ML25218A145

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Unit 2 and Waterford Steam Electric Station, Unit 3 – Issuance of Amendment Nos. 337 and 276, Respectively Related to Adoption of TSTF-589 (EPID L-2025-LLA-0023)
ML25218A145
Person / Time
Site: Waterford 
Issue date: 08/18/2025
From: Michael Mahoney, Tony Nakanishi
NRC/NRR/DORL/LPL4
To: Gustafson O
Entergy Operations
Drake, Jason
References
EPID L-2025-LLA-0023 TSTF-589
Download: ML25218A145 (1)
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Text

August 18, 2025 Mr. Otto Gustafson Vice President, Regulatory Assurance Entergy Services, LLC M-ECH-29 1340 Echelon Parkway Jackson, MS 39213

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT 2; WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENTS RELATED TO ADOPTION OF TSTF-589 (EPID L-2025-LLA-0023)

Dear Mr. Gustafson:

The U.S. Nuclear Regulatory Commission (the Commission) has issued amendments consisting of changes to the technical specifications (TSs) in response to your application dated February 3, 2025. The following amendments are enclosed:

Amendment No. 337 to Renewed Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2);

Amendment No. 276 to Renewed Facility Operating License No. NPF-38 for Waterford Steam Electric Station, Unit 3 (Waterford 3).

The amendments revised the TS for ANO-2 and Waterford 3. Specifically, the amendments revise the TS to eliminate the requirements for automatic diesel generator start and loading during plant shutdown. The proposed changes are consistent with Technical Specifications Task Force (TSTF) Traveler, TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown, Revision 0.

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

Sincerely,

/RA/

Michael Mahoney, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-368, 50-382

Enclosures:

1. Amendment No. 337 to NPF-6
2. Amendment No. 276 to NPF-38
3. Safety Evaluation cc: Listserv

ENTERGY OPERATIONS, INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 337 Renewed License No. NPF-6

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee), dated February 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 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; 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. NPF-6 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 337, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Tony Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-6 and the Technical Specifications Date of Issuance: August 18, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.08.18 13:39:20 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 337 RENEWED FACILITY OPERATING LICENSE NO. NPF-6 ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 Replace the following pages of Renewed Facility Operating License No. NPF-6 and 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.

Renewed Facility Operating License REMOVE INSERT 3

3 Technical Specifications REMOVE INSERT 3/4 8-5 3/4 8-5

Renewed License No. NPF-6 Amendment No. 337 3

(4)

EOI, 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)

EOI, 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)

EOI, 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 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 EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 3026 megawatts thermal. Prior to attaining this power level EOI shall comply with the conditions in Paragraph 2.C.(3).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 337, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

Exemptive 2nd paragraph of 2.C.2 deleted per Amendment 20, 3/3/81.

(3)

Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following issuance of the renewed license or within the operational restrictions indicated.

The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.

2.C.(3)(a)

Deleted per Amendment 24, 6/19/81.

ARKANSAS - UNIT 2 3/4 8-5 Amendment No. 149,255,322,327 337 ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b.

One diesel generator with:

1.

A day fuel tank containing a minimum volume of 300 gallons of fuel, 2.

A fuel storage system, and 3.

A fuel transfer pump.

APPLICABILITY:

MODES 5 and 6, or during movement of recently irradiated fuel assemblies or movement of new fuel assemblies over recently irradiated fuel assemblies.

ACTION:

Note: Enter applicable ACTIONs of LCO 3.8.2.2, "A.C. Distribution - Shutdown," and LCO 3.8.2.4, "D.C. Sources - Shutdown," with one required train de-energized.

With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend the movement of recently irradiated fuel assemblies, the movement of new fuel assemblies over recently irradiated fuel assemblies, and operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

SURVEILLANCE REQUIREMENT 4.8.1.2 Note: The following SRs are not required to be performed:

SR 4.8.1.1.2.a.5 SR 4.8.1.1.2.c.3 SR 4.8.1.1.2.c.4 SR 4.8.1.1.2.c.9 SR 4.8.1.1.2.c.10 SR 4.8.1.1.2.c.11 The following SRs are applicable for A.C. sources required to be OPERABLE:

SR 4.8.1.1.1.a SR 4.8.1.1.2.a.1 SR 4.8.1.1.2.a.3 SR 4.8.1.1.2.a.5 SR 4.8.1.1.2.c.3 SR 4.8.1.1.2.c.4 SR 4.8.1.1.2.c.9 SR 4.8.1.1.2.c.10 SR 4.8.1.1.2.c.11 SR 4.8.1.1.2.c.13

ENTERGY OPERATIONS, INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 276 Renewed License No. NPF-38

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (EOI),dated February 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 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; 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 Facility Operating License No. NPF-38 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. 276, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Tony Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-38 and the Technical Specifications Date of Issuance: August 18, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.08.18 13:39:46 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 Replace the following pages of Renewed Facility Operating License No. NPF-38 and 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.

Renewed Facility Operating License REMOVE INSERT 4

4 Technical Specifications REMOVE INSERT 3/4 8-8 3/4 8-8 the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on 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 EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the conditions specified herein.

2.

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 276, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

Antitrust Conditions (a)

Entergy Louisiana, LLC shall comply with the antitrust license conditions in Appendix C to this renewed license.

(b)

Entergy Louisiana, LLC is responsible and accountable for the actions of its agents to the extent said agent's actions contravene the antitrust license conditions in Appendix C to this renewed license.

AMENDMENT NO. 276

WATERFORD - Unit 3 3/4 8-8 AMENDMENT NO.

199,216,235, 251, 276 ELECTRICAL POWER SYSTEMS A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b.

One diesel generator with:

1.

A diesel oil feed tank containing a minimum one hour supply of fuel, and 2.

The diesel fuel oil storage tanks, and 3.

A fuel transfer pump.

APPLICABILITY:

MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, operations involving positive reactivity additions that could result in loss of required SHUTDOWN MARGIN or boron concentration, or load movements with or over irradiated fuel. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the top of the fuel seated in the reactor pressure vessel, immediately initiate corrective action to restore the required sources to OPERABLE status.

SURVEILLANCE REQUIREMENT 4.8.1.2 Note: The following SRs are not required to be performed:

SR 4.8.1.1.2a.5 SR 4.8.1.1.2e.1 SR 4.8.1.1.2e.2 SR 4.8.1.1.2e.6a SR 4.8.1.1.2e.6b SR 4.8.1.1.2e.7 SR 4.8.1.1.2e.8 The following SRs are applicable for A.C. sources required to be OPERABLE:

SR 4.8.1.1.1a SR 4.8.1.1.2a.1 SR 4.8.1.1.2a.3 SR 4.8.1.1.2a.4b SR 4.8.1.1.2a.5 SR 4.8.1.1.2b SR 4.8.1.1.2e.1 SR 4.8.1.1.2e.2 SR 4.8.1.1.2e.6a SR 4.8.1.1.2e.6b SR 4.8.1.1.2e.7 SR 4.8.1.1.2e.8 SR 4.8.1.1.2e.10

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 337 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-6, AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT 2 WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NOS. 50-368 AND 50-382 1.0 INTRODUCTION By letter CNRO2024-00013, dated February 3, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25034A156), Entergy Operations Inc (Entergy, the licensee), requested changes to the technical specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2) and Waterford Steam Electric Station, Unit 3 (Waterford 3), by license amendment request (LAR, application). In its LAR, Entergy requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed LAR under the Consolidated Line-Item Improvement Process (CLIIP).

The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-589, Revision 0, Eliminate Automatic Diesel Generator Start During Shutdown (TSTF-589) (ML22034A015), and the associated NRC staff safety evaluation (SE) of TSTF-589 (ML23241B040).

The proposed changes would eliminate the TS requirements for the automatic diesel generator (DG) start and loading capability to be operable during shutdown and modify which DG surveillance requirements (SRs) are required during shutdown.

2.0 REGULATORY EVALUATION

2.1 System Description The Class 1E alternating current (AC, A.C.) electrical power system provides a reliable source of power to the engineered safety feature (ESF) systems. The design provides independence and redundancy to ensure a reliable source of power to the Class 1E system. The AC electrical power system includes offsite power sources and Class 1E onsite standby power sources (i.e.,

DGs) that supply electrical power to the plant load groups, with each load group powered by an independent Class 1E ESF bus. Each ESF bus has connections to offsite power sources and one or more DGs.

DGs provide AC power during a loss of offsite power (LOOP). A DG starts automatically on a LOOP signal based on an ESF bus degraded voltage or undervoltage signal, or an ESF (safety injection) signal. After the DG starts, it automatically ties to its respective Class 1E ESF bus in case of LOOP signal, or coincident with, an ESF signal. In the event of a LOOP or LOOP coincident with an accident, the ESF electrical loads are automatically connected to the DG in time to provide for safe reactor shutdown and to mitigate the consequences of a design-basis accident such as a loss-of-coolant accident (LOCA).

2.2 Proposed TS Changed to Adopt TSTF-589 ANO-2 TS Changes Current TS 3.8.1, A.C. Sources, Limiting Condition for Operation (LCO) 3.8.1.1, contains requirements on AC sources (offsite power and DGs) in Modes 1, 2, 3, and 4. SR 4.8.1.2 states that all of the TS 4.8.1.1.1 and 4.8.1.1.2 SRs are applicable during shutdown, except for SR 4.8.1.2a.5. SR 4.8.1.2 would be revised to state which of the TS 4.8.1 SRs are not required to be performed, in addition to state which SRs are application for AC sources required to be OPERABLE.

The automatic start and loading capabilities of the DGs are no longer required to be operable during shutdown and the SRs which test the automatic start are no longer applicable during shutdown. SR 4.8.1.2 is revised to state that [t]he following SRs are applicable for AC sources required to be OPERABLE: SR 4.8.1.1.1.a, SR 4.8.1.1.1.a.1, SR 4.8.1.1.1.a.3, SR 4.8.1.1.1.a.5, SR 4.8.1.1.1.c.3, SR 4.8.1.1.1.c.4, SR 4.8.1.1.1.c.9, SR 4.8.1.1.1.c.10, SR 4.8.1.1.1.c.11, and SR 4.8.1.1.1.c.13.

A new Note is added to state that,, [t]he following SRs are not required to be performed: SR 4.8.1.1.1.a.5, SR 4.8.1.1.1.c.3, SR 4.8.1.1.1.c.4, SR 4.8.1.1.1.c.9, SR 4.8.1.1.1.c.10, and SR 4.8.1.1.1.c.11.

Waterford 3 TS Changes Current TS 3.8.1.1, A.C. Sources, Limiting Condition for Operation 3.8.1.1, contains requirements on AC sources (offsite power and DGs) in Modes 1, 2, 3, and 4. SR 4.8.1.2 states that all of the TS 4.8.1.1.1 and 4.8.1.1.2 SRs are applicable during shutdown, except for SR 4.8.1.1.2a.5. SR 4.8.1.2 would be revised to state which of the TS 3.8.1 SRs are applicable instead of the TS 3.8.1 SRs that are not required to be performed, in addition to state which SRs are application for AC sources required to be OPERABLE.

The automatic start and loading capabilities of the DGs are no longer required to be operable during shutdown and the SRs which test the automatic start are no longer applicable during shutdown. SR 4.8.1.2 is revised to state that [t]he following SRs are applicable for AC sources required to be OPERABLE: SR 4.8.1.1.1.a, SR 4.8.1.1.1.a.1, SR 4.8.1.1.1.a.3, SR 4.8.1.1.1.a.4b, SR 4.8.1.1.1.a.5, SR 4.8.1.1.1.2b, SR 4.8.1.1.1.2e.1, SR 4.8.1.1.1.2e.2, SR 4.8.1.1.1.2e.6a, SR 4.8.1.1.1.2e.6b, SR 4.8.1.1.1.2e.7, SR 4.8.1.1.1.2e.8, and SR 4.8.1.1.1.2e.10.

A new Note is added to state, [t]he following SRs are not required to be performed: SR 4.8.1.1.2a.5, SR 4.8.1.1.2e.1, SR 4.8.1.1.2e.2, SR 4.8.1.1.2e.6b, SR 4.8.1.1.2e.7, and SR 4.8.1.1.2e.8.

2.2.1 Variations That Do Not Affect the Applicability of the Traveler ANO-2 The licensee noted that ANO-2 TSs have different numbering and titles than standard technical specifications (STSs).

1. The existing ANO-2 SR 4.8.1.1.2.a differs from the STS TS 3.8.1 SRs. This surveillance contains multiple steps that align more than one STS. SR 4.8.1.1.2.a.4, which is related to a minimum timed start, is modified by a Note which requires performing the minimum time start on a basis consistent with STS SR 3.8.1.7. Therefore, SR 4.8.1.1.2.a.4 will be reflected in SR 4.8.1.2 as not required to be met and not required to be performed.
2. The existing ANO-2 SR 4.8.1.1.2.a.6 does not have an equivalent specification in STS TS 3.8.1 SRs. SR 4.8.1.1.2.a.6 verifies that the DG is aligned to provide standby power to the associated emergency busses. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the required automatic DG start and loading. Alignment of the DG to the safety buses will be accomplished manually by an operator. Therefore, SR 4.8.1.1.2.a.6 will be reflected in SR 4.8.1.2 as not required to be met and not required to be performed.
3. The existing ANO-2 SR 4.8.1.1.2.c.10 does not have an equivalent surveillance in STS TS 3.8.1 SRs. SR 4.8.1.1.2.c.10 verifies that the auto-connected loads to each DG do not exceed the 2-hour rating of 3135 kilowatt (kW). TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the automatic DG start and loading.

Verification of auto-connected loads is not required in MODES 5 and 6. This SR has similar conditions to STS SR 3.8.1.14, which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and not required to be performed. Therefore, SR 4.8.1.1.2.c.10 will be shown in SR 4.8.1.2 as required to be met and not required to be performed.

4. The existing ANO-2 TS 4.8.1.1.2.c.13 does not have an equivalent surveillance in STS TS 3.8.1 SRs. SR 4.8.1.1.2.c.13 verifies that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross connection lines. This SR is similar to STS SR 3.8.1.4, which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and required to be performed. Therefore, SR 4.8.1.1.2.c.13 will be shown in SR 4.8.1.2 as required to be met and required to be performed.

Waterford 3 The licensee noted that Waterford TSs have different numbering and titles than STSs.

1. The existing Waterford 3 SR 4.8.1.1.2a differs from the STS TS 3.8.1 SRs. This surveillance contains multiple steps that align with more than one STS. SR 4.8.1.1.2a.4a, which is related to a minimum timed start, is consistent with STS SR 3.8.1.7. TSTF-589 removed the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.1.7), the minimum start time since there is no minimum DG start time assumed during shutdown. Therefore, SR 4.8.1.1.2a.4a will be reflected in SR 4.8.1.2 as not required to be met and not required to be performed. SR 4.8.1.1.2a.4b is consistent with STS SR 3.8.2.1 and is listed as required to be met and required to be performed.
2. The existing Waterford 3 SR 4.8.1.1.2e.6 differs from the STS 3.8.1 SRs. This surveillance generally aligns with STS SR 3.8.1.14. Steps c and d of this surveillance are related to a minimum timed start and there is no equivalent time requirement in STS SR 3.8.1.14. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the minimum start time. This SR is split to support continuing to meet the requirements of SR 4.8.1.1.2e.6a and b that align with SR 3.8.1.14, while removing the minimum start time requirement of SR 4.8.1.1.2e.6c and d to not required to be met and not required to be performed.
3. The existing Waterford 3 SR 4.8.1.1.2a.6 does not have an equivalent specification in STS TS 3.8.1 SRs. SR 4.8.1.1.2a.6 verifies that the DG is aligned to provide standby power to the associated emergency busses. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the required automatic DG start and loading. Alignment of the DG to the safety buses will be accomplished manually by an operator. Therefore, SR 4.8.1.1.2a.6 will be reflected in SR 4.8.1.2 as not required to be met and not required to be performed.
4. The existing Waterford 3 TS 4.8.1.1.2e.7 does not have an equivalent specification in STS 3.8.1 SRs. SR 4.8.1.1.2e.7 verifies that the auto-connected loads and permanently connected loads to each DG do not exceed the 2000-hour rating of 4400 kW. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the required automatic DG start and loading. Verification of the auto and permanently connected loads is similar to SR 4.8.1.1.2e.6a and b (STS SR 3.8.1.14). SR 4.8.1.1.2e.7 will be shown in SR 4.8.1.2 as required to be met and not required to be performed, which is consistent with SR 4.8.1.1.2e.6a and b changes.
5. The existing Waterford 3 SR 4.8.1.1.2e.10 does not have an equivalent specification in STS TS 3.8.1 SRs. SR 4.8.1.1.2e.10 verifies that the fuel transfer pump transfers fuel from each diesel oil feed tank by taking suction from the opposite train fuel oil storage tank. This SR is similar to SR 4.8.1.1.2a.1 (STS 3.8.1.4) which is required to be met and required to be performed. SR 4.8.1.1.2e.10 will be changed to the same.

2.3 Regulatory Requirements 2.3.1 Applicable Regulatory Requirements The categories of items required to be in the TSs are listed in Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c). The regulation at 10 CFR 50.36(c)(2) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that

[w]hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut

down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.

The regulation at 10 CFR 50.36(c)(3) requires that TSs include items in the category of SRs, which 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 limiting conditions for operation will be met.

2.3.2 Applicable Regulatory Guidance 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, 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 NRC NUREG-1432, Standard Technical Specifications, Combustion Engineering Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21258A421 and ML21258A424, respectively), as modified by NRC-approved traveler.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-589 The NRC staff compared the proposed TS changes described in section 1.1 of this SE against the changes approved in TSTF-589. In accordance with SRP Chapter 16.0, the NRC staff determined that TSTF-589 is applicable to the proposed TS changes because ANO-2 and Waterford 3 are pressurized-water reactor (PWR) design plants, and the NRC staff approved the TSTF-589 changes for PWR designs. The NRC staff finds that the proposed changes to the ANO-2 and Waterford 3 TSs described in section 2.2 of this SE are consistent with those found acceptable in TSTF-589.

In the NRC SE for TSTF-589, the NRC staff concluded that the proposal to eliminate the TS requirements for the automatic DG start and loading capability to be operable during shutdown and the modification of which DG SRs are applicable during shutdown, is acceptable. Testing of the DG automatic start and load capabilities is not required to demonstrate the operability of the DG during shutdown conditions, because the DG automatic start is not required to mitigate the consequences of postulated events in shutdown conditions.

Therefore, 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3) will continue to be met because the revised SR 4.8.2.1 will continue to assure that the necessary quality of the onsite standby power systems and components is maintained, that facility operation will be within safety limits, and that the associated LCOs will be met. Thus, the proposed changes continue to meet the requirements of 10 CFR 50.36(c), and therefore acceptable.

3.2 Additional Proposed TS Changes 3.2.1 Variations That Do Not Affect the Applicability of the Traveler ANO-2 Variations

1. In the LAR, the licensee stated that the existing SR 4.8.1.1.2.a differs from the STS TS 3.8.1 SRs because it contains multiple steps that align with more than one STS.

SR 4.8.1.1.2.a.4 is related to performing a minimum timed start on a basis consistent with STS SR 3.8.1.7. TSTF-589 removes the requirement to perform STS 3.8.1.7, the minimum start time, since there is no minimum DG start time assumed during shutdown.

The NRC staff reviewed the proposed change for SR 4.8.1.1.2.a.4 to not required to be met and not required to be performed. The proposed SR 4.8.1.1.2.a.4 aligns with STS SR 3.8.1.7 and is consistent with TSTF-589. Therefore, the NRC staff finds the change to be acceptable.

2. In the LAR, the licensee stated that SR 4.8.1.1.2.a.6 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes to change SR 4.8.1.1.2.a.6 to not required to be met and not required to be performed. SR 4.8.1.1.2.a.6 verifies that the DG is aligned to provide standby power to the associated emergency buses. The NRC staff reviewed the proposed change and determined that it aligns with the intent of TSTF-589 by not requiring SR 4.8.1.1.2.a.6 to be required to be met or performed because it is currently required during an automatic DG start and loading. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the automatic DG start and loading. The licensee stated that alignment of the DG to the safety buses will be accomplished manually by an operator. The proposed change continues to meet the intent of TSTF-589 and, therefore, is acceptable.
3. In the LAR, the licensee stated that SR 4.8.1.1.2.c.10 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes to change SR 4.8.1.1.2.c.10 to, required to be met and not required to be performed. SR 4.8.1.1.2.c.10 verifies that the auto-connected loads to each DG do not exceed the 2-hour rating of 3135 Kw.

TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the automatic DG start and loading. Verification of auto-connected loads is not required in MODES 5 and 6. The NRC staff reviewed the proposed change and determined that it aligns with the intent of TSTF-589 by requiring SR 4.8.1.1.2.c.10 to be met but not performed, because it is currently required during an automatic DG start and loading.

The NRC staff confirmed that SR 4.8.1.1.2.c.10 has similar conditions to STS SR 3.8.1.14 which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and not required to be performed. The proposed change continues to meet the intent of TSTF-589 and, therefore, is acceptable.

4. In the LAR, the licensee stated that SR 4.8.1.1.2.c.13 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes not changing SR 4.8.1.1.2.c.13 and will remain as required to be met and required to be performed.

This SR is similar to STS SR 3.8.1.4 which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and required to be performed. The NRC staff reviewed the differences in SR 4.8.1.1.2c.13 and SR 3.8.1.4 and confirmed that they are similar and continues to meet the intent of TSTF-589 and, therefore, is acceptable.

Waterford 3 Variations

1. In the LAR, the licensee stated that the existing SR 4.8.1.1.2a differs from the STS TS 3.8.1 SRs because it contains multiple steps that align with more than one STS.

SR 4.8.1.1.2a.4a is related to performing a minimum timed start on a basis consistent with STS SR 3.8.1.7. TSTF-589 removes the requirement to perform STS 3.8.1.7 since there is no minimum DG start time assumed during shutdown. The NRC staff reviewed the proposed change for SR 4.8.1.1.2a.4a to not required to be met and not required to be performed. The proposed SR 4.8.1.1.2a.4 aligns with STS SR 3.8.1.7 and is consistent with TSTF-589. Therefore, the NRC staff finds the change to be acceptable.

2. In the LAR, the licensee stated that SR 4.8.1.1.2a.6 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes to change SR 4.8.1.1.2a.6 to not required to be met and not required to be performed. SR 4.8.1.1.2a.6 verifies that the DG is aligned to provide standby power to the associated emergency buses. The NRC staff reviewed the proposed change and determined that it aligns with the intent of TSTF-589 by not requiring SR 4.8.1.1.2a.6 to be required to be met or performed because it is currently required during an automatic DG start and loading. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the automatic DG start and loading. The licensee stated that alignment of the DG to the safety buses will be accomplished manually by an operator. The proposed change continues to meet the intent of TSTF-589 and, therefore, is acceptable.
3. In the LAR, the licensee stated that the existing SR 4.8.1.1.2e.6 differs from the STS TS 3.8.1 and with STS 3.8.1.14. The licensee proposes to change SR 4.8.1.1.2e.6c and d to not required to be met and not required to be performed. Steps c and d of this surveillance are related to a minimum timed start and there is no equivalent time requirement in STS SR 3.8.1.14. The NRC staff reviewed the proposed change and determined that it aligns with the intent of TSTF-589 by not requiring SR 4.8.1.1.2e.6c and d to be required to be met or performed because it is currently required during an automatic DG start and loading. TSTF-589 removes the requirement to demonstrate in SR 4.8.1.2 (STS SR 3.8.2.1), the automatic DG start and loading. The proposed change continues to meet the intent of TSTF-589 and, therefore, is acceptable.
4. In the LAR, the licensee stated that SR 4.8.1.1.2e.7 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes to change SR 4.8.1.1.2e.7 to required to be met and not required to be performed. SR 4.8.1.1.2e.7 verifies that the auto-connected loads and permanently connected loads to each DG do not exceed the 2000-hour rating of 4400 kW. TSTF-589 removes the requirement to demonstrate the automatic DG start and loading in SR 4.8.1.2 (STS SR 3.8.2.1). Verification of auto-connected loads is not required in MODES 5 and 6. The NRC staff reviewed the proposed change and determined that it aligns with the intent of TSTF-589 by requiring SR 4.8.1.1.2e.7 to be met but not performed, because it is currently required during an automatic DG start and loading. The NRC staff confirmed that SR 4.8.1.1.2e.7 has similar conditions to STS SR 3.8.1.14 which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and not required to be performed. The proposed change continues to meet the intent of TSTF-589 and, therefore, is acceptable.
5. In the LAR, the licensee stated that SR 4.8.1.1.2e.10 does not have an equivalent specification in STS TS 3.8.1 SRs. The licensee proposes not changing SR 4.8.1.1.2e.10 and will remain as required to be met and required to be performed.

This SR is similar to STS SR 3.8.1.4 which is identified in TSTF-589 STS SR 3.8.2.1 as required to be met and required to be performed. The NRC staff reviewed the differences in SR 4.8.1.1.2e.10 and SR 3.8.1.4 and confirmed that they are similar and continues to meet the intent of TSTF-589 and, therefore, is acceptable.

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, State officials for Arkansas and Louisiana were notified of the proposed issuance of the amendments on July 31, 2025. The State officials had no comments.

5.0 ENVIRONMENTAL CONSIDERATION The amendments change requirements with respect to installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change SRs pursuant to 10 CFR 50.36(c)(3). 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 20517), 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: T. Sweat, NRR M. Mahoney, NRR Date: August 18, 2025

ML25218A145

  • by eConcurrence OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA*

NRR/DSS/STSB/BC*

NAME MMahoney PBlechman SMehta DATE 08/13/2025 8/13/2025 07/17/2025 OFFICE NRR/DORL/LPL4/BC*

NRR/DORL/LPL/PM*

NAME TNakanishi MMahoney DATE 08/18/2025 08/18/2025

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