Arizona Public Service Company; Palo Verde Nuclear Generating Station Independent Spent Fuel Storage Installation, 44161-44162 [2023-14602]

Download as PDF 44161 Federal Register / Vol. 88, No. 131 / Tuesday, July 11, 2023 / Notices be acceptable for managing the effects of aging on SSCs within the scope of license renewal, as required by 10 CFR part 54. If an applicant’s SLRA credits an AMP described in the GALL–SLR Report, the applicant should ensure that the conditions and operating experience (OE) at the plant are bounded by the conditions and OE for which the GALL– SLR Report program was evaluated. If these bounding conditions are not met, the applicant should address any additional aging effects and augment the AMPs for subsequent license renewal. If an SLRA references the approach described in the GALL–SLR Report as the approach used for managing the aging effect(s), the NRC staff will use the GALL–SLR Report as a basis for the SLRA assessment, consistent with guidance specified in the SRP–SLR. The SRP–SLR, which references the GALL–SLR Report, provides guidance to updates were identified subsequent to issuance of the SLR–ISGs, which are also incorporated in the revisions to the GALL–SLR Report and SRP–SLR. The issued SLR–ISGs are listed in the ‘‘Availability of Documents’’ section. Supplement 1 of the Technical Bases Document is a knowledge management and knowledge transfer document associated with GALL–SLR Report, Revision 1, and SRP–SLR, Revision 1. This supplement details the technical changes that were made in the revisions to the GALL–SLR Report and SRP–SLR and provides the underlying rationale that the NRC staff used for those technical changes. III. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the following methods, as indicated. Document description Adams accession No. Draft NUREG–2191, ‘‘Generic Aging Lessons Learned for Subsequent License Renewal (GALL–SLR), Draft Report for Comment,’’ Revision 1, Volume 1. Draft NUREG–2191, ‘‘Generic Aging Lessons Learned for Subsequent License Renewal (GALL–SLR), Draft Report for Comment,’’ Revision 1, Volume 2. Draft NUREG–2192, ‘‘Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, Draft Report for Comment,’’ Revision 1. Draft NUREG–2221, ‘‘Technical Bases for Changes in the Subsequent License Renewal Guidance Documents, NUREG–2191, Revision 1, Draft Report for Comment and NUREG–2192, Revision 1, Draft Report for Comment,’’ Supplement 1. SLR–ISG–2021–01–PWRVI, ‘‘Updated Aging Management Criteria for Reactor Vessel Internal Components of PressurizedWater Reactors’’ Interim Staff Guidance. SLR–ISG–2021–02–MECHANICAL, ‘‘Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance’’ Interim Staff Guidance. SLR–ISG–2021–03–STRUCTURES, ‘‘Updated Aging Management Criteria for Structures Portions of Subsequent License Renewal Guidance’’ Interim Staff Guidance. SLR–ISG–2021–04–ELECTRICAL, ‘‘Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance’’ Interim Staff Guidance. ML23180A182 Dated: July 5, 2023. For the Nuclear Regulatory Commission. Michelle W. Hayes, Chief, Licensing and Regulatory Infrastructure Branch, Division of New and Renewed Licenses, Office of Nuclear Reactor Regulation. [FR Doc. 2023–14577 Filed 7–10–23; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 72–1031 and 72–44; NRC– 2023–0121] ddrumheller on DSK120RN23PROD with NOTICES1 the NRC staff reviewers in the Office of Nuclear Reactor Regulation. These reviewers perform safety reviews of applications to renew nuclear power plant licenses in accordance with 10 CFR part 54. After the initial issuance of the GALL–SLR Report and SRP–SLR in 2017, several documents referred to as Subsequent License Renewal Interim Staff Guidance (SLR–ISGs) were created to reflect new or updated industry guidance, codes, or standards; relevant plant operating experience; incorporation of lessons learned from completed SLR application reviews; development of new aging management programs or aging management review items; and identification of required corrections and clarifications to the guidance. GALL–SLR Report, Revision 1, and SRP–SLR, Revision 1, incorporate the issued SLR–ISGs. Additional Arizona Public Service Company; Palo Verde Nuclear Generating Station Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: VerDate Sep<11>2014 17:25 Jul 10, 2023 Jkt 259001 The U.S. Nuclear Regulatory Commission (NRC) issued an exemption in response to a request from Arizona Public Service Company. The exemption will allow the licensee to deviate from the requirements for the NAC International, Inc. MAGNASTOR® Storage System in Certificate of Compliance No. 1031, Amendment No. 7, by utilizing storage cask lids that were not fabricated in accordance with the requirements of two codes issued by the American Concrete Institute (ACI). DATES: The exemption to Arizona Public Service Company was issued on July 5, 2023. ADDRESSES: Please refer to Docket ID NRC–2023–0121 when contacting the NRC about the availability of information regarding this document. You may obtain publicly available information related to this document using any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search SUMMARY: PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 ML23180A188 ML23180A191 ML23180A208 ML20217L203 ML20181A434 ML20181A381 ML20181A395 for Docket ID NRC–2023–0121. Address questions about Dockets IDs in Regulations.gov to Stacy Schumann; telephone: 301–415–0624; email: Stacy.Schumanns@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publicly available documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, at 301–415–4737, or by email to PDR.Resource@nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) E:\FR\FM\11JYN1.SGM 11JYN1 44162 Federal Register / Vol. 88, No. 131 / Tuesday, July 11, 2023 / Notices is provided the first time that it is mentioned in this document. • NRC’s PDR: The PDR, where you may examine and order copies of publicly available documents, is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1–800–397–4209 or 301–415– 4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT: Nishka Devaser, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–5196, email: Nishka.Devaser@ nrc.gov. SUPPLEMENTARY INFORMATION: ddrumheller on DSK120RN23PROD with NOTICES1 I. Introduction The NRC issued an exemption (ADAMS Package Accession No. ML23166B082) in response to a request dated May 23, 2023, from Arizona Public Service Company for the Palo Verde Nuclear Generating Station Independent Spent Fuel Storage Installation (ISFSI) (ADAMS Accession No. ML23143A391). The exemption allows exemption from the requirements of §§ 72.212(a)(2), (b)(3), and (b)(5)(i) and 72.214 and the portion of § 72.212(b)(11) of title 10 of the Code of Federal Regulations (10 CFR) that requires compliance with the terms and conditions set forth in the certificate of compliance for each spent fuel cask used by an ISFSI general licensee. The exemption requested authorization to load and store spent fuel in MAGNASTOR® storage casks with lids that were not fabricated in accordance with Technical Specification A4.2, as specified in Amendment No. 7 of the NAC International Certificate of Compliance No. 1031 for the MAGNASTOR® storage system. Amendment No. 7 is used at the Palo Verde ISFSI (ADAMS Package Accession No. ML17013A466). Technical Specification, Appendix A, A4.2 requires the concrete cask lid to be designed and fabricated in accordance with the American Concrete Institute Specifications ACI–349, ‘‘Code Requirements for Nuclear Safety Related Concrete Structures,’’ and ACI–318, ‘‘Building Code Requirements for Structural Concrete,’’ which according to the technical specifications govern the concrete cask design and construction, respectively. NAC submitted an amendment request dated January 24, 2022 (ADAMS Accession No. ML22024A374) to eliminate the need for compliance with VerDate Sep<11>2014 17:25 Jul 10, 2023 Jkt 259001 the referenced technical specification for the concrete in the cask lids in the Certificate of Compliance No. 1031 for the MAGNASTOR® storage system, however this exemption was necessary to meet loading campaigns scheduled before resolution of NAC’s amendment request. The applications provided information documenting that the concrete in the cask lids is not relied upon for the strength safety function provided by the ACI codes in Technical Specification, Appendix A, A4.2, and the concrete in the cask lids was fabricated using standards that ensure the concrete will continue to meet the required shielding safety function. Based on the NRC staff’s evaluation of the exemption request, and the statements and representations provided by the applicant in the exemption request, the staff concluded that the proposed action to exempt the cask lids from the current Technical Specification in A4.2 at the ISFSI site is authorized by law and will not endanger life, property, or the common defense and security, and is otherwise in the public interest and therefore meets the exemption requirements in 10 CFR 72.7. Dated: July 6, 2023. For the Nuclear Regulatory Commission. Bernard H. White, Acting Chief, Storage and Transportation Licensing Branch, Division of Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2023–14602 Filed 7–10–23; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2023–0120] Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Nuclear Regulatory Commission. ACTION: Monthly notice. AGENCY: PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 I. Obtaining Information and Submitting Comments A. Obtaining Information Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the SUMMARY: Commission that such amendment involves no significant hazards consideration (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person. DATES: Comments must be filed by August 10, 2023. A request for a hearing or petitions for leave to intervene must be filed by September 11, 2023. This monthly notice includes all amendments issued, or proposed to be issued, from May 25, 2023, to June 22, 2023. The last monthly notice was published on June 13, 2023. ADDRESSES: You may submit comments by any of the following methods; however, the NRC encourages electronic comment submission through the Federal rulemaking website: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2023–0120. Address questions about Docket IDs in Regulations.gov to Stacy Schumann; telephone: 301–415–0624; email: Stacy.Schumann@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: Office of Administration, Mail Stop: TWFN–7– A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, ATTN: Program Management, Announcements and Editing Staff. For additional direction on obtaining information and submitting comments, see ‘‘Obtaining Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Paula Blechman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–415– 2242; email: Paula.Blechman@nrc.gov. SUPPLEMENTARY INFORMATION: Please refer to Docket ID NRC–2023– 0120, facility name, unit number(s), docket number(s), application date, and subject 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–2023–0120. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publicly available documents online in the E:\FR\FM\11JYN1.SGM 11JYN1

Agencies

[Federal Register Volume 88, Number 131 (Tuesday, July 11, 2023)]
[Notices]
[Pages 44161-44162]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-14602]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 72-1031 and 72-44; NRC-2023-0121]


Arizona Public Service Company; Palo Verde Nuclear Generating 
Station Independent Spent Fuel Storage Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) issued an 
exemption in response to a request from Arizona Public Service Company. 
The exemption will allow the licensee to deviate from the requirements 
for the NAC International, Inc. MAGNASTOR[supreg] Storage System in 
Certificate of Compliance No. 1031, Amendment No. 7, by utilizing 
storage cask lids that were not fabricated in accordance with the 
requirements of two codes issued by the American Concrete Institute 
(ACI).

DATES: The exemption to Arizona Public Service Company was issued on 
July 5, 2023.

ADDRESSES: Please refer to Docket ID NRC-2023-0121 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2023-0121. Address 
questions about Dockets IDs in Regulations.gov to Stacy Schumann; 
telephone: 301-415-0624; email: [email protected]. For technical 
questions, contact the individual listed in the FOR FURTHER INFORMATION 
CONTACT section of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, at 301-415-4737, 
or by email to [email protected]. The ADAMS accession number for 
each document referenced (if it is available in ADAMS)

[[Page 44162]]

is provided the first time that it is mentioned in this document.
     NRC's PDR: The PDR, where you may examine and order copies 
of publicly available documents, is open by appointment. To make an 
appointment to visit the PDR, please send an email to 
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8 
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except 
Federal holidays.

FOR FURTHER INFORMATION CONTACT: Nishka Devaser, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone: 301-415-5196, email: 
[email protected].

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC issued an exemption (ADAMS Package Accession No. 
ML23166B082) in response to a request dated May 23, 2023, from Arizona 
Public Service Company for the Palo Verde Nuclear Generating Station 
Independent Spent Fuel Storage Installation (ISFSI) (ADAMS Accession 
No. ML23143A391). The exemption allows exemption from the requirements 
of Sec. Sec.  72.212(a)(2), (b)(3), and (b)(5)(i) and 72.214 and the 
portion of Sec.  72.212(b)(11) of title 10 of the Code of Federal 
Regulations (10 CFR) that requires compliance with the terms and 
conditions set forth in the certificate of compliance for each spent 
fuel cask used by an ISFSI general licensee.
    The exemption requested authorization to load and store spent fuel 
in MAGNASTOR[supreg] storage casks with lids that were not fabricated 
in accordance with Technical Specification A4.2, as specified in 
Amendment No. 7 of the NAC International Certificate of Compliance No. 
1031 for the MAGNASTOR[supreg] storage system. Amendment No. 7 is used 
at the Palo Verde ISFSI (ADAMS Package Accession No. ML17013A466).
    Technical Specification, Appendix A, A4.2 requires the concrete 
cask lid to be designed and fabricated in accordance with the American 
Concrete Institute Specifications ACI-349, ``Code Requirements for 
Nuclear Safety Related Concrete Structures,'' and ACI-318, ``Building 
Code Requirements for Structural Concrete,'' which according to the 
technical specifications govern the concrete cask design and 
construction, respectively.
    NAC submitted an amendment request dated January 24, 2022 (ADAMS 
Accession No. ML22024A374) to eliminate the need for compliance with 
the referenced technical specification for the concrete in the cask 
lids in the Certificate of Compliance No. 1031 for the 
MAGNASTOR[supreg] storage system, however this exemption was necessary 
to meet loading campaigns scheduled before resolution of NAC's 
amendment request. The applications provided information documenting 
that the concrete in the cask lids is not relied upon for the strength 
safety function provided by the ACI codes in Technical Specification, 
Appendix A, A4.2, and the concrete in the cask lids was fabricated 
using standards that ensure the concrete will continue to meet the 
required shielding safety function. Based on the NRC staff's evaluation 
of the exemption request, and the statements and representations 
provided by the applicant in the exemption request, the staff concluded 
that the proposed action to exempt the cask lids from the current 
Technical Specification in A4.2 at the ISFSI site is authorized by law 
and will not endanger life, property, or the common defense and 
security, and is otherwise in the public interest and therefore meets 
the exemption requirements in 10 CFR 72.7.

    Dated: July 6, 2023.

    For the Nuclear Regulatory Commission.
Bernard H. White,
Acting Chief, Storage and Transportation Licensing Branch, Division of 
Fuel Management, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2023-14602 Filed 7-10-23; 8:45 am]
BILLING CODE 7590-01-P
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