List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewed Amendment No. 18, 72304-72309 [2024-19801]
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Amendment Number 3, Revision 2 on
October 16, 2023.
Amendment Number 4 Effective Date:
April 14, 2015, superseded by
Amendment Number 4, Revision 1, on
October 16, 2023.
Amendment Number 5 Effective Date:
June 29, 2015, superseded by
Amendment Number 5, Revision 1, on
October 16, 2023.
Amendment Number 6 Effective Date:
December 21, 2016, superseded by
Amendment Number 6, Revision 1, on
October 16, 2023.
Amendment Number 7 Effective Date:
August 21, 2017, as corrected (ADAMS
Accession No. ML19045A346),
superseded by Amendment Number 7,
Revision 1, on October 16, 2023.
Amendment Number 8, Effective
Date: March 24, 2020, superseded by
Amendment Number 8, Revision 1, on
October 16, 2023.
Amendment Number 9, Effective
Date: December 7, 2020, superseded by
Amendment Number 9, Revision 1, on
October 16, 2023.
Amendment Number 10, Effective
Date: January 18, 2023.
Amendment Number 11, Effective
Date: October 16, 2023.
Amendment Number 12, Effective
Date: October 16, 2023.
Amendment Number 13 Effective
Date: November 19, 2024.
SAR Submitted by: NAC
International, Inc.
SAR Title: Final Safety Analysis
Report for the MAGNASTOR® System.
Docket Number: 72–1031.
Certificate Expiration Date: February
4, 2029.
Model Number: MAGNASTOR®.
*
*
*
*
*
Dated: August 21, 2024.
For the Nuclear Regulatory Commission.
Mirela Gavrilas,
Executive Director for Operations.
[FR Doc. 2024–19894 Filed 9–4–24; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
[NRC–2024–0105]
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RIN 3150–AL18
ACTION:
Direct final rule.
The U.S. Nuclear Regulatory
Commission (NRC) is amending its
spent fuel storage regulations by
revising the Holtec International HI–
STORM 100 Cask System listing within
the ‘‘List of approved spent fuel storage
casks’’ to include Renewed Amendment
No. 18 to Certificate of Compliance No.
1014. Renewed Amendment No. 18
amends the certificate of compliance to
incorporate the Holtec Report No. HI–
2200343–A entitled, ‘‘Topical Report for
Allowance of Heat Load Patterns in HI–
STORM 100 and HI–STORM FW
Systems.’’
DATES: This direct final rule is effective
November 19, 2024, unless significant
adverse comments are received by
October 7, 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is withdrawn as a result of such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–2024–0105
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-2024-0105. 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:
Christian Jacobs, Office of Nuclear
Material Safety and Safeguards;
telephone: 301–415–6825; email:
Christian.Jacobs@nrc.gov or Sarah
Lopas, Office of Nuclear Material Safety
and Safeguards; telephone: 301–415–
6360; email: Sarah.Lopas@nrc.gov. Both
are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
SUMMARY:
List of Approved Spent Fuel Storage
Casks: Holtec International HI–STORM
100 Cask System, Certificate of
Compliance No. 1014, Renewed
Amendment No. 18
Table of Contents
Nuclear Regulatory
Commission.
I. Obtaining Information and Submitting
Comments
AGENCY:
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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–
0105 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–2024–0105. Address
questions about NRC dockets to Helen
Chang, telephone: 301–415–3228, email:
Helen.Chang@nrc.gov. For technical
questions contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publicly
available documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘Begin Web-based ADAMS Search.’’ For
problems with ADAMS, please contact
the NRC’s Public Document Room (PDR)
reference staff at 1–800–397–4209, 301–
415–4737, or by email to
PDR.Resource@nrc.gov. For the
convenience of the reader, instructions
about obtaining materials referenced in
this document are provided in the
‘‘Availability of Documents’’ section.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8 a.m. and 4 p.m. eastern
time, Monday through Friday, except
Federal holidays.
B. Submitting Comments
The NRC encourages electronic
comment submission through the
Federal rulemaking website (https://
www.regulations.gov). Please include
Docket ID NRC–2024–0105 in your
comment submission.
The NRC cautions you not to include
identifying or contact information that
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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 Renewed Amendment No.
18 to Certificate of Compliance No. 1014
and does not include other aspects of
the HI–STORM 100 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 certificate
of compliance 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
November 19, 2024. However, if the
NRC receives any significant adverse
comment on this direct final rule by
September 26, 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
republication, the NRC will not initiate
a second comment period on this action.
A significant adverse comment is a
comment where the commenter
explains why the rule would be
inappropriate, including challenges to
the rule’s underlying premise or
approach, or would be ineffective or
unacceptable without a change. A
comment is adverse and significant if:
(1) The comment opposes the rule and
provides a reason sufficient to require a
substantive response in a notice-andcomment process. For example, a
substantive response is required when:
(a) The comment causes the NRC to
reevaluate (or reconsider) its position or
conduct additional analysis;
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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 May 1, 2000 (65 FR 25241),
that approved the HI–STORM 100 Cask
System design and added it to the list
of NRC-approved cask designs in
§ 72.214 as Certificate of Compliance
No. 1014.
1014. Holtec International
supplemented its request on the
following dates: September 2, 2022
(ML22245A103), May 26, 2023
(ML23146A138), September 8, 2023
(ML23251A250), December 4, 2023
(ML23338A304), January 18, 2024
(ML24018A198), and February 15, 2024
(ML24046A254). Renewed Amendment
No. 18 amends the certificate of
compliance to incorporate the Holtec
Report No. HI–2200343–A entitled,
‘‘Topical Report for Allowance of Heat
Load Patterns in HI–STORM 100 and
HI–STORM FW Systems’’
(ML24018A198).
As documented in the preliminary
safety evaluation report, the NRC
performed a safety evaluation of the
proposed certificate of compliance
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 Renewed
Amendment No. 18 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 100 Cask System
design, when used under the conditions
specified in the certificate of
compliance, 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 100 cask systems that meet
the criteria of Renewed Amendment No.
18 to Certificate of Compliance No.
1014.
IV. Discussion of Changes
On December 15, 2021
(ML21349B418), Holtec International
submitted a request to the NRC to
amend Certificate of Compliance No.
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
(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, certificate of compliance, or
technical specifications.
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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 100 Cask
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
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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 100 listing within the ‘‘List of
approved spent fuel storage casks’’ to
include Renewed Amendment No. 18 to
Certificate of Compliance No. 1014.
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B. The Need for the Action
This direct final rule amends the
certificate of compliance for the Holtec
International HI–STORM 100 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, Renewed Amendment No.
18 amends the certificate of compliance
to incorporate the Holtec Report No. HI–
2200343–A entitled, ‘‘Topical Report for
Allowance of Heat Load Patterns in HI–
STORM 100 and HI–STORM FW
Systems.’’
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
Renewed Amendment No. 18 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
100 Cask 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 Renewed
Amendment No. 18 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
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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 Renewed Amendment
No. 18 and not issue the direct final
rule. Consequently, any 10 CFR part 72
general licensee that seeks to load spent
nuclear fuel into the Holtec
International HI–STORM 100 Cask
System in accordance with the changes
described in proposed Renewed
Amendment No. 18 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 Renewed Amendment
No. 18 to Certificate of Compliance No.
1014 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 100 Cask System Certificate of
Compliance No. 1014, Renewed
Amendment No. 18,’’ will not have a
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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 (10 CFR 2.810).
XI. Regulatory Analysis
On July 18, 1990 (55 FR 29181), the
NRC issued an amendment to 10 CFR
part 72 to provide for the storage of
spent nuclear fuel under a general
license in cask designs approved by the
NRC. Any nuclear power reactor
licensee can use NRC-approved cask
designs to store spent nuclear fuel if (1)
it notifies the NRC in advance; (2) the
spent fuel is stored under the conditions
specified in the cask’s certificate of
compliance; and (3) the conditions of
the general license are met. A list of
NRC-approved cask designs is contained
in § 72.214. On May 1, 2000 (65 FR
25241), the NRC issued an amendment
to 10 CFR part 72 that approved the
Holtec International HI–STORM 100
Cask Design system by adding it to the
list of NRC-approved cask designs in
§ 72.214.
On December 15, 2021, and as
supplemented on September 2, 2022,
May 26, 2023, September 8, 2023,
December 4, 2023, January 18, 2024, and
February 15, 2024, Holtec International
submitted a request to amend the Holtec
International HI–STORM 100 Cask
Design system, as described in Section
IV, ‘‘Discussion of Changes,’’ of this
document.
The alternative to this action is to
withhold approval of Renewed
Amendment No. 18 and to require any
10 CFR part 72 general licensee seeking
to load spent nuclear fuel into the
Holtec International HI–STORM 100
Cask System design under the changes
described in Renewed Amendment No.
18 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.
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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. 1014 for the Holtec International
HI–STORM 100 Cask System design, as
currently listed in § 72.214. The
amendment consists of the changes in
Renewed Amendment No. 18 previously
described, as set forth in the amended
certificate of compliance and technical
specifications.
Renewed Amendment No. 18 to
Certificate of Compliance No. 1014 for
the Holtec International HI–STORM 100
Cask System design was initiated by
Holtec International and was not
submitted in response to new NRC
requirements, or an NRC request for
amendment. Renewed Amendment No.
18 applies only to new casks fabricated
and used under Renewed Amendment
No. 18. These changes do not affect
existing users of the Holtec International
HI–STORM 100 Cask System design,
and previously issued renewed
amendments continue to be effective for
existing users. While current users of
this storage system may comply with
the new requirements in Renewed
Amendment No. 18, this would be a
voluntary decision on the part of current
users.
For these reasons, Renewed
Amendment No. 18 to Certificate of
Compliance No. 1014 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.
ADAMS accession No./
Federal Register citation
Document
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Proposed Certificate of Compliance, Proposed Technical Specifications, and Preliminary Safety Evaluation Report for Certificate of
Compliance No. 1014, Renewed Amendment No. 18
User Need Rulemaking Package for Certificate of Compliance No. 1014, HI–STORM 100 Cask System, Renewed
Amendment No. 18.
ML24095A039 (package).
Environmental Documents
Environmental Assessment for Proposed Rule Entitled, ‘‘Storage of Spent Nuclear Fuel in NRC-Approved Storage
Casks at Nuclear Power Reactor Sites.’’ (1989).
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ADAMS accession No./
Federal Register citation
Document
‘‘Environmental Assessment and Finding of No Significant Impact for the Final Rule Amending 10 CFR Part 72 License and Certificate of Compliance Terms’’ (2010).
Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel: Final Report (NUREG–
2157, Volumes 1 and 2) (2014).
‘‘Storage of Spent Fuel In NRC-Approved Storage Casks at Power Reactor Sites’’ Final Rule (July 18, 1990) .........
ML100710441.
ML14198A440 (package).
55 FR 29181.
Holtec International HI–STORM 100 Cask Design System Amendment No. 18 Request Documents
Holtec International, Submittal of HI–STORM 100 Request for Amendment No. 18, dated December 15, 2021 .......
Holtec International, HI–STORM 100 Amendment No. 18 Responses to Requests for Supplemental Information,
dated September 2, 2022.
Holtec International—Submittal of RAI Responses on HI–STORM 100 Amendment No. 18, dated May 26, 2023 ....
Holtec International, Submittal of Supplement to RAI Responses on HI–STORM 100 Amendment No. 18, dated
September 8, 2023.
Holtec International, Submittal of Supplement to RAI Responses on HI–STORM 100 Amendment No. 18, dated
December 4, 2023.
Holtec Report No. HI–2200343–A, ‘‘Topical Report for Allowance of Heat Load Patterns in HI–STORM 100 and
HI–STORM FW Systems’’ (January 18, 2024).
Holtec International, Submittal of Supplement to RAI Responses on HI–STORM 100 Amendment No. 18, dated
February 15, 2024.
ML21349B418 (package).
ML22245A103 (package).
ML23146A138 (package).
ML23251A250 (package).
ML23338A304 (package).
ML24018A198 (package).
ML24046A254 (package).
Other Documents
‘‘Agreement State Program Policy Statement; Correction’’ (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: Holtec HI–STORM 100 Addition, dated May 1, 2000 ............................
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–2024–0105. 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–
2024–0105); (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
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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:
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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 Number
1014 is revised to read as follows:
■
§ 72.214 List of approved spent fuel
storage casks.
*
*
*
*
*
Certificate Number: 1014.
Initial Certificate Effective Date: May
31, 2000, superseded by Renewed Initial
Certificate Effective Date: August 2,
2023.
Amendment Number 1 Effective Date:
July 15, 2002, superseded by Renewed
Amendment Number 1 Effective Date:
August 2, 2023.
PO 00000
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82
63
55
65
FR
FR
FR
FR
48535.
31885.
29181.
25241.
Amendment Number 2 Effective Date:
June 7, 2005, superseded by Renewed
Amendment Number 2 Effective Date:
August 2, 2023.
Amendment Number 3 Effective Date:
May 29, 2007, superseded by Renewed
Amendment Number 3 Effective Date:
August 2, 2023.
Amendment Number 4 Effective Date:
January 8, 2008, superseded by
Renewed Amendment Number 4
Effective Date: August 2, 2023.
Amendment Number 5 Effective Date:
July 14, 2008, superseded by Renewed
Amendment Number 5 Effective Date:
August 2, 2023.
Amendment Number 6 Effective Date:
August 17, 2009, superseded by
Renewed Amendment Number 6
Effective Date: August 2, 2023.
Amendment Number 7 Effective Date:
December 28, 2009, superseded by
Renewed Amendment Number 7
Effective Date: August 2, 2023.
Amendment Number 8 Effective Date:
May 2, 2012, as corrected on November
16, 2012 (ADAMS Accession No.
ML12213A170); superseded by
Amendment Number 8, Revision 1,
Effective Date: February 16, 2016;
superseded by Renewed Amendment
Number 8, Revision 1 Effective Date:
August 2, 2023.
Amendment Number 9 Effective Date:
March 11, 2014, superseded by
Amendment Number 9, Revision 1,
Effective Date: March 21, 2016, as
corrected on August 25, 2017 (ADAMS
Accession No. ML17236A451);
E:\FR\FM\05SER1.SGM
05SER1
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Federal Register / Vol. 89, No. 172 / Thursday, September 5, 2024 / Rules and Regulations
superseded by Renewed Amendment
Number 9, Revision 1 Effective Date:
August 2, 2023.
Amendment Number 10 Effective
Date: May 31, 2016, as corrected on
August 25, 2017 (ADAMS Accession
No. ML17236A452); superseded by
Renewed Amendment Number 10
Effective Date: August 2, 2023.
Amendment Number 11 Effective
Date: February 25, 2019, as corrected
(ADAMS Accession No. ML19343B024);
superseded by Renewed Amendment
Number 11 Effective Date: August 2,
2023.
Amendment Number 12 Effective
Date: February 25, 2019, as corrected on
May 30, 2019 (ADAMS Accession No.
ML19109A111); further corrected
December 23, 2019 (ADAMS Accession
No. ML19343A908); superseded by
Renewed Amendment Number 12
Effective Date: August 2, 2023.
Amendment Number 13 Effective
Date: May 13, 2019, as corrected on May
30, 2019 (ADAMS Accession No.
ML19109A122); further corrected
December 23, 2019 (ADAMS Accession
No. ML19343B156); superseded by
Renewed Amendment Number 13
Effective Date: August 2, 2023.
Amendment Number 14 Effective
Date: December 17, 2019, as corrected
(ADAMS Accession No. ML19343B287);
superseded by Renewed Amendment
Number 14 Effective Date: August 2,
2023.
Amendment Number 15 Effective
Date: June 14, 2021, superseded by
Renewed Amendment Number 15
Effective Date: August 2, 2023.
Renewed Amendment Number 16
[Reserved].
Renewed Amendment Number 17
Effective Date: January 16, 2024.
Renewed Amendment Number 18
Effective Date: November 19, 2024.
Safety Analysis Report (SAR)
Submitted by: Holtec International.
SAR Title: Final Safety Analysis
Report for the HI–STORM 100 Cask
System.
Docket Number: 72–1014.
Certificate Expiration Date: May 31,
2020.
Renewed Certificate Expiration Date:
May 31, 2060.
Model Number: HI–STORM 100.
*
*
*
*
*
Dated: August 22, 2024.
For the Nuclear Regulatory Commission.
Mirela Gavrilas,
Executive Director for Operations.
[FR Doc. 2024–19801 Filed 9–4–24; 8:45 am]
BILLING CODE 7590–01–P
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DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2024–2132; Project
Identifier MCAI–2024–00417–T; Amendment
39–22830; AD 2024–17–05]
RIN 2120–AA64
Airworthiness Directives; Airbus SAS
Airplanes
Federal Aviation
Administration (FAA), DOT.
ACTION: Final rule; request for
comments.
AGENCY:
The FAA is adopting a new
airworthiness directive (AD) for all
Airbus SAS Model A330–200, –200
Freighter, –300, –800, and –900 series
airplanes, and A340–200 and –300
series airplanes. This AD was prompted
by a report of incorrect instructions in
the aircraft maintenance manual (AMM)
that specify using oxygen instead of
nitrogen for a pressure test, which could
lead to an uncontrolled fire during
maintenance. This AD prohibits using
specific AMM tasks that include the
incorrect instructions, as specified in a
European Union Aviation Safety Agency
(EASA) AD, which is incorporated by
reference. The FAA is issuing this AD
to address the unsafe condition on these
products.
DATES: This AD is effective September
20, 2024.
The Director of the Federal Register
approved the incorporation by reference
of a certain publication listed in this AD
as of September 20, 2024.
The FAA must receive comments on
this AD by October 21, 2024.
ADDRESSES: You may send comments,
using the procedures found in 14 CFR
11.43 and 11.45, by any of the following
methods:
• Federal eRulemaking Portal: Go to
regulations.gov. Follow the instructions
for submitting comments.
• Fax: 202–493–2251.
• Mail: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue SE,
Washington, DC 20590.
• Hand Delivery: Deliver to Mail
address above between 9 a.m. and 5
p.m., Monday through Friday, except
Federal holidays.
AD Docket: You may examine the AD
docket at regulations.gov under Docket
No. FAA–2024–2132; or in person at
Docket Operations between 9 a.m. and
5 p.m., Monday through Friday, except
Federal holidays. The AD docket
SUMMARY:
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72309
contains this final rule, the mandatory
continuing airworthiness information
(MCAI), any comments received, and
other information. The street address for
Docket Operations is listed above.
Material Incorporated by Reference:
• For EASA material identified in this
AD, contact EASA, Konrad-AdenauerUfer 3, 50668 Cologne, Germany;
telephone +49 221 8999 000; email
ADs@easa.europa.eu; website
easa.europa.eu. You may find this
material on the EASA website at
ad.easa.europa.eu.
• You may view this material at the
FAA, Airworthiness Products Section,
Operational Safety Branch, 2200 South
216th Street, Des Moines, WA. For
information on the availability of this
material at the FAA, call 206–231–3195.
It is also available at regulations.gov
under Docket No. FAA–2024–2132.
FOR FURTHER INFORMATION CONTACT:
Vladimir Ulyanov, Aviation Safety
Engineer, FAA, 1600 Stewart Avenue,
Suite 410, Westbury, NY 11590;
telephone 206–231–3229; email
Vladimir.Ulyanov@faa.gov.
SUPPLEMENTARY INFORMATION:
Comments Invited
The FAA invites you to send any
written data, views, or arguments about
this final rule. Send your comments to
an address listed under the ADDRESSES
section. Include ‘‘Docket No. FAA–
2024–2132; Project Identifier MCAI–
2024–00417–T’’ at the beginning of your
comments. The most helpful comments
reference a specific portion of the final
rule, explain the reason for any
recommended change, and include
supporting data. The FAA will consider
all comments received by the closing
date and may amend this final rule
because of those comments.
Except for Confidential Business
Information (CBI) as described in the
following paragraph, and other
information as described in 14 CFR
11.35, the FAA will post all comments
received, without change, to
regulations.gov, including any personal
information you provide. The agency
will also post a report summarizing each
substantive verbal contact received
about this final rule.
Confidential Business Information
CBI is commercial or financial
information that is both customarily and
actually treated as private by its owner.
Under the Freedom of Information Act
(FOIA) (5 U.S.C. 552), CBI is exempt
from public disclosure. If your
comments responsive to this AD contain
commercial or financial information
that is customarily treated as private,
E:\FR\FM\05SER1.SGM
05SER1
Agencies
[Federal Register Volume 89, Number 172 (Thursday, September 5, 2024)]
[Rules and Regulations]
[Pages 72304-72309]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-19801]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2024-0105]
RIN 3150-AL18
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewed
Amendment No. 18
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 100 Cask System listing within the ``List of approved spent fuel
storage casks'' to include Renewed Amendment No. 18 to Certificate of
Compliance No. 1014. Renewed Amendment No. 18 amends the certificate of
compliance to incorporate the Holtec Report No. HI-2200343-A entitled,
``Topical Report for Allowance of Heat Load Patterns in HI-STORM 100
and HI-STORM FW Systems.''
DATES: This direct final rule is effective November 19, 2024, unless
significant adverse comments are received by October 7, 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-2024-0105
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-2024-0105. 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: Christian Jacobs, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-6825; email:
[email protected] or Sarah Lopas, Office of Nuclear Material
Safety and Safeguards; telephone: 301-415-6360; email:
[email protected]. Both are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
III. Background
IV. Discussion of Changes
V. Voluntary Consensus Standards
VI. Agreement State Compatibility
VII. Plain Writing
VIII. Environmental Assessment and Finding of No Significant Impact
IX. Paperwork Reduction Act Statement
X. Regulatory Flexibility Certification
XI. Regulatory Analysis
XII. Backfitting and Issue Finality
XIII. Congressional Review Act
XIV. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2024-0105 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-2024-0105. Address
questions about NRC dockets to Helen Chang, telephone: 301-415-3228,
email: [email protected]. For technical questions contact the
individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, please contact the NRC's Public
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or
by email to [email protected]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time, Monday through Friday, except Federal
holidays.
B. Submitting Comments
The NRC encourages electronic comment submission through the
Federal rulemaking website (https://www.regulations.gov). Please
include Docket ID NRC-2024-0105 in your comment submission.
The NRC cautions you not to include identifying or contact
information that
[[Page 72305]]
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 Renewed Amendment
No. 18 to Certificate of Compliance No. 1014 and does not include other
aspects of the HI-STORM 100 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 certificate of
compliance 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 November
19, 2024. However, if the NRC receives any significant adverse comment
on this direct final rule by September 26, 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
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, certificate of compliance, 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
May 1, 2000 (65 FR 25241), that approved the HI-STORM 100 Cask System
design and added it to the list of NRC-approved cask designs in Sec.
72.214 as Certificate of Compliance No. 1014.
IV. Discussion of Changes
On December 15, 2021 (ML21349B418), Holtec International submitted
a request to the NRC to amend Certificate of Compliance No. 1014.
Holtec International supplemented its request on the following dates:
September 2, 2022 (ML22245A103), May 26, 2023 (ML23146A138), September
8, 2023 (ML23251A250), December 4, 2023 (ML23338A304), January 18, 2024
(ML24018A198), and February 15, 2024 (ML24046A254). Renewed Amendment
No. 18 amends the certificate of compliance to incorporate the Holtec
Report No. HI-2200343-A entitled, ``Topical Report for Allowance of
Heat Load Patterns in HI-STORM 100 and HI-STORM FW Systems''
(ML24018A198).
As documented in the preliminary safety evaluation report, the NRC
performed a safety evaluation of the proposed certificate of compliance
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 Renewed Amendment No. 18 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 100 Cask System
design, when used under the conditions specified in the certificate of
compliance, 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 100 cask systems that meet the criteria of Renewed Amendment No.
18 to Certificate of Compliance No. 1014.
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
[[Page 72306]]
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
100 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 of 1969, as amended,
and the NRC's regulations in 10 CFR part 51, ``Environmental Protection
Regulations for Domestic Licensing and Related Regulatory Functions,''
the NRC has determined that this direct final rule, if adopted, would
not be a major Federal action significantly affecting the quality of
the human environment and, therefore, an environmental impact statement
is not required. The NRC has made a finding of no significant impact on
the basis of this environmental assessment.
A. The Action
The action is to amend Sec. 72.214 to revise the Holtec
International HI-STORM 100 listing within the ``List of approved spent
fuel storage casks'' to include Renewed Amendment No. 18 to Certificate
of Compliance No. 1014.
B. The Need for the Action
This direct final rule amends the certificate of compliance for the
Holtec International HI-STORM 100 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, Renewed Amendment No. 18 amends
the certificate of compliance to incorporate the Holtec Report No. HI-
2200343-A entitled, ``Topical Report for Allowance of Heat Load
Patterns in HI-STORM 100 and HI-STORM FW Systems.''
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 Renewed Amendment No. 18 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 100 Cask 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 Renewed Amendment No. 18 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 Renewed
Amendment No. 18 and not issue the direct final rule. Consequently, any
10 CFR part 72 general licensee that seeks to load spent nuclear fuel
into the Holtec International HI-STORM 100 Cask System in accordance
with the changes described in proposed Renewed Amendment No. 18 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 Renewed Amendment No. 18 to Certificate of Compliance
No. 1014 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 100
Cask System Certificate of Compliance No. 1014, Renewed Amendment No.
18,'' will not have a
[[Page 72307]]
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 (10 CFR
2.810).
XI. Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent nuclear fuel under a
general license in cask designs approved by the NRC. Any nuclear power
reactor licensee can use NRC-approved cask designs to store spent
nuclear fuel if (1) it notifies the NRC in advance; (2) the spent fuel
is stored under the conditions specified in the cask's certificate of
compliance; and (3) the conditions of the general license are met. A
list of NRC-approved cask designs is contained in Sec. 72.214. On May
1, 2000 (65 FR 25241), the NRC issued an amendment to 10 CFR part 72
that approved the Holtec International HI-STORM 100 Cask Design system
by adding it to the list of NRC-approved cask designs in Sec. 72.214.
On December 15, 2021, and as supplemented on September 2, 2022, May
26, 2023, September 8, 2023, December 4, 2023, January 18, 2024, and
February 15, 2024, Holtec International submitted a request to amend
the Holtec International HI-STORM 100 Cask Design system, as described
in Section IV, ``Discussion of Changes,'' of this document.
The alternative to this action is to withhold approval of Renewed
Amendment No. 18 and to require any 10 CFR part 72 general licensee
seeking to load spent nuclear fuel into the Holtec International HI-
STORM 100 Cask System design under the changes described in Renewed
Amendment No. 18 to request an exemption from the requirements of
Sec. Sec. 72.212 and 72.214. Under this alternative, each interested
10 CFR part 72 licensee would have to prepare, and the NRC would have
to review, a separate exemption request, thereby increasing the
administrative burden upon the NRC and the costs to each licensee.
Approval of this direct final rule is consistent with previous NRC
actions. Further, as documented in the preliminary safety evaluation
report and environmental assessment, this direct final rule will have
no adverse effect on public health and safety or the environment. This
direct final rule has no significant identifiable impact or benefit on
other government agencies. Based on this regulatory analysis, the NRC
concludes that the requirements of this direct final rule are
commensurate with the NRC's responsibilities for public health and
safety and the common defense and security. No other available
alternative is believed to be as satisfactory; therefore, this action
is recommended.
XII. Backfitting and Issue Finality
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 Certificate of Compliance No.
1014 for the Holtec International HI-STORM 100 Cask System design, as
currently listed in Sec. 72.214. The amendment consists of the changes
in Renewed Amendment No. 18 previously described, as set forth in the
amended certificate of compliance and technical specifications.
Renewed Amendment No. 18 to Certificate of Compliance No. 1014 for
the Holtec International HI-STORM 100 Cask System design was initiated
by Holtec International and was not submitted in response to new NRC
requirements, or an NRC request for amendment. Renewed Amendment No. 18
applies only to new casks fabricated and used under Renewed Amendment
No. 18. These changes do not affect existing users of the Holtec
International HI-STORM 100 Cask System design, and previously issued
renewed amendments continue to be effective for existing users. While
current users of this storage system may comply with the new
requirements in Renewed Amendment No. 18, this would be a voluntary
decision on the part of current users.
For these reasons, Renewed Amendment No. 18 to Certificate of
Compliance No. 1014 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.
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.
------------------------------------------------------------------------
ADAMS accession No./ Federal
Document Register citation
------------------------------------------------------------------------
Proposed Certificate of Compliance, Proposed Technical Specifications,
and Preliminary Safety Evaluation Report for Certificate of Compliance
No. 1014, Renewed Amendment No. 18
------------------------------------------------------------------------
User Need Rulemaking Package for ML24095A039 (package).
Certificate of Compliance No.
1014, HI-STORM 100 Cask System,
Renewed Amendment No. 18.
------------------------------------------------------------------------
Environmental Documents
------------------------------------------------------------------------
Environmental Assessment for ML051230231.
Proposed Rule Entitled, ``Storage
of Spent Nuclear Fuel in NRC-
Approved Storage Casks at Nuclear
Power Reactor Sites.'' (1989).
[[Page 72308]]
``Environmental Assessment and ML100710441.
Finding of No Significant Impact
for the Final Rule Amending 10
CFR Part 72 License and
Certificate of Compliance Terms''
(2010).
Generic Environmental Impact ML14198A440 (package).
Statement for Continued Storage
of Spent Nuclear Fuel: Final
Report (NUREG-2157, Volumes 1 and
2) (2014).
``Storage of Spent Fuel In NRC- 55 FR 29181.
Approved Storage Casks at Power
Reactor Sites'' Final Rule (July
18, 1990).
------------------------------------------------------------------------
Holtec International HI-STORM 100 Cask Design System Amendment No. 18
Request Documents
------------------------------------------------------------------------
Holtec International, Submittal of ML21349B418 (package).
HI-STORM 100 Request for
Amendment No. 18, dated December
15, 2021.
Holtec International, HI-STORM 100 ML22245A103 (package).
Amendment No. 18 Responses to
Requests for Supplemental
Information, dated September 2,
2022.
Holtec International--Submittal of ML23146A138 (package).
RAI Responses on HI-STORM 100
Amendment No. 18, dated May 26,
2023.
Holtec International, Submittal of ML23251A250 (package).
Supplement to RAI Responses on HI-
STORM 100 Amendment No. 18, dated
September 8, 2023.
Holtec International, Submittal of ML23338A304 (package).
Supplement to RAI Responses on HI-
STORM 100 Amendment No. 18, dated
December 4, 2023.
Holtec Report No. HI-2200343-A, ML24018A198 (package).
``Topical Report for Allowance of
Heat Load Patterns in HI-STORM
100 and HI-STORM FW Systems''
(January 18, 2024).
Holtec International, Submittal of ML24046A254 (package).
Supplement to RAI Responses on HI-
STORM 100 Amendment No. 18, dated
February 15, 2024.
------------------------------------------------------------------------
Other Documents
------------------------------------------------------------------------
``Agreement State Program Policy 82 FR 48535.
Statement; Correction'' (October
18, 2017).
Plain Language in Government 63 FR 31885.
Writing, dated June 10, 1998.
Storage of Spent Fuel In NRC- 55 FR 29181.
Approved Storage Casks at Power
Reactor Sites: Final Rule, dated
July 18, 1990.
List of Approved Spent Fuel 65 FR 25241.
Storage Casks: Holtec HI-STORM
100 Addition, dated May 1, 2000.
------------------------------------------------------------------------
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-2024-0105. 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-2024-0105); (2) click
the ``Subscribe'' link; and (3) enter an email address and click on the
``Subscribe'' link.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Indians,
Intergovernmental relations, Nuclear energy, Penalties, Radiation
protection, Reporting and recordkeeping requirements, Security
measures, Spent fuel, Whistleblowing.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended; the Energy Reorganization
Act of 1974, as amended; the Nuclear Waste Policy Act of 1982, as
amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following
amendments to 10 CFR part 72:
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
0
1. The authority citation for part 72 continues to read as follows:
Authority: Atomic Energy Act of 1954, secs. 51, 53, 57, 62, 63,
65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42
U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2210e,
2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C.
5841, 5842, 5846, 5851); National Environmental Policy Act of 1969
(42 U.S.C. 4332); Nuclear Waste Policy Act of 1982, secs. 117(a),
132, 133, 134, 135, 137, 141, 145(g), 148, 218(a) (42 U.S.C.
10137(a), 10152, 10153, 10154, 10155, 10157, 10161, 10165(g), 10168,
10198(a)); 44 U.S.C. 3504 note.
0
2. In Sec. 72.214, Certificate Number 1014 is revised to read as
follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1014.
Initial Certificate Effective Date: May 31, 2000, superseded by
Renewed Initial Certificate Effective Date: August 2, 2023.
Amendment Number 1 Effective Date: July 15, 2002, superseded by
Renewed Amendment Number 1 Effective Date: August 2, 2023.
Amendment Number 2 Effective Date: June 7, 2005, superseded by
Renewed Amendment Number 2 Effective Date: August 2, 2023.
Amendment Number 3 Effective Date: May 29, 2007, superseded by
Renewed Amendment Number 3 Effective Date: August 2, 2023.
Amendment Number 4 Effective Date: January 8, 2008, superseded by
Renewed Amendment Number 4 Effective Date: August 2, 2023.
Amendment Number 5 Effective Date: July 14, 2008, superseded by
Renewed Amendment Number 5 Effective Date: August 2, 2023.
Amendment Number 6 Effective Date: August 17, 2009, superseded by
Renewed Amendment Number 6 Effective Date: August 2, 2023.
Amendment Number 7 Effective Date: December 28, 2009, superseded by
Renewed Amendment Number 7 Effective Date: August 2, 2023.
Amendment Number 8 Effective Date: May 2, 2012, as corrected on
November 16, 2012 (ADAMS Accession No. ML12213A170); superseded by
Amendment Number 8, Revision 1, Effective Date: February 16, 2016;
superseded by Renewed Amendment Number 8, Revision 1 Effective Date:
August 2, 2023.
Amendment Number 9 Effective Date: March 11, 2014, superseded by
Amendment Number 9, Revision 1, Effective Date: March 21, 2016, as
corrected on August 25, 2017 (ADAMS Accession No. ML17236A451);
[[Page 72309]]
superseded by Renewed Amendment Number 9, Revision 1 Effective Date:
August 2, 2023.
Amendment Number 10 Effective Date: May 31, 2016, as corrected on
August 25, 2017 (ADAMS Accession No. ML17236A452); superseded by
Renewed Amendment Number 10 Effective Date: August 2, 2023.
Amendment Number 11 Effective Date: February 25, 2019, as corrected
(ADAMS Accession No. ML19343B024); superseded by Renewed Amendment
Number 11 Effective Date: August 2, 2023.
Amendment Number 12 Effective Date: February 25, 2019, as corrected
on May 30, 2019 (ADAMS Accession No. ML19109A111); further corrected
December 23, 2019 (ADAMS Accession No. ML19343A908); superseded by
Renewed Amendment Number 12 Effective Date: August 2, 2023.
Amendment Number 13 Effective Date: May 13, 2019, as corrected on
May 30, 2019 (ADAMS Accession No. ML19109A122); further corrected
December 23, 2019 (ADAMS Accession No. ML19343B156); superseded by
Renewed Amendment Number 13 Effective Date: August 2, 2023.
Amendment Number 14 Effective Date: December 17, 2019, as corrected
(ADAMS Accession No. ML19343B287); superseded by Renewed Amendment
Number 14 Effective Date: August 2, 2023.
Amendment Number 15 Effective Date: June 14, 2021, superseded by
Renewed Amendment Number 15 Effective Date: August 2, 2023.
Renewed Amendment Number 16 [Reserved].
Renewed Amendment Number 17 Effective Date: January 16, 2024.
Renewed Amendment Number 18 Effective Date: November 19, 2024.
Safety Analysis Report (SAR) Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask
System.
Docket Number: 72-1014.
Certificate Expiration Date: May 31, 2020.
Renewed Certificate Expiration Date: May 31, 2060.
Model Number: HI-STORM 100.
* * * * *
Dated: August 22, 2024.
For the Nuclear Regulatory Commission.
Mirela Gavrilas,
Executive Director for Operations.
[FR Doc. 2024-19801 Filed 9-4-24; 8:45 am]
BILLING CODE 7590-01-P