ML25191A194

Issuance of Amendment Nos. 351 and 333 to Revise Containment Fan Cooler Unit Surveillance Requirement

ML25191A194
Person / Time
Site:	Salem
Issue date:	08/05/2025
From:	Shawn Williams Plant Licensing Branch 1
To:	Mcfeaters C Public Service Enterprise Group
Williams, S
References
EPID L-2025-LLA-0065
Download: ML25191A194 (1)

Text

August 5, 2025 Mr. Charles V. McFeaters President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 ISSUANCE OF AMENDMENT NOS. 351 AND 333 TO REVISE CONTAINMENT FAN COOLER UNIT SURVEILLANCE REQUIREMENT (EPID L-2025-LLA-0065)

Dear Mr. McFeaters:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 351 and 333 to Renewed Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit 1 and 2, respectively. The amendments are in response to the application from PSEG Nuclear, LLC, dated April 3, 2025.

The amendments modify the Technical Specification Surveillance Requirements for the containment fan cooler units by removing overly detailed information and relocating it to licensee-controlled documents, consistent with NUREG-1431, Standard Technical Specifications - Westinghouse Plants.

A copy of the related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Shawn Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosures:

1. Amendment No. 351 to DPR-70

2. Amendment No. 333 to DPR-75

3. Safety Evaluation cc: Listserv

PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 351 Renewed License No. DPR-70

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PSEG Nuclear LLC dated April 3, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-70 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 351, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: August 5, 2025 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2025.08.05 13:47:03 -04'00'

Renewed License No. DPR-70 Amendment No. 351 ATTACHMENT TO LICENSE AMENDMENT NO. 351 RENEWED FACILITY OPERATING LICENSE NO. DPR-70 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272 Replace the following page of Renewed Facility Operating License No. DPR-70 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 6-11a 3/4 6-11a Renewed License No. DPR-70 Amendment No. 351 (4)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 351, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications, and the Environmental Protection Plan.

(3)

Deleted Per Amendment 22, 11-20-79 (4)

Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this renewed license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this renewed license.

(5)

PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety.

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying the water level in each service water accumulator vessel is greater than or equal to 226 inches and less than or equal to 252 inches.

2.

Verifying the temperature in each service water accumulator vessel is greater than or equal to 55°F and less than or equal to 95°F.

3.

Verifying the nitrogen cover pressure in each service water accumulator vessel is greater than or equal to 135 psig and less than or equal to 160 psig.

b.

In accordance with the Surveillance Frequency Control Program by:

1.

Deleted 2.

Verifying that each fan operates for at least 15 minutes.

3.

Verifying a cooling water flow rate of greater than or equal to 1300 gpm to each cooler.

c.

In accordance with the Surveillance Frequency Control Program by verifying that on an actual or simulated actuation signal:

1.

Each fan starts automatically.

2.

The automatic valves and dampers actuate to their correct positions and that the cooling water flow rate to each cooler is greater than or equal to 1300 gpm.

d.

In accordance with the Surveillance Frequency Control Program by verifying that on a loss of offsite power test signal, each service water accumulator vessel discharge valve response time is within limits.

SALEM - UNIT 1 3/4 6-11a Amendment No. 351

PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 333 Renewed License No. DPR-75

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PSEG Nuclear LLC dated April 3, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-75 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 333, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: August 5, 2025 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2025.08.05 13:47:40 -04'00'

Renewed License No. DPR-75 Amendment No. 333 ATTACHMENT TO LICENSE AMENDMENT NO. 333 RENEWED FACILITY OPERATING LICENSE NO. DPR-75 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 Replace the following page of Renewed Facility Operating License No. DPR-75 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 6-13 3/4 6-13 Renewed License No. DPR-75 Amendment No. 333 (3)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended (4)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source or special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration and as fission detectors in amounts as required; (5)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 3459 megawatts (thermal).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 333, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

a.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying the water level in each service water accumulator vessel is greater than or equal to 226 inches and less than or equal to 252 inches.

2.

Verifying the temperature in each service water accumulator vessel is greater than or equal to 55ºF and less than or equal to 95ºF.

3.

Verifying the nitrogen cover pressure in each service water accumulator vessel is greater than or equal to 135 psig and less than or equal to 160 psig.

b.

In accordance with the Surveillance Frequency Control Program by:

1.

Deleted

2.

Verifying that each fan operates for at least 15 minutes.

3.

Verifying a cooling water flow rate of greater than or equal to 1300 gpm to each cooler.

c.

In accordance with the Surveillance Frequency Control Program by verifying that on an actual or simulated actuation signal:

1.

Each fan starts automatically.

2.

The automatic valves and dampers actuate to their correct positions and that the cooling water flow rate to each cooler is greater than or equal to 1300 gpm.

d.

In accordance with the Surveillance Frequency Control Program by verifying that on a loss of offsite power test signal, each service water accumulator vessel discharge valve response time is within limits.

SALEM - UNIT 2 3/4 6-13 Amendment No. 333

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 351 AND 333 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PSEG NUCLEAR LLC CONSTELLATION ENERGY GENERATION, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311

1.0 INTRODUCTION

By application dated April 3, 2025 (Agencywide Documents Access and Management System Accession No. ML25093A108), PSEG Nuclear LLC (the licensee) submitted a license amendment request (LAR) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2.

The proposed amendments would revise the Technical Specification (TS) Surveillance Requirements (SRs) for the containment fan cooler units by removing details of system design and relocating it to licensee-controlled documents as well as adding an explicit allowance to take credit for a SR for an unplanned system actuation. These changes are consistent with NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (collectively referred to as NUREG-1431 in this document) (ML21259A155 and ML21259A159, respectively).

2.0 REGULATORY EVALUATION

2.1

System Description

Salem, Units Nos. 1 and 2, are pressurized water reactors, specifically Westinghouse four-loop designs.

The licensee provided the following system description:

The Containment Fan Cooling System is an Engineered Safety Features (ESF) system. The system is designed to remove heat from the containment during normal operation, and remove heat and reduce pressure in the containment following a Loss of Coolant Accident (LOCA). The system consists of five containment fan cooler units (CFCUs), each including motor, fan, motor heat exchanger, cooling coils, roughing filters, dampers, duct distribution system, instrumentation, and controls.

The CFCUs are powered from three separate vital buses as follows: one CFCU is powered from the A vital bus and two CFCUs are powered from each of the B and C vital buses. This ensures that, in the event of a single failure of a vital bus, the minimum number of three CFCUs required to maintain containment integrity would remain available during a design basis event. Two CFCUs are each supplied with cooling water from one of the two separate service water headers. One CFCU is supplied from both service water headers through normally open isolation valves and check valves from each header.

The CFCUs operate in high speed during normal plant operation where the CFCUs direct air through the roughing filters, cooling coil, fan and discharge header.

Low speed operation of the Fan Cooling System is entered during post-accident conditions which is actuated by a safety injection signal. During post-accident operation, air is drawn through a moisture separator, a post-accident high-efficiency particulate air (HEPA) filter section and cooling coils and is discharged to the duct header.

A minimum of three CFCUs in operation with a single containment spray train is capable of maintaining post-accident containment temperature and pressure below their design basis values, assuming a worst-case single active failure.

2.2 Description of Proposed Changes Current SR 4.6.2.3.b states:

b. In accordance with the Surveillance Frequency Control Program by:

1. Starting (unless already operating) each fan from the control room in low speed.

2. Verifying that each fan operates for at least 15 minutes in low speed.

3. Verifying a cooling water flow rate of greater than or equal to 1300 gpm to each cooler.

Revised SR 4.6.2.3.b would state:

b. In accordance with the Surveillance Frequency Control Program by:

1. Deleted.

2. Verifying that each fan operates for at least 15 minutes.

3. Verifying a cooling water flow rate of greater than or equal to 1300 gpm to each cooler.

Current SR 4.6.2.3.c states:

c. In accordance with the Surveillance Frequency Control Program by verifying that on a safety injection test signal:

1. Each fan starts automatically in low speed.

2. The automatic valves and dampers actuate to their correct positions and that the cooling water flow rate to each cooler is greater than or equal to 1300 gpm.

Revised SR 4.6.2.3.c would state:

c. In accordance with the Surveillance Frequency Control Program by verifying that on an actual or simulated actuation signal:

1. Each fan starts automatically.

2. The automatic valves and dampers actuate to their correct positions and that the cooling water flow rate to each cooler is greater than or equal to 1300 gpm.

2.3 Regulatory Requirements and Guidance Under Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of a license wishes to amend the license, including TSs in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a),

determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public, and that the applicant will comply with the Commissions regulations.

The Commissions regulatory requirements related to the content of TSs are set forth in 10CFR50.36, Technical Specifications, which requires, in pertinent part, that the TSs include: (1) safety limits, limiting safety system settings, and limiting control settings; (2)

LCOs; (3)surveillance requirements; (4) design features; and (5) administrative controls.

Section 50.36(a)(1) states, that Each applicant for a license authorizing operation of a utilization facility shall include in his application proposed technical specifications with the requirements of this section. A summary statement of the bases or reasons for such specifications shall also be included in the application, but shall not become part of the technical specifications.

Regulation 10 CFR 50.36(c)(3) provides that SRs are requirements relating to test, calibration, or inspection to assure the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.

The Summary section of the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, 58 FR39132, published July 22, 1993, states, in part:

Implementation of the Policy Statement through implementation of the improved STS [Standard Technical Specifications] is expected to produce an improvement in the safety of nuclear power plants through the use of more operator-oriented Technical Specifications, improved Technical Specification Bases, reduced action statement induced plant transients, and more efficient use of NRC and industry resources.

SectionIV, The Commission Policy, of the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors states, in part:

The purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by identifying those features that are of controlling importance to safety and establishing on them certain conditions of operation which cannot be changed without prior Commission approval.

[T]he Commission will also entertain requests to adopt portions of the improved STS even if the licensee does not adopt all STS improvements.

The Commission encourages all licensees who submit Technical Specification related submittals based on this Policy Statement to emphasize human factors principles.

In accordance with this Policy Statement, improved STS have been developed and will be maintained for each NSSS [nuclear steam supply system] owners group. The Commission encourages licensees to use the improved STS as the basis for plant specific Technical Specifications. [I]t is the Commission intent that the wording and Bases of the improved STS be used to the extent practicable.

NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Chapter 16.0, Revision 3 (ML100351425), provides NRC staff guidance for reviewing technical specifications.

NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021, which contains the Standard Technical Specifications for Westinghouse plants, includes SRs consistent with the regulatory requirements of 10 CFR 50.36(c)(3). Salem is a Westinghouse design reactor, and the corresponding STSs are NUREG-1431. Although Salem has not adopted standard technical specifications (STS), the STS are still applicable. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1431, as modified by NRC approved travelers.

3.0 TECHNICAL EVALUATION

3.1

NRC Staff Evaluation

The NRC staff evaluated the licensees application to determine whether the proposed changes align with applicable regulations, guidance, and the plant-specific design and licensing basis described in Section 2.3 of this safety evaluation. The staff assessed the acceptability of the proposed TS changes by determining whether they continue to provide reasonable assurance that the limiting condition for operation (LCO) will be met.

The NRC staff also compared the proposed changes to the corresponding SRs in NUREG-1431. The applicable SRs are as follows:

SR 3.6.6A.2: Operate each [required] containment cooling train fan unit for 15 minutes, with a frequency of 31 days OR in accordance with the Surveillance Frequency Control Program.

SR 3.6.6A.8: Verify each [required] containment cooling train starts automatically on an actual or simulated actuation signal, with a frequency of 18 months OR in accordance with the Surveillance Frequency Control Program.

3.1.1 Evaluation of Deletion of SR 4.6.2.3.b.1 SR 4.6.2.3.b.1 currently requires Starting (unless already operating) each fan from the control room in low speed. The proposed change deletes this requirement and replaces it with the word Deleted.

The safety function of the CFCUs is to automatically start on a safety injection signal and provide cooling to containment. Manually starting the fans from the control room is not necessary to demonstrate operability or confirm that the LCO is met. SR 4.6.2.3.b.2 remains in place and continues to verify operability by requiring each fan to operate for at least 15 minutes in accordance with the SFCP, regardless of how the fan is started.

The staff finds the deletion of SR 4.6.2.3.b.1 acceptable because the remaining surveillance requirements adequately verify equipment operability and assure the LCO will be met, and it is consistent with NUREG 1431.

3.1.2 Evaluation of relocation of SRs 4.6.2.3.b.2 and 4.6.2.3.c.1 details to Bases The current SR 4.6.2.3.b.2 states, Verifying that each fan operates for at least 15 minutes in low speed, and the current SR 4.6.2.3.c.1 states Each fan starts automatically in low speed.

For both SRs, the words in low speed are proposed to be deleted from the SR and relocated to the TS Bases, which is a licensee-controlled document. Changes to the TS Bases are controlled in accordance with Salem, Unit 1, TS 6.17 and Salem, Unit 2, TS 6.16, Technical Specification (TS) Bases Control Program.

The NRC staff finds that the proposed relocation of the details for fan speed are acceptable because the revised SRs will continue to ensure the fans are operable, and the LCO will be met by requiring each fan to automatically start and operate for at least 15 minutes, and this change is consistent with NUREG-1431, SR 3.6.6A.2 and SR 3.6.6A.8.

3.1.3 Evaluation of SR 4.6.2.3.c changes The current SR 4.6.2.3.c states In accordance with the Surveillance Frequency Control Program by: verifying that on a safety injection test signal. The proposed change would replace a safety injection test signal with an actual or simulated actuation signal. The purpose of this SR is to verify the operability of the CFCUs by verifying that each fan starts and automatic valves and dampers actuate to their correct positions, and the cooling water flowrate is sufficient. This change allows taking credit for actual system actuation if sufficient information is collected to satisfy the surveillance test requirements. The NRC staff finds that allowing the SR to be confirmed by normal system actuation as well as a test signal is acceptable because it will continue to verify that the CFCUs can perform their specified safety function, the LCO is met, and it is consistent with NUREG-1431, SR 3.6.6A.2 and SR 3.6.6A.8.

3.2 NRC Staff Conclusion

Based on the review described above, the NRC staff finds that the proposed changes to SR 4.6.2.3 meet the requirements of 10 CFR 50.36(c)(3) because the modified SRs will continue to confirm that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met. The NRC staff also confirmed that the proposed changes align with the Commissions Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, as they are consistent with the corresponding STSs in NUREG-1431. Therefore, the NRC staff concludes the proposed amendment is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the New Jersey State official was notified of the proposed issuance of the amendments on July 10, 2025. On July 15, 2025, the State official confirmed that the State of New Jersey had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration published in the Federal Register on May 14, 2025 (90 FR 20513) and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: Joshua Wilson, NRR Hanry Wagage, NRR Rob Atienza, NRR Date: August 5, 2025

ML25191A194 NRR-058 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL1/LA NRR/DSS/SCPB/BC NAME SWilliams KEntz MValentin DATE 07/10/2025 07/28/2025 07/31/2025 OFFICE NRR/DSS/STSB/BC NRR/DORL/LPL1/BC NAME SMehta HGonzález DATE 08/05/2025 08/05/2025