[Federal Register Volume 88, Number 126 (Monday, July 3, 2023)]
[Rules and Regulations]
[Pages 42587-42592]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-13992]
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Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
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Federal Register / Vol. 88, No. 126 / Monday, July 3, 2023 / Rules
and Regulations
[[Page 42587]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2022-0109]
RIN 3150-AK86
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewal
of Initial Certificate and Amendment Nos. 1 Through 15; Correction
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule; correction and announcement of effective
date.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is correcting and
announcing the effective date for the direct final rule that was
published in the Federal Register on February 13, 2023. The direct
final rule renews the initial certificate (Amendment 0) and Amendment
Nos. 1 through 15 of the Holtec International HI-STORM 100 Certificate
of Compliance No. 1014 for 40 years and revises the certificate of
compliance's conditions and technical specifications to address aging
management activities related to the structures, systems, and
components important to safety of the dry storage system to ensure that
these will maintain their intended functions during the period of
extended storage operations.
DATES: The effective date of the direct final rule published February
13, 2023 (88 FR 9106), which was delayed indefinitely on April 26, 2023
(88 FR 25271), is August 2, 2023, and the correction set out at the end
of this document is effective August 2, 2023.
ADDRESSES: Please refer to Docket ID NRC-2022-0109 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-2022-0109. Address
questions about NRC dockets to Dawn Forder; telephone: 301-415-3407;
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 Web-based ADAMS
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: You may examine and purchase copies of public
documents, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Maryland 20852. 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.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room P1-B35, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Kristina Banovac, Office of Nuclear
Materials Safety and Safeguards, telephone: 301-415-7116, email:
[email protected] and James Firth, Office of Nuclear Materials
Safety and Safeguards, telephone: 301-415-6628, email:
[email protected]. Both are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Discussion
On February 13, 2023 (88 FR 9106), the NRC published a direct final
rule amending its regulations in part 72 of title 10 of the Code of
Federal Regulations (10 CFR) to revise the Holtec International HI-
STORM 100 Cask System listing within the ``List of approved spent fuel
storage casks'' to renew the initial certificate (Amendment No. 0) and
Amendment Nos. 1 through 15 to Certificate of Compliance No. 1014. The
renewal of the initial certificate and Amendment Nos. 1 through 15 for
40 years revised the certificate of compliance's conditions and
technical specifications to address aging management activities related
to the structures, systems, and components important to safety of the
dry storage system to ensure that these will maintain their intended
functions during the period of extended storage operations.
In the direct final rule, published on February 13, 2023, the NRC
stated that if no significant adverse comments were received, the
direct final rule would become effective on May 1, 2023. The comment
period closed on March 15, 2023; however, on March 22, 2023, in
response to requests for an extension of the public comment period, the
NRC reopened the public comment period to allow the public more time to
comment on the action (88 FR 17164). The re-opened comment period
closed on April 14, 2023. On April 26, 2023 (88 FR 25271), the NRC
published a document that indefinitely delayed the effective date of
the direct final rule to provide the NRC staff sufficient time to
evaluate and respond to public comments.
The NRC received eight comment submissions on the companion
proposed rule published on February 13, 2023 (88 FR 9195). The comments
were submitted by four individuals, and a joint comment was provided on
behalf of five nongovernmental organizations. An electronic copy of the
comment submissions can be obtained from the Federal rulemaking website
https://www.regulations.gov under Docket ID NRC-2022-0109. The comments
are also available in ADAMS using the Accession numbers shown in the
table in the ``Availability of Documents'' section of this document.
The NRC binned the comments by topic and evaluated the comments
using the criteria stated in the direct final rule. The NRC is
providing a response to the comments in section II. of this document,
``Public Comment Responses.'' Some comments were not
[[Page 42588]]
unique to this action, in that they raised issues the NRC has addressed
in previous spent fuel storage actions, (e.g., guidance for evaluating
the aging management programs). Other comments were on topics that are
outside of the scope of this rulemaking, such as transportation, cask
design bases, and storage at a consolidated interim storage facility.
In addition, some comments pertain to the regulations in 10 CFR part 72
rather than the safety of the Holtec International HI-STORM 100 Cask
System design and are also outside of the scope of this rulemaking.
For ease of reference, the criteria for a significant adverse
comment are repeated here:
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.
The NRC evaluated the comments against these criteria and
determined that the public comments received on this action did not
warrant any additions or changes (other than editorial) to the final
rule, the certificates of compliance, or the accompanying technical
specifications. The NRC is not making substantive changes to the rule;
it is apparent that the rule is effective and acceptable as proposed,
without the need for a substantive change or addition. The comments did
not raise a relevant issue that was not previously addressed or
considered by the NRC, and the comments did not cause the NRC to
either: (1) reevaluate or reconsider its position, or (2) conduct
additional analyses.
The NRC has determined that none of the comments were significant
adverse comments. Therefore, the NRC is correcting and confirming the
direct final rule amending the listing for Certificate of Compliance
No. 1014, the Holtec International HI-STORM 100 Cask System design, to
renew the NRC's approval of the certificate of compliance and is
announcing the effective date.
II. Public Comment Responses
Comment: The joint comment raised concerns regarding the transport
of storage canisters under 10 CFR part 71.
Response: This rulemaking only applies to the use of the Holtec
International HI-STORM 100 Cask System design in an independent spent
fuel storage installation at power reactor sites. The use of a
component of the Holtec International HI-STORM 100 Cask System design--
the multi-purpose canister--in transportation, would fall under NRC's
regulations in 10 CFR part 71, which is outside of the scope of this
rulemaking. Allowing the Holtec International HI-STORM 100 Cask System
design to be used for the storage of spent fuel under the general
license issued by 10 CFR 72.210 neither affects nor contributes to the
evaluation of its use during transportation.
Comment: The joint comment re-submitted a comment that had
previously been submitted to the NRC on the Interim Storage Partners
Consolidated Interim Storage Facility Project Draft Environmental
Impact Statement regarding the need to consider the foreseeable
environmental impacts of the entire project, including transporting
spent nuclear fuel to and from the proposed Consolidated Interim
Storage Facility in Texas.
Response: This rulemaking action only approves the use of the
Holtec International HI-STORM 100 Cask System design under the renewed
Certificate of Compliance No. 1014 for the initial certificate
(Amendment No. 0) and Amendment Nos. 1 through 15 under the general
license issued by 10 CFR 72.210, which involves the storage of spent
nuclear fuel in an independent spent fuel storage installation at power
reactor sites. This does not include the use of the Holtec
International HI-STORM 100 Cask System design at a consolidated interim
storage facility. This comment is outside the scope of this rulemaking.
Additionally, the use of a Holtec International HI-STORM 100 Cask
System design at a consolidated interim storage facility would be
authorized under a specific license and, before such approval would be
granted, there would be an opportunity to request a hearing and to
petition to intervene.
Comment: Three comments raised concerns regarding the design bases
for the Holtec International HI-STORM 100 Cask System design.
Response: Pursuant to 10 CFR part 72, the design bases for a cask
system design include reference bounds for the design and analyses of
postulated accidents caused by severe natural events and severe human-
induced events. The renewal of the Holtec International HI-STORM 100
Cask System design does not involve reevaluation of the approved design
bases, changes to the approved design bases, nor changes to the
fabrication of the cask system. Rather, the renewal requires aging
management programs to ensure that structures, systems, and components
important to safety will continue to perform their intended functions,
as designed, during the period of extended operation, thus maintaining
the approved design bases during the period of extended operation. The
issue of approved design bases is outside of the scope of this
rulemaking.
Comment: The joint comment objected to the use of the direct final
rule process by the NRC and requested the NRC withdraw the direct final
rule. The comment stated that the direct final rule process was not
appropriate because the rule appears to be controversial and because
the process appears to violate the National Environmental Policy Act of
1969 and the Administrative Procedure Act (APA). The comment noted that
the direct final rule does not fall within the good cause exception in
10 CFR 2.804(d).
Response: The NRC disagrees with this comment. Direct final
rulemaking \1\ is a process for expediting the issuance of
noncontroversial rules and is a variation on section 553 notice-and-
comment rulemaking under the APA. The NRC issued a direct final rule
and a companion proposed rule in the same issue of the Federal Register
and requested public comment. In the NRC's description of the direct
final rulemaking process, the NRC explains that a direct final rule,
while not explicitly delineated by the APA, does comply with the APA
and includes all of the essential elements of rulemaking required by
the APA. In this rulemaking, the NRC has provided
[[Page 42589]]
notice and opportunity for comment; a statement of basis and purpose;
and publication of the rule not less than 30 days prior to its
effective date (see, https://www.nrc.gov/about-nrc/regulatory/rulemaking/rulemaking-process/direct-final-rule.html).
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\1\ The Administrative Conference of the United States (ACUS)
has endorsed the use of the direct final rule process as a means for
expediting rulemaking (see ACUS Recommendation 95-4, ``Procedures
for Non-Controversial and Expedited Rulemaking'' (60 FR 43110;
August 18, 1995)).
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The NRC's requirements at 10 CFR part 72 currently list 15 approved
certificates of compliance for spent fuel storage casks. NRC has
conducted rulemaking to renew six of these certificates of compliance.
All six certificate of compliance renewals included aging management
programs and involved 40-year terms. The Agency considers these prior
rulemaking actions to be non-controversial because the NRC either did
not receive any comments opposing the renewals or did not receive any
significant adverse comments. The NRC's decision to use the direct
final rulemaking process for the renewal of Certificate of Compliance
No. 1014 (Holtec International HI-STORM 100 Cask System design) was
based on this experience.
Additionally, this rulemaking did adhere to the requirements of the
National Environmental Policy Act of 1969. In the direct final rule,
the NRC published an environmental assessment and a final finding of no
significant impact. The NRC previously considered the impacts from the
continued storage of spent fuel, including in the Generic Environmental
Impact Statement for Continued Storage of Spent Nuclear Fuel: Final
Report (NUREG-2157, Volumes 1 and 2) (2014).
Comment: One commenter requested the NRC make all the renewed
amendments expire on the same day. The commenter noted the expiration
dates for the early certificates (i.e., the initial certificate
(Amendment No. 0) and Amendment Nos. 1 through 6) have an expiration
date of June 1, 2020; however, the later Amendment certificates have an
expiration date of May 31, 2020.
Response: The NRC agrees with this comment regarding an editorial
issue. This change has no substantive effect on the requirements;
because this comment is limited to editorial changes that do not affect
the renewal of the certificate of compliance, it is not considered to
be a significant adverse comment. The NRC has made editorial
corrections to the certificates of compliance in response to this
comment.
Comment: The NRC received two comments on the topic of NRC's
generic technical basis for canister cracking, the canister aging
management program, and the need for periodic reviews and updates to
the aging management programs based on new information from research
and operating experience. The NRC also received a comment stating that
NRC should track the U.S. Department of Energy's (DOE's) research
efforts in this area and that the DOE's ongoing research does not
support the NRC conclusions in its Safety Evaluation Report. This
comment also noted that comparing the applicant's aging management
program elements to program elements developed by industry does not
constitute sufficient due diligence by NRC.
Response: The NRC previously considered and addressed these
concerns during the development of its general technical basis for
canister aging management. The NRC established a generic technical
basis for the safety review of storage renewal applications through
guidance in NUREG-2214, ``Managing Aging Processes in Storage (MAPS)
Report.'' NUREG-2214 establishes a generic technical basis in terms of
the evaluation of (1) aging mechanisms and effects that could affect
the ability of structures, systems, and components important to safety
to fulfill their safety functions in the period of extended operation
(i.e., credible aging mechanisms and effects) and (2) aging management
approaches to address credible aging effects, including examples of
aging management programs that are considered generically acceptable to
address the credible aging effects to ensure that the design bases will
be maintained in the period of extended operation.
The NRC sought public input during development of NUREG-2214 and
related guidance. The NRC responded to the public comments on the draft
guidance and finalized the guidance after considering the comments
provided by the public. The NRC issued its responses at the time it
announced the issuance of NUREG-2214 (84 FR 39022; August 8, 2019),
NUREG-1927, Revision 1, ``Standard Review Plan for Renewal of Specific
Licenses and Certificates of Compliance for Dry Storage of Spent
Nuclear Fuel'' (81 FR 44054; July 6, 2016), and NUREG-2224, ``Dry
Storage and Transportation of High Burnup Spent Nuclear Fuel'' (85 FR
77267; December 1, 2020). The comments submitted on this rulemaking did
not provide new information that was not previously considered during
the development of this NRC guidance.
The NRC disagrees with the commenter's assertion about the
significance of ongoing research and the extent to which it supports or
contradicts NRC staff conclusions. This ongoing research is compatible
with the NRC's conclusions in the NRC's Safety Evaluation Report. The
NRC has conducted and continues to conduct research associated with
stress corrosion cracking and coordinates its research efforts with DOE
in this area. In addition, the NRC collaborates with DOE and national
counterparts, consensus committees, industry, and international
partners to share research, knowledge, and operating experience related
to degradation and aging of cask systems. The NRC considers this pool
of information in its regulatory framework for spent fuel storage.
The NRC recognizes that there will be new information gained in the
period of extended operation, including operating experience and
findings from research and development. Therefore, as described in
NUREG-1927, NUREG-2214, and Regulatory Guide 3.76, ``Implementation of
Aging Management Requirements for Spent Fuel Storage Renewals'' (86 FR
38506; July 21, 2021), aging management programs include learning
aspects designed to appropriately address and respond to new
information. These learning programmatic features are called
``tollgates,'' which offer a structured approach for: (1) periodically
reviewing site-specific and industrywide operating experience and data
from applicable research and industry initiatives at specific times
during the period of extended operation; and (2) performing a safety
assessment that confirms the program's effectiveness or otherwise
identifies a need to enhance or modify the program in a timely manner
to address any emerging aging issues.
As aging management inspections of canisters are performed at
independent spent fuel storage installations, licensees and certificate
of compliance holders will upload the inspection results to the
Independent Spent Fuel Storage Installation Aging Management Institute
of Nuclear Power Operations Database (AMID), and this operating
experience will be shared across the industry through licensee access
to this database by the independent spent fuel storage installation
sites and by certificate of compliance holders. The implementation of
tollgate assessments and use of AMID provides reasonable assurance that
the aging management programs will continue to effectively manage aging
effects during the period of extended operation.
The NRC disagrees with the commenter's statement regarding the
comparison of the applicant's aging management program elements to
program elements developed by industry. During the NRC's review of
Holtec International's renewal application for the HI-STORM 100 Cask
System design, the NRC evaluated
[[Page 42590]]
Holtec International's technical basis for its aging management review
and aging management programs and compared it to the generic technical
basis in NUREG-2214. The generic technical basis in NUREG-2214 was
developed by the NRC, not by the industry. The guidance in NUREG-2214
provides examples of aging management programs that are considered
generically acceptable to address the credible aging mechanisms
evaluated in the guidance to ensure that the design bases of the cask
system will be maintained in the period of extended operation. The NRC
found the Holtec International aging management program acceptable. The
NRC Safety Evaluation Report documents the consistency between the
applicant's canister aging management program and the NUREG-2214
canister aging management program.
Comment: The NRC received two comments regarding scratching and
cracking of canisters. The first comment, from the joint comments,
stated that NRC has not reviewed the long-term impact of the scraping,
gouging, and scratching of canisters when they are loaded into the
casks, including the potential for increased and accelerated corrosion.
The second comment noted that the Holtec International HI-STORM 100
Cask System design above ground system may cause canisters to scratch
and scrape against the carbon steel vertical channels in the overpack
cask, leading to potential initiation of carbon[hyphen]induced pit
corrosion cracking and a serious accelerated canister degradation
condition.
Response: The comments on the topic of scratching and cracking of
canisters do not introduce new information that was not already
considered during the NRC's development of NUREG-2214 and during the
review of Holtec International's renewal application for the Holtec HI-
STORM 100 Cask System design. Welded stainless steel dry storage
canisters, like those used in the HI-STORM 100 Cask System design, may
contact dissimilar metal surfaces, and may get scraped, scratched, or
gouged during handling and loading into the storage overpack. During
the development of NUREG-2214, the NRC considered these potential
effects and the potential for handling practices to result in the
contact and transfer of carbon steel onto the surface of the stainless-
steel canister.
NUREG-2214 identifies stress corrosion cracking as a credible aging
effect for canisters and includes an aging management program for
canisters to identify and manage localized corrosion (a potential
precursor to stress corrosion cracking) and stress corrosion cracking.
NUREG-2214 notes the potential for handling practices to result in
contact and transfer of iron (i.e., carbon steel) onto the stainless-
steel canister surface, which can create localized corrosion. The
NUREG-2214 canister aging management program addresses aging effects
and provides reasonable assurance that aging associated with any
initial defects, scrapes, or effects of dissimilar materials being in
contact will not compromise the intended functions of the canister
during the period of extended operation.
NUREG-2214 provides examples of aging management programs that the
NRC considers as being generically acceptable to address those credible
aging mechanisms evaluated in the guidance to ensure that the design
bases of dry storage systems will be maintained. In its review of the
renewal application for the Holtec International HI-STORM 100 Cask
System design, the NRC staff evaluated Holtec International's technical
basis for its aging management review and aging management programs for
the Holtec International HI-STORM 100 Cask System design and compared
it to the generic technical basis in NUREG-2214. The NRC Safety
Evaluation Report documents the consistency between the applicant's
canister aging management program and the NUREG-2214 canister aging
management program. Consistent with the NUREG-2214 canister aging
management program, the Holtec International HI-STORM 100 Cask System
design canister aging management program includes inspections of
canister surfaces to identify the presence of red-orange corrosion
deposits that may indicate iron transfer onto the stainless-steel
canister surface. Any areas of corrosion that are found and identified
are subject to additional examination and evaluation.
Additionally, the Holtec International HI-STORM 100 Cask System
design canister aging management program includes criteria to inspect
those canisters that are most susceptible to degradation. The aging
management program for the Holtec International HI-STORM 100 Cask
System design considers the susceptibility criteria in Electric Power
Research Institute (EPRI) TR-3002005371, ``Susceptibility Assessment
Criteria for Chloride-Induced Stress Corrosion Cracking (CISCC) of
Welded Stainless-Steel Canisters for Dry Cask Storage Systems''
(referenced also in NUREG-2214). The EPRI report identifies areas of
``mechanical damage (e.g., gouges)'' and ``scraping during handling''
as being the most susceptible to aging. The concerns expressed in the
comments (i.e., long-term effects of any scraping, gouging, and
scratching of canisters or contact between dissimilar materials when
canisters are loaded into the storage overpack including the potential
for increased and accelerated corrosion) are addressed in the canister
aging management program.
Comment: The joint comment expressed concern with radiation effects
and dose limits.
Response: This comment raises issues that are outside of the scope
of this rulemaking. The NRC establishes safety standards for protection
against radiation, including public dose limits, in 10 CFR part 20,
``Standards for Protection against Radiation.'' The regulations in 10
CFR part 72 also include dose limits for spent fuel storage. The
current requirements in 10 CFR parts 20 and 72 are protective of public
health and safety and the environment.
III. Availability of Documents
The documents identified in this table are available to interested
persons through one or more of the following methods, as indicated.
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Adams Accession No./Federal
Document Register citation
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Renewed Certificate of Compliance No. 1014, HI-STORM 100 Cask System
Design
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Renewal of Certificate of Compliance No. ML23068A384 (package).
1014, HI-STORM 100 Cask System. (Includes
Renewed Certificates of Compliance;
Approved Contents and Design Features;
Technical Specifications; and Final Safety
Evaluation Report).
Final Safety Evaluation Report for the HI- ML23068A455.
STORM 100 Cask System: Certificate of
Compliance No. 1014 Renewal, Docket No. 72-
1014.
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[[Page 42591]]
Rulemaking Documents
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``List of Approved Spent Fuel Storage 88 FR 9106.
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 Through 15.'' Direct
final rule. (Includes environmental
assessment and final finding of no
significant impact) (February 13, 2023).
``List of Approved Spent Fuel Storage 88 FR 9195.
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 Through 15.'' Proposed
rule. (February 13, 2023).
``List of Approved Spent Fuel Storage 88 FR 17164.
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 Through 15;'' Proposed
rule; Reopening of comment period. (March
22, 2023).
``List of Approved Spent Fuel Storage 88 FR 25271.
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 Through 15; Delay of
Effective Date.'' Direct final rule; Delay
of effective date. (April 26, 2027).
Comment (001) from Brian Gutherman on PR- ML23046A406.
72--List of Approved Spent Fuel Storage
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment (002) from Renante Baniaga on PR- ML23046A407.
72--List of Approved Spent Fuel Storage
Casks: Holtec International HI-STORM 100
Cask System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment (003) from Michael Ford on PR-72-- ML23073A116.
List of Approved Spent Fuel Storage Casks:
Holtec International HI-STORM 100 Cask
System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment (004) from Kalene Walker on PR-72-- ML23075A156.
List of Approved Spent Fuel Storage Casks:
Holtec International HI-STORM 100 Cask
System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment Period Extension Request from ML23073A095.
Nuclear Information and Resource Service,
et al. on PR-72--List of Approved Spent
Fuel Storage Casks: Holtec International
HI-STORM 100 Cask System, Certificate of
Compliance No. 1014, Renewal of Initial
Certificate and Amendment Nos. 1 through
15.
Comment (005) from Nuclear Information and ML23107A144.
Resource Service, et al. on PR-72--List of
Approved Spent Fuel Storage Casks: Holtec
International HI-STORM 100 Cask System,
Certificate of Compliance No. 1014,
Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment (006) from Michael Ford on PR-72-- ML23108A278.
List of Approved Spent Fuel Storage Casks:
Holtec International HI-STORM 100 Cask
System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
Comment (007) from Kalene Walker on PR-72-- ML23108A279.
List of Approved Spent Fuel Storage Casks:
Holtec International HI-STORM 100 Cask
System, Certificate of Compliance No.
1014, Renewal of Initial Certificate and
Amendment Nos. 1 through 15.
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Environmental Documents
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Generic Environmental Impact Statement for ML14198A440 (package).
Continued Storage of Spent Nuclear Fuel:
Final Report (NUREG-2157, Volumes 1 and 2)
(2014).
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Other Documents
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ACUS Recommendation 95-4, ``Procedures for 60 FR 43110.
Non-Controversial and Expedited
Rulemaking'' (August 18, 1995).
``Standard Review Plan for Renewal of ML16179A148.
Specific Licenses and Certificates of
Compliance for Dry Storage of Spent
Nuclear Fuel.'' NUREG-1927, Revision 1.
Washington, DC. June 2016.
``Managing Aging Processes in Storage ML19214A111.
(MAPS) Report.'' Final Report. NUREG-2214.
Washington, DC. July 2019..
NUREG-2224, ``Dry Storage and ML20191A321.
Transportation of High Burnup Spent
Nuclear Fuel'' (November 2020).
``Implementation of Aging Management 86 FR 38506.
Requirements for Spent Fuel Storage
Renewals.'' Regulatory Guide; Issuance
(July 21, 2021).
Regulatory Guide 3.76, Revision 0, ML21098A022.
``Implementation of Aging Management
Requirements for Spent Fuel Storage
Renewals.'' July 2021.
``Standard Review Plan for Renewal of 81 FR 44054.
Specific Licenses and Certificates of
Compliance for Dry Storage of Spent
Nuclear Fuel.'' NUREG; Issuance. (July 6,
2016).
``Managing Aging Processes in Storage 84 FR 39022.
(MAPS) Report.'' NUREG; Issuance. (August
8, 2019).
``Dry Storage and Transportation of High 85 FR 77267.
Burnup Spent Nuclear Fuel.'' NUREG;
Issuance. (December 1, 2020).
EPRI TR-3002005371, ``Susceptibility https://www.epri.com/
Assessment Criteria for Chloride-Induced research/ products/
Stress Corrosion Cracking (CISCC) of 3002005371.
Welded Stainless-Steel Canisters for Dry
Cask Storage Systems'' (September 18,
2015).
``Direct Final Rule''...................... https://www.nrc.gov/about-nrc/ nrc/ regulatory/rulemaking/
rulemaking-process/
direct-final-rule.html.
------------------------------------------------------------------------
The direct final rule published on February 13, 2023 (88 FR 9106),
which was delayed indefinitely on April 26, 2023 (88 FR 25271), is
confirmed. The direct final rule is effective on August 2, 2023, and
the following correction is effective August 2, 2023.
[[Page 42592]]
Correction of Direct Final Rule
0
In FR 2023-03002, published at 88 FR 9106 on February 13, 2023, on page
9116, in the second and third columns, remove the date ``May 1, 2023''
wherever it appears and add ``August 2, 2023'' in its place.
Dated: June 27, 2023.
For the Nuclear Regulatory Commission.
Catherine Haney,
Acting Executive Director for Operations.
[FR Doc. 2023-13992 Filed 6-30-23; 8:45 am]
BILLING CODE 7590-01-P