[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
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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.

-----------------------------------------------------------------------

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).
---------------------------------------------------------------------------

    \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)).
---------------------------------------------------------------------------

    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.

------------------------------------------------------------------------
                                             Adams Accession No./Federal
                  Document                        Register citation
------------------------------------------------------------------------
  Renewed Certificate of Compliance No. 1014, HI-STORM 100 Cask System
                                 Design
------------------------------------------------------------------------
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.
------------------------------------------------------------------------

[[Page 42591]]

 
                          Rulemaking Documents
------------------------------------------------------------------------
``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.
------------------------------------------------------------------------
                         Environmental Documents
------------------------------------------------------------------------
Generic Environmental Impact Statement for   ML14198A440 (package).
 Continued Storage of Spent Nuclear Fuel:
 Final Report (NUREG-2157, Volumes 1 and 2)
 (2014).
------------------------------------------------------------------------
                             Other Documents
------------------------------------------------------------------------
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