2024-27489. Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations

License Amendment Requests

Arizona Public Service Company, et al; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Maricopa County, AZ
Docket Nos	50-528, 50-529, 50-530.
Application date	August 28, 2024.
ADAMS Accession No	ML24241A278.
Location in Application of NSHC	Pages 7-10 of the Enclosure.
Brief Description of Amendments	The proposed amendments would revise Technical Specification (TS) Section 3.5.1, “Safety Injection Tanks (SITs)—Operating,” and TS Section 3.5.2, “Safety Injection Tanks (SITs)—Shutdown,” and their bases. Specifically, the proposed TS changes revise Surveillance Requirements (SR) 3.5.1.3 and SR 3.5.2.3 to increase the upper limit of their SIT pressure bands, and to list their pressure requirements in units of pounds per square inch absolute as reflected in the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 safety analyses, with no instrument uncertainties included, instead of the SIT instrument units of pounds per square inch gauge with instrument uncertainties included.
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Carey Fleming, Senior Counsel, Pinnacle West Capital Corporation, 500 N. 5th Street, MS 8695, Phoenix, AZ 85004.
NRC Project Manager, Telephone Number	William Orders, 301-415-3329.
Energy Northwest; Columbia Generating Station; Benton County, WA
Docket No	50-397.
Application date	September 23, 2024.
ADAMS Accession No	ML24267A302.
( print page 93364)
Location in Application of NSHC	Pages 2-3 of the Enclosure.
Brief Description of Amendment	The proposed amendment would modify the Columbia Generating Station technical specifications (TSs) to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-592, “Revise Automatic Depressurization System (ADS) Instrumentation Requirements.” The proposed amendment would revise TS 3.3.5.1, “Emergency Core Cooling System (ECCS) Instrumentation,” Actions to reflect the plant design and the safety significance of inoperable ADS monitoring channels.
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Ryan Lukson, Assistant General Counsel, Energy Northwest, MD 1020, P.O. Box 968, Richland, WA 99352.
NRC Project Manager, Telephone Number	Mahesh Chawla, 301-415-8371.
Entergy Louisiana, LLC, and Entergy Operations, Inc.; River Bend Station, Unit 1; West Feliciana Parish, LA; Entergy Operations, Inc., System Energy Resources, Inc., Cooperative Energy, A Mississippi Electric Cooperative, and Entergy Mississippi, LLC; Grand Gulf Nuclear Station, Unit 1; Claiborne County, MS
Docket Nos	50-416, 50-458.
Application date	September 19, 2024.
ADAMS Accession No	ML24263A271.
Location in Application of NSHC	Pages 1-3 of the Enclosure.
Brief Description of Amendments	The proposed amendments would revise the technical specifications (TSs) for Grand Gulf Nuclear Station, Unit 1, and River Bend Station, Unit 1. The proposed change would revise the “Emergency Core Cooling System (ECCS) Instrumentation” TS Actions related to automatic depressurization system instrumentation monitoring channels, consistent with NRC-approved Industry/Technical Specifications Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-592, “Revise Automatic Depressurization System (ADS) Instrumentation Requirements.”
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Susan Raimo, Associate General Counsel—Nuclear, 101 Constitution Avenue NW, Washington, DC 20001.
NRC Project Manager, Telephone Number	Michael Mahoney, 301-415-3867.
NextEra Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Manitowoc County, WI
Docket Nos	50-266, 50-301.
Application date	October 8, 2024.
ADAMS Accession No	ML24282A760.
Location in Application of NSHC	Pages 22-24 of the Enclosure.
Brief Description of Amendments	The proposed amendments would modify the Point Beach Nuclear Plant, Units 1 and 2 licensing basis to implement a change to the approved voluntary implementation of the provisions of 10 CFR 50.69, “Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.” The proposed amendments would incorporate the use of an alternative seismic method into the previously approved 10 CFR 50.69 categorization process. Additionally, the proposed amendments would make editorial corrections to Unit 1 License Condition M and Unit 2 License Condition L, “Additional Conditions,” Functions 5 and 6 on Technical Specification (TS) table 3.3.1-1, and TS section 5.5.18.h.
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Steven Hamrick, Senior Attorney 801 Pennsylvania Ave NW, Suite 220, Washington, DC 20004.
NRC Project Manager, Telephone Number	Scott Wall, 301-415-2855.
Southern Nuclear Operating Company, Inc.; Joseph M. Farley Nuclear Plant, Units 1 and 2; Houston County, AL
Docket Nos	50-348, 50-364.
Application date	September 27, 2024.
ADAMS Accession No	ML24271A291.
Location in Application of NSHC	Pages E-6 through E-8 of the Enclosure.
Brief Description of Amendments	The proposed amendments would revise the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, Updated Final Safety Analysis Report to provide gap release fractions for high burnup fuel rods that exceed the linear heat generation rate limit stated in Regulatory Guide (RG) 1.183, Revision 0, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors.” Specifically, the proposed amendments would allow Farley, Units 1 and 2, to be excepted from Footnote 11 to Table 3, “Non-[Loss-of-Coolant-Accident] Fraction of Fission Product Inventory in Gap,” of RG 1.183, Revision 0.
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Millicent Ronnlund, Vice President and General Counsel, Southern Nuclear Operating Co., Inc., P.O. Box 1295, Birmingham, AL 35201-1295.
NRC Project Manager, Telephone Number	Zachary Turner, 301-415-6303.
Virginia Electric and Power Company; Surry Power Station, Unit Nos. 1 and 2; Surry County, VA
Docket Nos	50-280, 50-281.
Application date	September 3, 2024.
( print page 93365)
ADAMS Accession No	ML24248A171.
Location in Application of NSHC	Pages 49 to 51 of Attachment 1.
Brief Description of Amendments	The proposed amendments would modify Technical Specification (TS) 3.7, “Instrumentation Systems,” and TS 3.14, “Circulating and Service Water (SW) System,” that support the use of temporary SW piping and maintenance activities on the existing SW piping.
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	W.S. Blair, Senior Counsel, Dominion Energy Services, Inc., 120 Tredegar St, RS-2, Richmond, VA 23219.
NRC Project Manager, Telephone Number	John Klos, 301-415-5136.
Vistra Operations Company LLC ; Beaver Valley Power Station, Units 1 and 2; Beaver County, PA
Docket Nos	50-334, 50-412.
Application date	September 17, 2024.
ADAMS Accession No	ML24261B850.
Location in Application of NSHC	Pages 4-5 of Attachment 1.
Brief Description of Amendments	The proposed amendments would revise Technical Specifications (TS) 3.5.2, “ECCS [emergency core cooling system]—Operating,” LCO [limiting condition for operation] 3.5.2, to remove Note 4, which allowed a one-time use of an alternate manual flow path to support repair of a leak. Additionally, the application requests a revision to correct three titles of references cited in TS 5.6.3, “CORE OPERATING LIMITS REPORT (COLR).”
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Roland Backhaus, Senior Lead Counsel-Nuclear, Vistra Corp., 325 7th Street NW, Suite 520, Washington, DC 20004.
NRC Project Manager, Telephone Number	V. Sreenivas, 301-415-2597.
Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Somervell County, TX
Docket Nos	50-445, 50-446.
Application date	September 12, 2024.
ADAMS Accession No	ML24256A088.
Location in Application of NSHC	Pages 13-15 of the Enclosure.
Brief Description of Amendments	The proposed amendments would revise technical specifications to eliminate use of the defined term core alterations and revise requirements during handling of irradiated fuel by adopting Technical Specifications Task Force (TSTF) Traveler TSTF-51, “Revise containment requirements during handling irradiated fuel and core alterations;” TSTF-471, “Eliminate use of term CORE ALTERATIONS in ACTIONS and Notes,” and TSTF-571-T, “Revise Actions for Inoperable Source Range Neutron Flux Monitor.”
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Roland Backhaus, Senior Lead Counsel-Nuclear, Vistra Corp., 325 7th Street NW, Suite 520, Washington, DC 20004.
NRC Project Manager, Telephone Number	Samson Lee, 301-415-3168.
Wolf Creek Nuclear Operating Corporation; Wolf Creek Generating Station, Unit 1; Coffey County, KS
Docket No	50-482.
Application date	September 12, 2024.
ADAMS Accession No	ML24260A071.
Location in Application of NSHC	Pages 13-16 of Attachment I.
Brief Description of Amendment	The proposed amendment would revise the licensing basis as described in the Wolf Creek Updated Safety Analysis Report to allow the use of a risk-informed approach to address safety issues discussed in Generic Safety Issue (GSI)-191, “Assessment of Debris Accumulation on PWR [pressurized-water reactor] Sump Performance.” The amendment would also add a new Technical Specification 3.6.8, “Containment Sump.”
Proposed Determination	NSHC.
Name of Attorney for Licensee, Mailing Address	Chris Johnson, Corporate Counsel Director, Evergy, One Kansas City Place, 1KC-Missouri HQ 16, 1200 Main Street, Kansas City, MO 64105.
NRC Project Manager, Telephone Number	Samson Lee, 301-415-3168.

III. Notice of Issuance of Amendments to Facility Operating Licenses and Combined Licenses

During the period since publication of the last monthly notice, the Commission has issued the following amendments. The Commission has determined for each of these amendments that the application complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate 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.

A notice of consideration of issuance of amendment to facility operating license or combined license, as applicable, proposed NSHC determination, and opportunity for a hearing in connection with these ( print page 93366) actions, were published in the Federal Register as indicated in the safety evaluation for each amendment.

Unless otherwise indicated, the Commission has determined that these amendments satisfy the criteria for categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these amendments. If the Commission has prepared an environmental assessment under the special circumstances provision in 10 CFR 51.22(b) and has made a determination based on that assessment, it is so indicated in the safety evaluation for the amendment.

For further details with respect to each action, see the amendment and associated documents such as the Commission's letter and safety evaluation, which may be obtained using the ADAMS accession numbers indicated in the following table. The safety evaluation will provide the ADAMS accession numbers for the application for amendment and the Federal Register citation for any environmental assessment. All of these items can be accessed as described in the “Obtaining Information and Submitting Comments” section of this document.

License Amendment Issuances

Constellation FitzPatrick, LLC and Constellation Energy Generation, LLC; James A. FitzPatrick Nuclear Power Plant; Oswego County, NY
Docket No	50-333.
Amendment Date	October 17, 2024.
ADAMS Accession No	ML24276A133.
Amendment No	357.
Brief Description of Amendment	The amendment revised the technical specification (TS) requirements in Section 1.3 regarding completion times and Section 3.0 regarding limiting condition for operation and surveillance requirement usage. These changes are consistent with the NRC-approved Technical Specification Task Force (TSTF) Traveler TSTF-529, Revision 4, “Clarify Use and Application Rules.” Additionally, the amendment makes several administrative changes to the TS.
Public Comments Received as to Proposed NSHC (Yes/No)	No.
Nine Mile Point Nuclear Station, LLC and Constellation Energy Generation, LLC; Nine Mile Point Nuclear Station, Unit 1; Oswego County, NY
Docket No	50-220.
Amendment Date	October 16, 2024.
ADAMS Accession No	ML24268A338.
Amendment No	253.
Brief Description of Amendment	The amendment revised the Nine Mile Point Nuclear Station Point, Unit 1 (NMP1), technical specifications (TSs) by relocating surveillance requirement (SR) 4.3.6.a to the licensee-controlled surveillance frequency control program (SFCP). The SFCP was previously implemented at NMP1 by License Amendment No. 222 dated May 16, 2016; however, the SR was not fully revised with the adoption of NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-425, Revision 3, “Relocated Surveillance Frequencies to Licensee Control—RITSTF [Risk-Informed TSTF] Initiative 5b.” Specifically, the amendment corrected the SR specification to include the surveillance frequency for the verification of the operability of the valves, position switches, and position indicators and alarms, in the SFCP, consistent with TSTF-425, Revision 3.
Public Comments Received as to Proposed NSHC (Yes/No)	No.
Pacific Gas and Electric Company; Diablo Canyon Nuclear Power Plant, Units 1 and 2; San Luis Obispo County, CA
Docket Nos	50-275, 50-323.
Amendment Date	October 24, 2024.
ADAMS Accession No	ML24261B949.
Amendment Nos	246 (Unit 1) and 248 (Unit 2).
Brief Description of Amendments	The amendments revised Technical Specification 5.6.6, “Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR).” Specifically, the amendments revised the fluence calculational methodology used to determine the reactor coolant system pressure and temperature limits.
Public Comments Received as to Proposed NSHC (Yes/No)	No.