Northern States Power Company; Prairie Island Independent Spent Fuel Storage Installation; License Amendment Application, 18680-18681 [2024-05409]

Download as PDF 18680 Federal Register / Vol. 89, No. 51 / Thursday, March 14, 2024 / Notices Document description Adams accession No. Letter to Ricky Sylestine, Chairman, Alabama-Coushatta Tribe of Texas, Re ACU Molten Salt Research Reactor Construction Permit Application, dated May 5, 2023. Letter to NRC from ACU, Response to NRC Request for Supplemental Information, dated October 14 and October 20, 2022. Letter to NRC from ACU, Submittal of Construction Permit Application for the Molten Salt Research Reactor, dated August 12, 2022. Dated: March 11, 2024. For the Nuclear Regulatory Commission. Daniel Barnhurst, Chief, Environmental Project Management Branch 3, Division of Rulemaking, Environmental, and Financial Support, Office of Nuclear Material Safety, and Safeguards. [FR Doc. 2024–05399 Filed 3–13–24; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 72–10; NRC–2023–0155] Northern States Power Company; Prairie Island Independent Spent Fuel Storage Installation; License Amendment Application Nuclear Regulatory Commission. ACTION: Notice; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by Northern States Power Company (NSPM) for amendment of Special Nuclear Materials License No. SNM–2506 which authorizes NSPM to receive, possess, store, and transfer spent nuclear fuel and associated radioactive materials. The amendment request sought to revise the technical specifications (TS) for the Prairie Island Independent Spent Fuel Storage Installation (PI ISFSI) to allow use of a Code alternative as an option to the requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1, Subsection NB, Paragraph NB–5130, by revising the TS to add the Code alternative to TS section 4.4, table 4.4– 1, TN–40HT ASME Code Exceptions. DATES: The license amendment was issued March 5, 2024. ADDRESSES: Please refer to Docket ID NRC–2023–0155 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–2023–0155. Address ddrumheller on DSK120RN23PROD with NOTICES1 SUMMARY: VerDate Sep<11>2014 16:47 Mar 13, 2024 Jkt 262001 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. • 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) 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: John-Chau Nguyen, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–0262; email: JohnChau.Nguyen@nrc.gov. SUPPLEMENTARY INFORMATION: The NRC received, by letter dated July 14, 2023 (ADAMS Accession No. ML23195A187), a license amendment application from NSPM, to amend Special Nuclear Materials License No. SNM–2506, which authorizes the storage of spent fuel at the PI ISFSI located in Welch, Minnesota. Specifically, the amendment sought to revise the TS to allow use of a Code alternative as an option to the requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1, Subsection NB, Paragraph NB–5130, by PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 ML23009B617. ML22293B816 (Package). ML22227A201 (Package). revising the TS to add the Code alternative to TS section 4.4, table 4.4– 1, TN–40HT ASME Code Exceptions. An NRC administrative completeness review, documented in a letter to NSPM dated August 24, 2023 (ADAMS Accession No. ML23234A135), found the application acceptable to begin a technical review. In accordance with section 72.16 of title 10 of the Code of Federal Regulations (10 CFR), a notice of docketing was published in the Federal Register on September 8, 2023 (88 FR 62108). The notice of docketing included an opportunity to request a hearing and to petition for leave to intervene. No requests for a hearing or petitions for leave to intervene were submitted. The NRC prepared a safety evaluation report (SER) (ADAMS Accession No. ML24008A131) to document its review and evaluation of the amendment request. In addition, the NRC evaluated an assertion by NSPM that the amendment request satisfied the categorical exclusion criteria specified in 10 CFR 51.22(c)(11). Under 10 CFR 51.22(c)(11), a categorical exclusion is allowed for amendments to materials licenses which are administrative, organizational, or procedural in nature, or which result in a change to process operations or equipment, provided that (i) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, (ii) there is no significant increase in individual or cumulative occupational radiation exposure, (iii) there is no significant construction impact, and (iv) there is no significant increase in the potential for or consequences from radiological accidents. As explained in the SER, the NRC determined that the license amendment satisfied the 10 CFR 51.22(c)(11) categorical exclusion criteria. Consequently, an environmental assessment and finding of no significant impact are not required. Upon completing its review, the NRC staff determined that the request complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), as well as the NRC’s rules and regulations. The Commission has made appropriate E:\FR\FM\14MRN1.SGM 14MRN1 Federal Register / Vol. 89, No. 51 / Thursday, March 14, 2024 / Notices findings as required by the Act and the Commission’s rules and regulations in 10 CFR chapter I, which are set forth in the license amendment. The NRC approved and issued Amendment No. 12 to Special Nuclear Materials License No. SNM–2506 (ML24008A130), held by NSPM for the receipt, possession, transfer, and storage of spent fuel and associated radioactive materials at the PI ISFSI. Pursuant to 10 CFR 72.46(d), the NRC is providing notice of the action taken. Amendment No. 12 was effective as of the date of issuance, March 5, 2024. Dated: March 11, 2024. For the Nuclear Regulatory Commission. Yoira K. Diaz-Sanabria, Chief, Storage and Transportation Licensing Branch, Division of Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2024–05409 Filed 3–13–24; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION 714th Meeting of the Advisory Committee on Reactor Safeguards (ACRS) ddrumheller on DSK120RN23PROD with NOTICES1 In accordance with the purposes of sections 29 and 182b of the Atomic Energy Act (42 U.S.C. 2039, 2232(b)), the Advisory Committee on Reactor Safeguards (ACRS) will hold meetings on April 3–4, 2024. The Committee will be conducting meetings that will include some Members being physically present at the NRC while other Members participate remotely. Interested members of the public are encouraged to participate remotely in any open sessions via MS Teams or via phone at 301–576–2978, passcode 678949385#. A more detailed agenda including the MSTeams link may be found at the ACRS public website at https:// www.nrc.gov/reading-rm/doccollections/acrs/agenda/. If you would like the MSTeams link forwarded to you, please contact the Designated Federal Officer (DFO) as follows: Quynh.Nguyen@nrc.gov, or Lawrence.Burkhart@nrc.gov. Wednesday, April 3, 2024 8:30 a.m.–8:35 a.m.: Opening Remarks by the ACRS Chair (Open)— The ACRS Chair will make opening remarks regarding the conduct of the meeting. 8:35 a.m.–3:30 p.m.: Research Topic— Non-Light Water Reactor Code Development (Open)—The Committee will have presentations and discussion with the NRC staff regarding the subject topic. VerDate Sep<11>2014 16:47 Mar 13, 2024 Jkt 262001 3:30 p.m.–6:00 p.m.: NuScale Standard Design Approval Application Topics (Open/Closed)—The Committee will have presentations and discussion with the NRC staff and NuScale regarding the subject topic. [Note: Pursuant to 5 U.S.C 552b(c)(4), a portion of this session may be closed in order to discuss and protect information designated as proprietary.] Thursday, April 4, 2024 8:30 a.m.–6:00 p.m.: Planning and Procedures Session/Future ACRS Activities/Reconciliation of ACRS Comments and Recommendations/ Preparation of Reports (Open/Closed)— The Committee will hear discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the Full Committee during future ACRS meetings, and/or proceed to preparation of reports as determined by the Chair. [NOTE: Pursuant to 5 U.S.C. 552b(c)(2), a portion of this meeting may be closed to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of the ACRS.] [Note: Pursuant to 5 U.S.C. 552b(c)(4), a portion of this session may be closed in order to discuss and protect information designated as proprietary.] Procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on June 13, 2019 (84 FR 27662). In accordance with those procedures, oral or written views may be presented by members of the public, including representatives of the nuclear industry. Persons desiring to make oral statements should notify Quynh Nguyen, Cognizant ACRS Staff and the DFO (Telephone: 301–415–5844, Email: Quynh.Nguyen@ nrc.gov), 5 days before the meeting, if possible, so that appropriate arrangements can be made to allow necessary time during the meeting for such statements. In view of the possibility that the schedule for ACRS meetings may be adjusted by the Chair as necessary to facilitate the conduct of the meeting, persons planning to attend should check with the cognizant ACRS staff if such rescheduling would result in major inconvenience. An electronic copy of each presentation should be emailed to the cognizant ACRS staff at least one day before the meeting. In accordance with Subsection 10(d) of Public Law 92–463 and 5 U.S.C. 552b(c), certain portions of this meeting may be closed, as specifically noted above. Use of still, motion picture, and television cameras during the meeting may be limited to selected portions of PO 00000 Frm 00092 Fmt 4703 Sfmt 4703 18681 the meeting as determined by the Chair. Electronic recordings will be permitted only during the open portions of the meeting. ACRS meeting agendas, meeting transcripts, and letter reports are available through the NRC Public Document Room (PDR) at pdr.resource@ nrc.gov, or by calling the PDR at 1–800– 397–4209, or from the Publicly Available Records System component of NRC’s Agencywide Documents Access and Management System, which is accessible from the NRC website at https://www.nrc.gov/reading-rm/ adams.html or https://www.nrc.gov/ reading-rm/doc-collections/#ACRS/. Dated: March 11, 2024. Russell E. Chazell, Federal Advisory Committee Management Officer, Office of the Secretary. [FR Doc. 2024–05402 Filed 3–13–24; 8:45 am] BILLING CODE 7590–01–P POSTAL REGULATORY COMMISSION [Docket Nos. MC2024–203 and CP2024–209; MC2024–204 and CP2024–210; MC2024–205 and CP2024–211] New Postal Products Postal Regulatory Commission. Notice. AGENCY: ACTION: The Commission is noticing a recent Postal Service filing for the Commission’s consideration concerning a negotiated service agreement. This notice informs the public of the filing, invites public comment, and takes other administrative steps. DATES: Comments are due: March 18, 2024. SUMMARY: Submit comments electronically via the Commission’s Filing Online system at https:// www.prc.gov. Those who cannot submit comments electronically should contact the person identified in the FOR FURTHER INFORMATION CONTACT section by telephone for advice on filing alternatives. ADDRESSES: FOR FURTHER INFORMATION CONTACT: David A. Trissell, General Counsel, at 202–789–6820. SUPPLEMENTARY INFORMATION: Table of Contents I. Introduction II. Docketed Proceeding(s) I. Introduction The Commission gives notice that the Postal Service filed request(s) for the Commission to consider matters related to negotiated service agreement(s). The E:\FR\FM\14MRN1.SGM 14MRN1

Agencies

[Federal Register Volume 89, Number 51 (Thursday, March 14, 2024)]
[Notices]
[Pages 18680-18681]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-05409]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 72-10; NRC-2023-0155]


Northern States Power Company; Prairie Island Independent Spent 
Fuel Storage Installation; License Amendment Application

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) reviewed an 
application by Northern States Power Company (NSPM) for amendment of 
Special Nuclear Materials License No. SNM-2506 which authorizes NSPM to 
receive, possess, store, and transfer spent nuclear fuel and associated 
radioactive materials. The amendment request sought to revise the 
technical specifications (TS) for the Prairie Island Independent Spent 
Fuel Storage Installation (PI ISFSI) to allow use of a Code alternative 
as an option to the requirements of the 2004 Edition through 2006 
Addenda of the American Society of Mechanical Engineers (ASME) Boiler 
and Pressure Vessel (B&PV) Code, Section III, Division 1, Subsection 
NB, Paragraph NB-5130, by revising the TS to add the Code alternative 
to TS section 4.4, table 4.4-1, TN-40HT ASME Code Exceptions.

DATES: The license amendment was issued March 5, 2024.

ADDRESSES: Please refer to Docket ID NRC-2023-0155 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-2023-0155. Address 
questions about Docket 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) 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: John-Chau Nguyen, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone: 301-415-0262; email: [email protected].

SUPPLEMENTARY INFORMATION: The NRC received, by letter dated July 14, 
2023 (ADAMS Accession No. ML23195A187), a license amendment application 
from NSPM, to amend Special Nuclear Materials License No. SNM-2506, 
which authorizes the storage of spent fuel at the PI ISFSI located in 
Welch, Minnesota. Specifically, the amendment sought to revise the TS 
to allow use of a Code alternative as an option to the requirements of 
the 2004 Edition through 2006 Addenda of the American Society of 
Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 
Section III, Division 1, Subsection NB, Paragraph NB-5130, by revising 
the TS to add the Code alternative to TS section 4.4, table 4.4-1, TN-
40HT ASME Code Exceptions.
    An NRC administrative completeness review, documented in a letter 
to NSPM dated August 24, 2023 (ADAMS Accession No. ML23234A135), found 
the application acceptable to begin a technical review. In accordance 
with section 72.16 of title 10 of the Code of Federal Regulations (10 
CFR), a notice of docketing was published in the Federal Register on 
September 8, 2023 (88 FR 62108). The notice of docketing included an 
opportunity to request a hearing and to petition for leave to 
intervene. No requests for a hearing or petitions for leave to 
intervene were submitted.
    The NRC prepared a safety evaluation report (SER) (ADAMS Accession 
No. ML24008A131) to document its review and evaluation of the amendment 
request. In addition, the NRC evaluated an assertion by NSPM that the 
amendment request satisfied the categorical exclusion criteria 
specified in 10 CFR 51.22(c)(11). Under 10 CFR 51.22(c)(11), a 
categorical exclusion is allowed for amendments to materials licenses 
which are administrative, organizational, or procedural in nature, or 
which result in a change to process operations or equipment, provided 
that (i) there is no significant change in the types or significant 
increase in the amounts of any effluents that may be released offsite, 
(ii) there is no significant increase in individual or cumulative 
occupational radiation exposure, (iii) there is no significant 
construction impact, and (iv) there is no significant increase in the 
potential for or consequences from radiological accidents. As explained 
in the SER, the NRC determined that the license amendment satisfied the 
10 CFR 51.22(c)(11) categorical exclusion criteria. Consequently, an 
environmental assessment and finding of no significant impact are not 
required.
    Upon completing its review, the NRC staff determined that the 
request complies with the standards and requirements of the Atomic 
Energy Act of 1954, as amended (the Act), as well as the NRC's rules 
and regulations. The Commission has made appropriate

[[Page 18681]]

findings as required by the Act and the Commission's rules and 
regulations in 10 CFR chapter I, which are set forth in the license 
amendment. The NRC approved and issued Amendment No. 12 to Special 
Nuclear Materials License No. SNM-2506 (ML24008A130), held by NSPM for 
the receipt, possession, transfer, and storage of spent fuel and 
associated radioactive materials at the PI ISFSI. Pursuant to 10 CFR 
72.46(d), the NRC is providing notice of the action taken. Amendment 
No. 12 was effective as of the date of issuance, March 5, 2024.

    Dated: March 11, 2024.

    For the Nuclear Regulatory Commission.
Yoira K. Diaz-Sanabria,
Chief, Storage and Transportation Licensing Branch, Division of Fuel 
Management, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2024-05409 Filed 3-13-24; 8:45 am]
BILLING CODE 7590-01-P
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