister and per cell
limits for those patterns.
Incorporation of the ``Topical Report on the Radiological
Fuel Qualification Methodology for Dry Storage Systems,'' Holtec Report
HI-2210161-A. Related details and requirements are specified in the new
Appendix B to Chapter 5 of the FSAR.
[[Page 46245]]
Reduce MPC-44 minimum cooling time from 3 years to 1 year,
and MPC-37P minimum cooling time from 1.6 years to 1 year.
Revise the FSAR methodology for HI-TRAC VW missile
penetration to allow site-specific analysis to take credit for the HI-
TRAC VW water jacket shell.
Minor editorial change to the CoC and providing a
clarification to AppendixB of the CoC by updating the MPC-89 maximum
fuel assembly length in Table 2.1-1 to 181.5 inches, which includes
configurations involving a damaged fuel canister or a damaged fuel
isolator.
The changes to the aforementioned documents are identified with
revisions 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 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.
10 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 staff determined that the amended HI-STORM FW 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 Sec.
72.210 may, consistent with the license conditions under Sec. 72.212,
load spent nuclear fuel into HI-STORM FW casks that meet the criteria
of Amendment No. 10 to CoC No. 1032.
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
HI-STORM FW Cask System design listed in Sec. 72.214, ``List of
approved spent fuel storage casks.'' This action does not constitute
the establishment of a standard that contains generally applicable
requirements.
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 (NEPA) 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. This
environmental assessment and finding of no significant impact can be
tracked with identification number NEPA ID EAXX-429-00-000-1778667092.
A. The Action
The action is to amend Sec. 72.214 to revise the Holtec
International HI-STORM FW listing within the ``List of approved spent
fuel storage casks'' to include Amendment No. 10 to CoC No. 1032.
B. The Need for the Action
This direct final rule amends the CoC for Holtec International HI-
STORM FW 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. 10 revises the CoC for the HI-STORM FW dry
storage system to incorporate several enhancements. These changes
include the introduction of the HI-STORM FW Extended Configuration, an
anchored design that accommodates two multi-purpose canisters stored
vertically within specially engineered overpacks; adoption of a
methodology for developing site-specific loading patterns with higher
allowable per-canister and per-cell heat-load limits; incorporation of
a radiological fuel-qualification methodology, including associated
analytical requirements; reduction of minimum cooling-time requirements
for certain multi-purpose canister models based on updated evaluations;
and refinement of the missile-impact analysis methodology to allow
site-specific credit for the HI-TRAC VW water-jacket shell. The
amendment also includes a minor editorial clarification. Collectively,
these revisions update the HI-STORM FW CoC and Final Safety Analysis
Report consistent with Holtec's requested 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. 10 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.
Holtec International HI-STORM FW 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
[[Page 46246]]
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. 10 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.
10 and not issue the direct final rule. Consequently, any 10 CFR part
72 general licensee that seeks to load spent nuclear fuel into Holtec
International HI-STORM FW in accordance with the changes described in
proposed Amendment No. 10 would have to request an exemption from the
requirements of Sec. Sec. 72.212 and 72.214. Under this alternative,
interested licensees would have to prepare, and the NRC would have to
review, a separate exemption request, thereby increasing the
administrative burden upon the NRC and the costs to each licensee. The
environmental impacts would be the same as the proposed action.
E. Alternative Use of Resources
Approval of Amendment No. 10 to CoC No. 1032 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.
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 Flood/Wind System, CoC No. 1032,
Amendment No. 10,'' 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. Regulatory Planning and Review
Executive Order (E.O.) 12866, as amended by E.O. 14215, provides
that the Office of Information and Regulatory Affairs (OIRA) will
determine whether a regulatory action is significant as defined by E.O.
12866 and will review significant regulatory actions. OIRA determined
that this direct final rule is not a significant regulatory action
under E.O. 12866
X. 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 collection of information unless the document requesting
or requiring the collection displays a currently valid OMB control
number.
XI. 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 Internation. These entities do not fall within the scope of the
definition of small entities set forth in the Regulatory Flexibility
Act or the size standards established by the NRC (Sec. 2.810).
XII. Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent nuclear fuel under a
general license in cask designs approved by the NRC. Any nuclear power
reactor licensee can use NRC-approved cask designs to store spent
nuclear fuel if (1) it notifies the NRC in advance; (2) the spent fuel
is stored under the conditions specified in the cask's CoC; and (3) the
conditions of the general license are met. A list of NRC-approved cask
designs is contained in Sec. 72.214. On 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 Sec. 72.214.
On March 1, 2024, and as supplemental on September 16, 2024,
December 12, 2024, February 28, 2025, July 28, 2025, September 11,
2025, and January 30, 2026, 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. 10 and to require any 10 CFR part 72 general licensee seeking to
load spent nuclear fuel into Holtec International HI-STORM FW under the
changes described in Amendment No. 10 to request an exemption from the
requirements of Sec. Sec. 72.212 and 72.214. Under this alternative,
each interested 10 CFR part 72 licensee would have to prepare, and the
NRC would have to review, a separate exemption request, thereby
increasing the administrative burden upon the NRC and the costs to each
licensee.
Approval of this direct final rule is consistent with previous NRC
actions. Further, as documented in the preliminary safety evaluation
report and environmental assessment, this direct final rule will have
no adverse effect on public health and safety or the environment. This
direct final rule has no significant identifiable impact or benefit on
other government agencies. Based on this regulatory analysis, the NRC
concludes that the requirements of this direct final rule are
commensurate with the NRC's responsibilities for public health and
safety and the common defense and security. No other available
alternative is believed to be as satisfactory; therefore, this action
is recommended.
XIII. Backfitting and Issue Finality
The NRC has determined that the backfit rule (Sec. 72.62) does not
apply to this direct final rule. Therefore, a backfit analysis is not
required. This direct final rule revises CoC No. 1032 for the Holtec
International HI-STORM FW, as currently listed in Sec. 72.214. The
revision consists of the changes in Amendment
[[Page 46247]]
No. 10 previously described, as set forth in the revised CoC and
technical specifications.
Amendment No. 10 to CoC No. 1032 for the Holtec International HI-
STORM FW was initiated by Holtec International and was not submitted in
response to new NRC requirements, or an NRC request for amendment.
Amendment No. 10 applies only to new casks fabricated and used under
Amendment No. 10. These changes do not affect existing users of the
Holtec International HI-STORM FW, and the current Amendment No. 7
continues to be effective for existing users. While current users of
this storage system may comply with the new requirements in Amendment
No. 10, this would be a voluntary decision on the part of current
users.
For these reasons, Amendment No. 10 to CoC No. 1032 does not
constitute backfitting under Sec. 72.62 or Sec. 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.
XIV. Congressional Review Act
This direct final rule is not a rule as defined in the
Congressional Review Act.
XV. Availability of Documents
The documents identified in the following table are available to
interested persons as indicated.
------------------------------------------------------------------------
ADAMS Accession No./web link/
Document Federal Register citation
------------------------------------------------------------------------
Proposed Certificate of Compliance and Proposed Technical Specifications
Documents
------------------------------------------------------------------------
Proposed HI-STORM FW 1032 ML26057A285.
Amendment No. 10 CoC.
Proposed CoC 1032 Amendment No. 10 ML26057A287.
Technical Specification Appendix
A.
Proposed CoC 1032 Amendment No. 10 ML26057A286.
Technical Specification Appendix
B.
Preliminary Safety Evaluation ML26057A284.
Report. CoC No. 1032, Amendment
10.
------------------------------------------------------------------------
Holtec International HI-STORM FW Amendment No. 10 Request Documents
------------------------------------------------------------------------
Holtec International--HI-STORM FW ML24109A249 (package).
Amendment 10 Request, dated March
1, 2024.
Holtec International--HI-STORM FW ML24260A280 (package).
Amendment 10 Responses to RSIs,
dated September 16, 2024.
Holtec International--HI-STORM FW ML24348A143 (package).
Amendment 10 Supplemental
Information; dated December 12,
2024.
HI-STORM FW Amendment 10 Response ML25062A248 (package).
to Non-Proprietary RSI 3-1, dated
February 28, 2025.
Holtec International--HI-STORM FW ML25209A538 (package).
Amendment 10, Response to Request
for Additional Information First
Batch, dated July 28, 2025.
Holtec International--HI-STORM FW ML25254A228 (package).
Amendment 10, Response to Request
for Additional Information Second
Batch, dated September 11, 2025.
Holtec International--HI-STORM FW ML26030A208 (package).
Amendment 10, RAI Batch 1
Response Clarification, dated
January 30, 2026.
Holtec International--HI-STORM FW ML26030A224 (package).
Amendment 10, RAI Batch 2
Response Clarification, dated
January 30, 2026.
------------------------------------------------------------------------
Other Documents
------------------------------------------------------------------------
User Need for Rulemaking for ML26063A538.
Amendment No. 10 to HI-STORM FW
No.1032 System.
Final Rule, ``General License for 55 FR 29181.
Storage of Spent Fuel at Power
Reactor Sites,'' published July
18, 1990.
Direct Final Rule, ``List of 76 FR 17019.
Approved Spent Fuel Storage
Casks: HI-STORM Flood/Wind
Addition,'' published March 28,
2011.
``List of Approved Spent Fuel 76 FR 33121.
Storage Casks: HI-STORM Flood/
Wind Addition,'' published June
8, 2011.
Revision to Policy Statement, 82 FR 48535.
``Agreement State Program Policy
Statement; Correction,''
published October 18, 2017.
Executive Order 12866, 58 FR 51735.
``Regulatory Planning and
Review,'' October 4, 1993.
Presidential Memorandum, ``Plain 63 FR 31885.
Language in Government Writing,''
published June 10, 1998.
------------------------------------------------------------------------
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-2026-2476. 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-2026-2476); (2) click
the ``Subscribe'' link; and (3) enter an email address and click on the
``Subscribe'' link.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Indians,
Intergovernmental relations, Nuclear energy, Penalties, Radiation
protection, Reporting and recordkeeping requirements, Security
measures, Spent fuel, Whistleblowing.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended; the Energy Reorganization
Act of 1974, as amended; the Nuclear Waste Policy Act of 1982, as
amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following
amendments to 10 CFR part 72:
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
0
1. The authority citation for part 72 continues to read as follows:
Authority: Atomic Energy Act of 1954, secs. 51, 53, 57, 62, 63,
65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42
U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2210e,
2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C.
5841, 5842, 5846, 5851); National Environmental Policy Act of 1969
(42 U.S.C. 4332); Nuclear Waste Policy Act of 1982, secs. 117(a),
132, 133, 134, 135, 137,
[[Page 46248]]
141, 145(g), 148, 218(a) (42 U.S.C. 10137(a), 10152, 10153, 10154,
10155, 10157, 10161, 10165(g), 10168, 10198(a)); 44 U.S.C. 3504
note.
0
2. In Sec. 72.214, Certificate of Compliance No. 1032 is revised to
read as follows:
Sec. 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 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: September 25, 2024.
Amendment Number 8 Effective Date: October 11, 2022.
Amendment Number 10 Effective Date: October 6, 2026.
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: July 13, 2026.
For the Nuclear Regulatory Commission.
David Curtis,
Acting Executive Director for Operations.
[FR Doc. 2026-14876 Filed 7-22-26; 8:45 am]
BILLING CODE 7590-01-P