ML25225A243

Amendment to Adopt TSTF-541

ML25225A243
Person / Time
Site:	Prairie Island
Issue date:	08/25/2025
From:	Wetzel B Office of Nuclear Reactor Regulation
To:	Paulhardt W Northern States Power Co
Ballard, Brent
References
EPID L-2025-LLA-0047 TSTF-541
Download: ML25225A243 (1)

Text

August 25, 2025 Mr. Werner Paulhardt Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

ISSUANCE OF AMENDMENT NOS. 248 AND 236 RE: REVISION OF THE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-541, ADD EXCEPTIONS TO SURVEILLANCE REQUIREMENTS FOR VALVES AND DAMPERS LOCKED IN THE ACTUATED POSITION (EPID L-2025-LLA-0047)

Dear Mr. Paulhardt:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 248 to Renewed Facility Operating License No. DPR-42 and Amendment No. 236 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the technical specifications (TSs) in response to your application dated March 12, 2025, as supplemented by letter dated April 15, 2025.

The amendments revise certain TS surveillance requirements (SRs) by adding exceptions to the SRs for when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position, in order to consider the SR met based on the TS Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19240A315), and the NRC associated safety evaluation for TSTF-541, Revision 2 (ML19323E926).

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's monthly Federal Register notice.

Sincerely,

/RA/

Beth Wetzel, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosures:

1. Amendment No. 248 to DPR-42

2. Amendment No. 236 to DPR-60

3. Safety Evaluation cc: Listserv

NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 Renewed License No. DPR-42

1.

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

A.

The application for amendment by Northern States Power Company (NSPM, the licensee), dated March 12, 2025, as supplemented by letter dated April 15, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 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 Commission's regulations; 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 Commission's 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-42 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 248, are hereby incorporated in the renewed operating license. NSPM shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 25, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.08.25 11:47:02 -04'00'

NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 236 Renewed License No. DPR-60

1.

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

A.

The application for amendment by Northern States Power Company (NSPM, the licensee), dated March 12, 2025, as supplemented by letter dated April 15, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 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 Commission's regulations; 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 Commission's 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-60 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 236, are hereby incorporated in the renewed operating license. NSPM shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 25, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.08.25 15:09:21 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 248 AND 236 RENEWED FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Renewed Facility Operating License Nos. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by a marginal line.

Renewed Facility Operating License No. DPR-42 REMOVE INSERT Page 3 Page 3 Renewed Facility Operating License No. DPR-60 REMOVE INSERT Page 3 Page 3 Technical Specifications Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.6.9-2 3.6.9-2 3.7.10-4 3.7.10-4 3.7.12-3 3.7.12-3 Renewed Operating License No. DPR-42 Amendment No. 248 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM 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; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM 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 and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 248, are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Renewed Operating License No. DPR-60 Amendment No. 236 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM 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; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM 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 and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purposes of volume reduction and decontamination.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l:

Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 236 are hereby incorporated in the renewed operating license.

NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains

SBVS 3.6.9 Prairie Island Unit 1 - Amendment No. 248 Units 1 and 2 3.6.9-2 Unit 2 - Amendment No. 236 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.9.2 Perform required SBVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.6.9.3 Verify each SBVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.6.9.4 Verify SBVS isolation dampers actuate on an actual or simulated signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

CRSVS 3.7.10 Prairie Island Unit 1 - Amendment No. 248 Units 1 and 2 3.7.10-4 Unit 2 - Amendment No. 236 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRSVS train > 15 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Perform required CRSVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with VFTP SR 3.7.10.3 Verify each CRSVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Verify each CRSVS train in the Emergency Mode delivers 3600 to 4400 cfm through the associated CRSVS filters.

In accordance with the Surveillance Frequency Control Program SR 3.7.10.5 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

In accordance with the Control Room Habitability Program

ABSVS 3.7.12 Prairie Island Unit 1 - Amendment No. 248 Units 1 and 2 3.7.12-3 Unit 2 - Amendment No. 236 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.12.2 Perform required ABSVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.12.3 Verify each ABSVS train can produce a negative pressure within 20 minutes after initiation.

In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Verify each ABSVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 236 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 NORTHERN STATES POWER COMPANY - MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306

1.0 PROPOSED CHANGE

S By application dated March 12, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25071A416), as supplemented by letter dated April 15, 2025 (ML25105A222), Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), requested changes to the Technical Specifications (TSs) for Prairie Island Nuclear Generating Plant (Prairie Island, PINGP), Units 1 and 2. The license amendment request (LAR, application) is based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ML19240A315), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission) staff safety evaluation (SE) of TSTF-541 (ML19323E926).

Limiting Conditions for Operation (LCOs) in the TS identify the lowest functional capability or performance level of equipment required for safe operation of the facility. Surveillance requirements (SRs) are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. Several existing SRs require the licensee to verify that each train of specified trains actuates on an actual or simulated actuation signal. When the trains actuate, valves and dampers within the trains will, if needed, reposition to their actuated position, which is the position appropriate to respond to the transient or accident that caused the actuation. The proposed amendment would eliminate the need to verify that a damper or valve has repositioned if the damper or valve is secured in its actuated position by adding a phrase to each SR as described in Section 1.2 of this SE.

The proposed amendment is based on TSTF Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ML19240A315), and the associated NRC staff SE of TSTF-541 (ML19323E926). Section 1.1 of the NRC staffs SE of TSTF-541 discusses the reason for the proposed changes.

1.1 System Descriptions The control room special ventilation system (CRSVS) provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The purpose of SR 3.7.10.3 is to verify that each train/subsystem starts and operates on an actual or simulated actuation signal.

The shield building ventilation system (SBSVS) is required to ensure that radioactive materials that leak from the primary containment into the shield building (secondary containment) following a design-basis accident are filtered and adsorbed prior to exhausting to the environment. The containment has a secondary containment called the shield building, which is a concrete structure that surrounds the steel primary containment vessel. Between the containment vessel and the shield building inner wall is an annular space that collects any containment leakage that may occur following a loss-of-coolant accident (LOCA). The SBSVS establishes a negative pressure in the annulus between the shield building and the steel containment vessel. Filters in the system control the release of radioactive contaminants to the environment. The SBSVS consists of two separate and redundant trains. Each train includes a heater, cooling coils, a prefilter, moisture separators, a high-efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of radioiodines, and a fan. Ductwork, valves and/or dampers, and instrumentation also form part of the system. The system initiates and maintains negative air pressure in the shield building by means of filtered exhaust ventilation of the shield building following receipt of a safety injection signal. The purpose of SR 3.6.9.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal. The purpose of SR 3.6.9.4 is to verify proper actuation of isolation dampers on an actual or simulated actuation signal.

The auxiliary building special ventilation system (ABSVS), in conjunction with other normally operating systems, also provides environmental control of temperature and humidity in the emergency core cooling system (ECCS) pump room area and the lower reaches of the auxiliary building. Ductwork, valves or dampers, and instrumentation also form part of the system, as well as demisters functioning to reduce the relative humidity of the air stream. During emergency operations, the ABSVS dampers are realigned, and fans are started to begin filtration. Upon receipt of the actuating ECCS signal(s), normal air discharges from the ECCS pump room are isolated, and the stream of ventilation air is discharged through the system filter trains. The prefilters or demisters remove any large particles in the air, and any entrained water droplets present, to prevent excessive loading of the HEPA filters and charcoal adsorbers. The purpose of SR 3.7.12.4 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal.

1.2 Description of Proposed Changes to Adopt TSTF 541 In accordance with NRC staff-approved TSTF-541, the licensee proposed to revise certain SRs by adding exceptions to the SRs for automatic valves or dampers that are locked, sealed or otherwise secured in the actuated position. The proposed revisions, therefore, allow the licensee to meet the LCOs without having to test for actuation those valves or dampers that are already secured in the actuated position. Specifically, the licensee proposed the following changes to adopt TSTF-541. The proposed new text is shown in italics.

SR 3.6.9.3 Verify each SBVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.6.9.4 Verify each SBVS isolation dampers actuate on an actual or simulated signal, except for dampers that are locked, sealed, or otherwise secured in the open position.

SR 3.7.10.3 Verify each CRSVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.12.4 Verify each ABSVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

1.3 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.1, the licensee proposed the following variations.

1.3.1 Editorial Variations The licensee noted that PINPG, Units 1 and 2, TSs have different numbering and nomenclature than standard technical specifications (STSs).

2.0 REGULATORY EVALUATION

The regulation under 10 CFR 50.36(b) requires that:

Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information.] The Commission may include such additional technical specifications as the Commission finds appropriate.

Additionally, under 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The considerations for issuance of operating licenses in 10 CFR 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. The LAR asks for changes to SRs, which are controlled by 10 CFR 50.36(c)(3) (saying that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met). Accordingly, the amended SRs that no longer require verification of valves and dampers already in, and secured in, their actuated positions, must continue to provide reasonable assurance that the LCOs will be met and the other standards of 10 CFR 50.36(c)(3) will be met.

The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), March 2010 (ML100351425).

As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the NUREG-1431, Revision 5, Standard Technical Specifications, Westinghouse Plants (ML21259A155), as modified by NRC-approved travelers.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-541 The NRC staff compared the licensees proposed TS changes in Section 1.2 of this SE against the changes approved in TSTF-541. In accordance with the SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-541 are applicable to PINGP, Units 1 and 2, TSs because PINGP, Units 1 and 2, are Westinghouse Pressurized Water Reactor (PWR) designs and the NRC staff approved the TSTF-541 changes for Westinghouse PWR designs.

Therefore, the NRC staff concludes that the licensees proposed changes to the PINGP, Units 1 and 2, TSs in Section 1.2 of this SE are consistent with TSTF-541.

As defined in TS [1.1], a system, subsystem, train, component, or device shall be operable:

when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

The SRs, as proposed to be amended, would exclude the need to verify actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal.

The licensees LAR contains the following statements:

While the proposed exceptions permit automatic valves and dampers that are locked, sealed, or otherwise secured in the actuated position to be excluded from the SR in order to consider the SR met, the proposed changes will not permit a system that is made inoperable by locking, sealing, or otherwise securing an automatic damper in the actuated position to be considered operable. As stated in the SR 3.0.1 Bases:

"Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs."

NSPM acknowledges that under the proposed change, the affected valves and dampers may be excluded from the SR when locked, sealed or otherwise secured in the actuated position. However, if the safety analysis assumes movement from the actuated position following an event, or the system is rendered inoperable by locking, sealing, or otherwise securing the valve or damper in the actuated position, then the system cannot perform its specified safety function and is inoperable regardless of whether the SR is met.

NSPM acknowledges for components for which the SR allowance can be utilized, the SR must be verified to have been met within its required Frequency after removing the valve or damper from the locked, sealed or otherwise secured status. If the SR exception is utilized to not test the actuation of a valve or damper and the specified Frequency of the SR is exceeded without testing the component, the SR must be performed on the component when it is returned to service in order to meet the SR.

The licensee provided a verification statement in Section 2.3 to confirm that existing administrative processes will be used to assess the operability of the system or any supported systems when utilizing the SR allowances.

Given the above statements provided on the docket to adopt TSTF-541, the NRC staff determined that there is reasonable assurance that the licensee will continue to properly control affected equipment in accordance with existing regulations and requirements when using the exceptions added to the respective SRs.

The amended SRs will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position. But the NRC staff finds that it is not necessary to verify actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions Therefore, the NRC staff determined that the amended PINGP, Units 1 and 2, TSs will continue to meet 10 CFR 50.36(c)(3) because the revised SRs will continue to provide reasonable assurance that necessary quality of systems and components is maintained and that the LCOs will be met.

Thus, the proposed changes continue to meet the requirements of 10 CFR 50.36(c)(3) as discussed in Section 3.0 of the NRC staffs SE of TSTF-541.

3.2 Additional Proposed TS Changes 3.2.1 Editorial The licensee noted that PINGP, Units 1 and 2, TSs have different numbering and nomenclature than STS. The NRC staff finds that the different TS numbering and nomenclature changes are acceptable because they do not substantively alter TS requirements.

3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are therefore acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Minnesota State officials were notified of the proposed issuance of the amendments on June 10, 2025. The State officials had no comments.

5.0 ENVIORNMENTAL 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. 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 June 10, 2025 (90 FR 2440), 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: M. Schwieg J. Wilson Date of Issuance: August 25, 2025

ML25225A243 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NAME BWetzel SLent SMehta DATE 08/14/2025 8/18/2025 05/19/2025 OFFICE NRR/DORL/LPL3/BC(A)

NRR/DORL/LPL3/PM NAME IBerrios BWetzel DATE 08/20/2025/

08/25/2025