ML23103A211
| ML23103A211 | |
| Person / Time | |
|---|---|
| Issue date: | 06/27/2023 |
| From: | Catherine Haney NRC/EDO |
| To: | |
| Shared Package | |
| ML23103A202 | List: |
| References | |
| RIN 3150-AK86, NRC-2022-0109 | |
| Download: ML23103A211 (19) | |
Text
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[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 Ini tial Certificate and
Amendment Nos. 1 Through 15; Correction
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule; correction and announcement of effective dat e.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is correcting and
announcing the effective date for the direct final rule that wa s 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 Int ernational
HI-STORM 100 Certificate of Compliance No. 1014 for 40 years an d revises the
certificate of compliances conditions and technical specificat ions to address aging
management activities related to the structures, systems, and c omponents important to
safety of the dry storage system to ensure that these will main tain 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
1 August 2, 2023, and the correction set out at the end of this d ocument is effective
August 2, 2023.
ADDRESSES: Please refer to Docket ID NRC2022-0109 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 meth ods:
- Federal Rulemaking Website: Go to https://www.regulations.gov and
search for Docket ID NRC2022-0109. Address questions about NRC dockets to Dawn
Forder; telephone: 301-415-3407; email: Dawn.Forder@nrc.gov. Fo r technical
questions, contact the individuals listed in the FOR FURTHER IN FORMATION
CONTACT section of this document.
- NRCs Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the ADAM S Public
Documents collection at https://www.nrc.gov/reading-rm/adams.ht ml. To begin the
search, select Begin Web-based ADAMS Search. For problems wit h ADAMS, please
contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, at
301-415-4737, or by email to PDR.Resource@nrc.gov. For the conv enience of the
reader, instructions about obtaining materials referenced in th is document are provided
in the Availability of Documents section.
- NRCs PDR: You may examine and purchase copies of public documents, by
appointment, at the NRCs PDR, Room P1 B35, One White Flint Nor th, 11555 Rockville
Pike, Maryland 20852. 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.
- NRCs PDR: You may examine and purchase copies of public documents at
2 the NRCs PDR, Room P1-B35, One White Flint North, 11555 Rockvi lle Pike, Rockville,
Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Kristina Banovac, Office of Nuclear
Materials Safety and Safeguards, telephone: 301-415-7116, email :
Kristina.Banovac@nrc.gov and James Firth, Office of Nuclear Mat erials Safety and
Safeguards, telephone: 301-415-6628, email: James.Firth@nrc.gov. 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 f inal 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 S ystem listing within
the List of approved spent fuel storage casks to renew the in itial certificate
(Amendment No. 0) and Amendment Nos. 1 through 15 to Certificat e of Compliance
No. 1014. The renewal of the initial certificate and Amendment Nos. 1 through 15 for
40 years revised the certificate of compliances 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 ens ure 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 N RC stated that if no
significant adverse comments were received, the direct final ru le would become effective
on May 1, 2023. The comment period closed on March 15, 2023; ho wever, on
3 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 close d on April 14, 2023.
On April 26, 2023 (88 FR 25271), the NRC published a document t hat 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 pro posed 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 ca n be obtained from the
Federal rulemaking website https://www.regulations.gov under Do cket ID NRC2022-
0109. The comments are also available in ADAMS using the Access ion 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. So me comments were not
unique to this action, in that they raised issues the NRC has a ddressed 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 consolidate d 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 des ign and are also
outside of the scope of this rulemaking.
For ease of reference, the criteria for a significant adverse c omment are repeated
here:
A significant adverse comment is a comment where the commenter explains why
4 the rule would be inappropriate, including challenges to the ru les underlying premise or
approach, or would be ineffective or unacceptable without a cha nge. A comment is
adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficie nt to require a
substantive response in a notice-and-comment process. For examp le, a substantive
response is required when:
(a) The comment causes the NRC to reevaluate (or reconsider) it s position or
conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a sub stantive
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, a nd it is apparent
that the rule would be ineffective or unacceptable without inco rporation of the change or
addition.
(3) The comment causes the NRC to make a change (other than edi torial) to the
rule, certificate of compliance, or technical specifications.
The NRC evaluated the comments against these criteria and deter mined that the
public comments received on this action did not warrant any add itions or changes (other
than editorial) to the final rule, the certificates of complian ce, or the accompanying
technical specifications. The NRC is not making substantive cha nges 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 re levant issue that was
not previously addressed or considered by the NRC, and the comm ents did not cause
the NRC to either: 1) reevaluate or reconsider its position, or 2) conduct additional
analyses.
5 The NRC has determined that none of the comments were significa nt adverse
comments. Therefore, the NRC is correcting and confirming the d irect final rule
amending the listing for Certificate of Compliance No. 1014, th e Holtec International
HISTORM 100 Cask System design, to renew the NRCs approval of th e 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 Interna tional
HISTORM 100 Cask System design in an independent spent fuel stora ge installation at
power reactor sites. The use of a component of the Holtec Inter national HISTORM 100
Cask System designthe multi-purpose canisterin transportation, would fall under
NRCs regulations in 10 CFR part 71, which is outside of the sc ope of this rulemaking.
Allowing the Holtec International HI-STORM 100 Cask System desi gn to be used for the
storage of spent fuel under the general license issued by 10 CF R 72.210 neither affects
nor contributes to the evaluation of its use during transportat ion.
Comment: The joint comment re-submitted a comment that had previously been
submitted to the NRC on the Interim Storage Partners Consolidat ed Interim Storage
Facility Project Draft Environmental Impact Statement regarding the need to consider the
foreseeable environmental impacts of the entire project, includ ing transporting spent
nuclear fuel to and from the proposed Consolidated Interim Stor age Facility in Texas.
Response: This rulemaking action only approves the use of the Holtec
International HISTORM 100 Cask System design under the renewed Certificate of
6 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 Holte c International
HISTORM 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 HISTORM 100 Cask System design at a consolidated interim storage
facility would be authorized under a specific license and, befo re 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 syste m
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 i nvolve reevaluation
of the approved design bases, changes to the approved design ba ses, nor changes to
the fabrication of the cask system. Rather, the renewal require s aging management
programs to ensure that structures, systems, and components imp ortant to safety will
continue to perform their intended functions, as designed, duri ng the period of extended
operation, thus maintaining the approved design bases during th e 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 rul e process
by the NRC and requested the NRC withdraw the direct final rule. The comment stated
7 that the direct final rule process was not appropriate because the rule appears to be
controversial and because the process appears to violate the Na tional 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 excep tion in 10 CFR 2.804(d).
Response: The NRC disagrees with this comment. Direct final rulemaking1 is a
process for expediting the issuance of noncontroversial rules a nd is a variation on
section 553 notice-and-comment rulemaking under the APA. The NR C issued a direct
final rule and a companion proposed rule in the same issue of t he Federal Register and
requested public comment. In the NRCs description of the direc t final rulemaking
process, the NRC explains that a direct final rule, while not e xplicitly 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 n otice 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/a bout-
nrc/regulatory/rulemaking/rulemaking-process/direct-final-rule. html).
The NRCs requirements at 10 CFR part 72 currently list 15 appr oved certificates
of compliance for spent fuel storage casks. NRC has conducted r ulemaking to renew six
of these certificates of compliance. All six certificate of com pliance renewals included
aging management programs and invo lved 40-year terms. The Agenc y considers these
prior rulemaking actions to be non-controversial because the NR C either did not receive
any comments opposing the renewals or did not receive any signi ficant adverse
comments. The NRCs decision to use the direct final rulemaking process for the
renewal of Certificate of Compliance No. 1014 (Holtec Internati onal HISTORM 100
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)).
8 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 expi ration 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, th e 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 t his comment is limited
to editorial changes that do not affect the renewal of the cert ificate 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 th is comment.
Comment: The NRC received two comments on the topic of NRCs generic
technical basis for canister cracking, the canister aging manag ement program, and the
need for periodic reviews and updates to the aging management p rograms 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 En ergys (DOEs)
research efforts in this area and that the DOEs ongoing resear ch does not support the
NRC conclusions in its Safety Evaluation Report. This comment a lso noted that
9 comparing the applicants aging management program elements to program elements
developed by industry does not constitute sufficient due dilige nce by NRC.
Response: The NRC previously considered and addressed these concerns
during the development of its general technical basis for canis ter aging management.
The NRC established a generic techni cal basis for the safety review of storage renewal
applications through guidance in NUREG2214, Managing Aging Processes in Storage
(MAPS) Report. NUREG2214 establishes a generic technical basis in terms of the
evaluation of (1) aging mechanisms and effects that could affec t the ability of structures,
systems, and components important to safety to fulfill their sa fety functions in the period
of extended operation (i.e., credible aging mechanisms and effe cts) and (2) aging
management approaches to address credible aging effects, includ ing 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 NUREG2214 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 N UREG2214 (84 FR
39022; August 8, 2019), NUREG1927, Revision 1, Standard Review Plan for Renewal
of Specific Licenses and Certificates of Compliance for Dry Sto rage of Spent Nuclear
Fuel (81 FR 44054; July 6, 2016), and NUREG2224, Dry Storage and Transportation
of High Burnup Spent Nuclear Fuel (85 FR 77267; December 1, 20 20). The comments
submitted on this rulemaking did not provide new information th at was not previously
considered during the development of this NRC guidance.
The NRC disagrees with the commenters assertion about the sign ificance of
10 ongoing research and the extent to which it supports or contrad icts NRC staff
conclusions. This ongoing research is compatible with the NRCs conclusions in the
NRCs Safety Evaluation Report. The NRC has conducted and conti nues to conduct
research associated with stress corrosion cracking and coordina tes its research efforts
with DOE in this area. In addition, the NRC collaborates with D OE and national
counterparts, consensus committees, industry, and international partners to share
research, knowledge, and operating experience related to degrad ation and aging of cask
systems. The NRC considers this p ool 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 oper ating experience and findings from research and
development. Therefore, as described in NUREG1927, NUREG2214, and Regulatory
Guide 3.76, Implementation of Aging Management Requirements fo r Spent Fuel
Storage Renewals (86 FR 38506; July 21, 2021), aging managemen t programs include
learning aspects designed to appropriately address and respond to new information.
These learning programmatic features are called tollgates, wh ich offer a structured
approach for: (1) periodically reviewing site-specific and indu strywide operating
experience and data from applicable research and industry initi atives at specific times
during the period of extended operation; and (2) performing a s afety assessment that
confirms the programs effectiveness or otherwise identifies a need to enhance or modify
the program in a timely manner to address any emerging aging is sues.
As aging management inspections of canisters are performed at i ndependent
spent fuel storage installations, licensees and certificate of compliance holders will
upload the inspection results to the Independent Spent Fuel Sto rage 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
11 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 co ntinue to effectively
manage aging effects during the period of extended operation.
The NRC disagrees with the commenters statement regarding the comparison of
the applicants aging management program elements to program el ements developed by
industry. During the NRCs review of Holtec Internationals ren ewal application for the
HISTORM 100 Cask System design, the NRC evaluated Holtec Internat ionals technical
basis for its aging management review and aging management prog rams and compared
it to the generic technical basis in NUREG2214. The generic technical basis in
NUREG2214 was developed by the NRC, not by the industry. The guidanc e in
NUREG2214 provides examples of aging management programs that are co nsidered
generically acceptable to address the credible aging mechanisms evaluated in the
guidance to ensure that the design bases of the cask system wil l be maintained in the
period of extended operation. The NRC found the Holtec Internat ional aging
management program acceptable. The NRC Safety Evaluation Report documents the
consistency between the applicants canister aging management p rogram and the
NUREG2214 canister aging management program.
Comment: The NRC received two comments regarding scratching and cracki ng
of canisters. The first comment, from the joint comments, state d that NRC has not
reviewed the long-term impact of the scraping, gouging, and scr atching of canisters
when they are loaded into the casks, including the potential fo r increased and
accelerated corrosion. The second comment noted that the Holtec International
HISTORM 100 Cask System design above ground system may cause cani sters to
12 scratch and scrape against the carbon steel vertical channels i n the overpack cask,
leading to potential initiation of carboninduced pit corrosion cracking and a serious
accelerated canister degradation condition.
Response: The comments on the topic of scratching and cracking of canis ters do
not introduce new information that was not already considered d uring the NRCs
development of NUREG2214 and during the review of Holtec Internationals renewal
application for the Holtec HISTORM 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 surfac es, and may get scraped, scratch ed, or gouged during
handling and loading into the storage overpack. During the deve lopment of
NUREG2214, the NRC considered these potential effects and the potent ial for handling
practices to result in the contact and transfer of carbon steel onto the surface of the
stainless-steel canister.
NUREG2214 identifies stress corrosion cracking as a credible aging e ffect for
canisters and includes an aging management program for canister s to identify and
manage localized corrosion (a potential precursor to stress cor rosion cracking) and
stress corrosion cracking. NUREG2214 notes the potential for handling practices to
result in contact and transfer of iron (i.e., carbon steel) ont o the stainless-steel canister
surface, which can create localized corrosion. The NUREG2214 canister aging
management program addresses aging effects and provides reasona ble 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 ca nister during the period of
extended operation.
NUREG2214 provides examples of aging management programs that the NR C
considers as being generically acceptable to address those cred ible aging mechanisms
13 evaluated in the guidance to ensure that the design bases of dr y storage systems will be
maintained. In its review of the renewal application for the Ho ltec International
HISTORM 100 Cask System design, the NRC staff evaluated Holtec In ternationals
technical basis for its aging management review and aging manag ement programs for
the Holtec International HISTORM 100 Cask System design and compared it to the
generic technical basis in NUREG2214. The NRC Safety Evaluation Report documents
the consistency between the applicants canister aging manageme nt program and the
NUREG-2214 canister aging managemen t program. Consistent with the NUREG2214
canister aging management program, the Holtec International HI STORM 100 Cask
System design canister aging management program includes inspec tions of canister
surfaces to identify the presence of red-orange corrosion depos its that may indicate iron
transfer onto the stainless-steel canister surface. Any areas o f corrosion that are found
and identified are subject to additional examination and evalua tion.
Additionally, the Holtec International HISTORM 100 Cask System design
canister aging management program includes criteria to inspect those canisters that are
most susceptible to degradation. The aging management program f or the Holtec
International HISTORM 100 Cask System design considers the susceptibility crite ria in
Electric Power Research Institute (EPRI) TR-3002005371, Suscep tibility 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., gouge s) 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 load ed into the storage
overpack including the potential for increased and accelerated corrosion) are addressed
14 in the canister aging management program.
Comment: The joint comment expressed concern with radiation effects an d dose
limits.
Response: This comment raises issues that are outside of the scope of t his
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 interes ted persons through
one or more of the following methods, as indicated.
DOCUMENT ADAMS ACCESSION NO. /
FEDERAL REGISTER CITATION Renewed Certificate of Compliance No. 1014, HI STORM 100 Cask System Design
Renewal of Certificate of Compliance No. 1014, ML23068A384 (package)
HISTORM 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-STORM ML23068A455 100 Cask System: Certificate of Compliance No. 1014 Renewal, Docket No. 72-1014 Rulemaking Documents
List of Approved Spent Fuel Storage Casks: 88 FR 9106 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
15 environmental assessment and final finding of no significant impact) (February 13, 2023)
List of Approved Spent Fuel Storage Casks: 88 FR 9195 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 Casks: 88 FR 17164 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 Casks: 88 FR 25271 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 PR72 ML23046A406
- List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 through 15 Comment (002) from Renante Baniaga on PR72 ML23046A407
- List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 through 15 Comment (003) from Michael Ford on PR72 - ML23073A116 List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 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 ML23075A156 List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 through 15 Comment Period Extension Request from Nuclear ML23073A095 Information and Resource Service, et al. on PR72 - List of Approved Spent Fuel Storage Casks: Holtec International HISTORM 100 Cask
16 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 PR72 - List of Approved Spent Fuel Storage Casks: Holtec International HISTORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 through 15.
Comment (006) from Michael Ford on PR72 - ML23108A278 List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 through 15.
Comment (007) from Kalene Walker on PR72 - ML23108A279 List of Approved Spent Fuel Storage Casks:
Holtec International HISTORM 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 (NUREG2157, 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 Specific ML16179A148 Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel. NUREG1927, Revision 1. Washington, DC. June 2016.
Managing Aging Processes in Storage (MAPS) ML19214A111 Report. Final Report. NUREG-2214. Washington, DC. July 2019.
NUREG2224, Dry Storage and Transportation of ML20191A321 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.
17 Standard Review Plan for Renewal of Specific 81 FR 44054 Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel. NUREG; Issuance. (July 6, 2016)
Managing Aging Processes in Storage (MAPS) 84 FR 39022 Report. NUREG; Issuance. (August 8, 2019)
Dry Storage and Transportation of High Burnup 85 FR 77267 Spent Nuclear Fuel. NUREG; Issuance.
(December 1, 2020)
EPRI TR3002005371, Susceptibility https://www.epri.com/research/pr Assessment Criteria for Chloride-Induced Stress oducts/3002005371 Corrosion Cracking (CISCC) of Welded Stainless-Steel Canisters for Dry Cask Storage Systems (September 18, 2015)
Direct Final Rule https://www.nrc.gov/about-nrc/regulatory/rulemaking/rulema king-process/direct-final-rule.html
The direct final rule published on February 13, 2023 (88 FR 910 6), which was
delayed indefinitely on April 26, 2023 (88 FR 25271), is confir med. The direct final rule is
effective on August 2, 2023, and the following correction is ef fective August 2, 2023.
Correction of Direct Final Rule
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.
/RA/
Catherine Haney, Acting Executive Director for Operations.
18
ML23103A211 *via e-mail **via e-concurren ce OFFICE REFS/MRPB** DFM/STLB** REFS/MRPB** REFS/RASB**
NAME JFirth KBanovac DBearde KCastellon DATE 5/5/2023 5/11/2023 5/10/2023 5/11/2023 OFFICE REFS/MRPB** DFM/STLB** REFS/RASB** OGC/NLO*
NAME JShepard YDiaz-Sanabria CBladey TJones*
(ACarerra for)
DATE 5/31/2023 5/14/2023 5/25/2023 6/7/2023 OFFICE NMSS/DFM/D** NMSS/REFS/D** EDO**
NAME SShelton CRegan DDorman (JZimmerman for) (DSilberfeld for) (CHaney for)
DATE 6/12/2023 6/9/2023 6/27/2023