ML25059A409

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Issuance of Amendment Nos. 237 and 217, Respectively, to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
ML25059A409
Person / Time
Site: Grand Gulf, River Bend  
(NPF-029, NPF-047)
Issue date: 04/10/2025
From: Michael Mahoney
NRC/NRR/DORL/LPL4
To: Gustafson O
Entergy Services
Mahoney M, NRR/DORL/LPL4
References
EPID L-2024-LLA-0133
Download: ML25059A409 (1)
v • d • e


Text

April 10, 2025 Otto Gustafson Vice President Regulatory Assurance Entergy Services, LLC M-ECH-29 1340 Echelon Parkway Jackson, MS 39213

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 AND RIVER BEND STATION, UNIT 1 - ISSUANCE OF AMENDMENT NOS. 237 AND 217, RESPECTIVELY, TO ADOPT TSTF-592, REVISE AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INSTRUMENTATION REQUIREMENTS (EPID: L-2024-LLA-0133)

Dear Otto Gustafson:

The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued amendments in response to your application dated September 19, 2024. The following amendments are enclosed:

Amendment No. 237 to Renewed Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1;

Amendment No. 217 to Renewed Facility Operating License No. NPF-47 for River Bend Station, Unit 1; The amendments revise the technical specifications to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-592, Revise Automatic Depressurization System (ADS)

Instrumentation Requirements.

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. 50-416 and 50-458

Enclosures:

1. Amendment No. 237 to NPF-29
2. Amendment No. 217 to NPF-47
3. Safety Evaluation
4. Notices and Environmental Findings cc: Listserv

ENTERGY OPERATIONS, INC.

SYSTEM ENERGY RESOURCES, INC.

COOPERATIVE ENERGY, A MISSISSIPPI ELECTRIC COOPERATIVE ENTERGY MISSISSIPPI, LLC DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 237 Renewed License No. NPF-29

1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee), dated September 19, 2024, 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-29 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 237 are hereby incorporated into this renewed license. Entergy Operations, Inc. 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-29 and the Technical Specifications Date of Issuance: April 10, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.04.10 14:31:34 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 237 RENEWED FACILITY OPERATING LICENSE NO. NPF-29 GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 Replace the following pages of Renewed Facility Operating License No. NPF-29 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 Technical Specifications REMOVE INSERT 3.3-36 3.3-36 3.3-37 3.3-37 3.3-37a 3.3-37b 3.3-42 3.3-42 3.3-43 3.3-43

4 Amendment No. 237 amended, are fully applicable to the lessors and any successors in interest to those lessors, as long as the renewed license of GGNS Unit 1 remains in effect.

(b)

SERI is required to notify the NRC in writing prior to any change in (i) the terms or conditions of any new or existing sale or lease agreements executed as part of the above authorized financial transactions, (ii) the GGNS Unit 1 operating agreement, (iii) the existing property insurance coverage for GGNS Unit 1 that would materially alter the representations and conditions set forth in the Staff's Safety Evaluation Report dated December 19, 1988 attached to Amendment No. 54. In addition, SERI is required to notify the NRC of any action by a lessor or other successor in interest to SERI that may have an effect on the operation of the facility.

C.

The 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 Entergy Operations, Inc. is authorized to operate the facility at reactor core power levels not in excess of 4408 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 237 are hereby incorporated into this renewed license. Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

During Cycle 19, GGNS will conduct monitoring of the Oscillation Power Range Monitor (OPRM). During this time, the OPRM Upscale function (Function 2.f of Technical Specification Table 3.3.1.1-1) will be disabled and operated in an indicate only mode and technical specification requirements will not apply to this function. During such time, Backup Stability Protection measures will be implemented via GGNS procedures to provide an alternate method to detect and suppress reactor core thermal hydraulic instability oscillations. Once monitoring has been successfully completed, the OPRM Upscale function will be enabled and technical specification requirements will be applied to the function; no further operating with this function in an indicate only mode will be conducted.

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-36 Amendment No. 120, 234, 237 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.

(continued)

F.2 Place channel in trip.

96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCS or reactor core isolation cooling (RCIC) inoperable AND 8 days OR In accordance with the Risk Informed Completion Time Program G.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems (continued)

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-37 Amendment No. 120, 234, 237 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

(continued)

G.2 Restore channel to OPERABLE status.

96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCS or RCIC inoperable AND 8 days OR In accordance with the Risk Informed Completion Time Program H.

As required by Required Action A.1 and referenced in Table 3.3.5-1-1 H.1

NOTES----------

1.

Only applicable for Functions 4.e, 4.f, and 5.e.

2.

Only applicable when both ADS trip systems are inoperable due to LPCS/LPCI Pump Discharge Pressure -

High channels inoperable.

Declare ADS valves inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems (continued)

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-37a Amendment No. 237 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME H.

(continued)

H.2

NOTES----------

1.

Only applicable for Functions 4.e, 4.f, and 5.e.

2.

Only applicable when one ADS trip system is inoperable due to LPCS/LPCI Pump Discharge Pressure -

High channels inoperable.

Restore affected channels to OPERABLE status.

AND H.3 Restore channel to OPERABLE status.

96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels concurrent with HPCS or RCIC inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels 30 days (continued)

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-37b Amendment No. 237 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

Required Action and associated Completion Time of Condition B, C, D, E, F, G, or H not met.

I.1 Declare associated supported feature(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-42 Amendment No. 120, 207, 218, 237 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3.

HPCS System (continued) h.

Manual Initiation 1,2,3 1

C SR 3.3.5.1.6 NA 4.

Automatic Depressurzation System (ADS) Trip System A a.

Reactor Vessel Water Level - Low Low Low, Level 1 1,2 (d),3 (d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

-152.5 inches b.

Drywell Pressure -

High 1,2 (d),3 (d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 1.44 psig c.

ADS Initiation Timer 1,2 (d),3 (d) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 115 seconds d.

Reactor Vessel Water Level - Low, Level 3 (Confirmatory) 1,2 (d),3 (d) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 10.8 inches e.

LPCS Pump Discharge Pressure -

High 1,2 (d),3 (d) 2 H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 125 psig and 165 psig f.

LPCI Pump A Discharge Pressure

- High 1,2 (d),3 (d) 2 H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 115 psig and 135 psig (continued)

(d)

With reactor steam dome pressure > 150 psig.

ECCS Instrumentation 3.3.5.1 GRAND GULF 3.3-43 Amendment No. 120, 207, 218, 237 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.

ADS Trip system A (continued) g.

ADS Bypass Timer (High Drywell Pressure) 1,2(d),3(d) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 9.4 minutes h.

Manual Initiation 5.

ADS Trip System B 1,2(d),3(d) 2/system H

SR 3.3.5.1.6 NA a.

Reactor Vessel Water Level - Low Low Low, Level 1 1,2(d),3(d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

-152.5 inches b.

Drywell Pressure -

High 1,2(d),3(d) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 1.44 psig c.

ADS Initiation Timer 1,2(d),3(d) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 115 seconds d.

Reactor Vessel Water LeveL -

Low, Level 3 (Confirmatory) 1,2(d),3(d) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 10.8 inches e.

LPCI Pumps B & C Discharge Pressure - High 1,2(d),3(d) 2 per pump H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 115 psig and 135 psig f.

ADS Bypass Timer (High Drywell Pressure) 1,2(d),3(d) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 9.4 minutes g.

Manual Initiation 1,2(d),3(d) 2/system H

SR 3.3.5.1.6 NA (d)

With reactor steam dome pressure > 150 psig.

ENTERGY LOUISIANA, LLC AND ENTERGY OPERATIONS, INC.

DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 217 Renewed License No. NPF-47

1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee), dated September 19, 2024, 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, as amended, 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-47 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. 217 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.

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-47 and the Technical Specifications Date of Issuance: April 10, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.04.10 14:32:22 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 217 RENEWED FACILITY OPERATING LICENSE NO. NPF-47 RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458 Replace the following pages of Renewed Facility Operating License No. NPF-47 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 Technical Specifications Remove Insert 3.3-36a 3.3-36a 3.3-37 3.3-37 3.3-37a 3.3-37b 3.3-42 3.3-42 3.3-43 3.3-43 Amendment No. 217 (2)

EOI, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in accordance with the procedures and limitations set forth in this renewed license; (3)

EOI, pursuant to Section 103 of the Act and 10 CFR Part 70, to receive, possess and to 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)

EOI, pursuant to Section 103 of 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 Section 103 of 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 Section 103 of 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.

(7)

EOI, pursuant to the Act and 10 CFR Part 30, 40, and 70 to receive, possess and use, in amounts as required, such byproduct and special nuclear materials as may be produced by the operation of Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, Unit 1, River Bend Station, Unit 1, and Waterford Steam Electric Station, Unit 3, without restriction to chemical or physical form for the purposes of sample analysis, equipment calibration, or equipment repair.

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 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 3091 megawatts thermal (100% rated 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. 217 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.

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-36a Amendment No. 213,

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems (continued)

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-37 Amendment No. 81, 213

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.

(continued)

G.2 Restore channel to OPERABLE status.

NOTE---------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCS or RCIC inoperable AND

NOTE---------

The Risk Informed Completion Time Program is not applicable when a loss of function occurs.

8 days or in accordance with the Risk Informed Completion Time Program (continued)

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-37a Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

H.1 ----------------NOTES--------------

1. Only applicable for Functions 4.e, 4.f, and 5.e.
2. Only applicable when both ADS trip systems are inoperable due to LPCS/LPCI Pump Discharge Pressure -

High channels inoperable.

Declare ADS valves inoperable.

AND H.2 ----------------NOTES--------------

1. Only applicable for Functions 4.e, 4.f, and 5.e.
2. Only applicable when one ADS trip system is inoperable due to LPCS/LPCI Pump Discharge Pressure -

High channels inoperable.

Restore affected channels to OPERABLE status.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels concurrent with HPCS or RCIC inoperable AND (continued)

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-37b Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

(continued)

H.3 Restore channel to OPERABLE status.

8 days or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channels 30 days I.

Required Action and associated Completion Time of Condition B, C, D, E, F, G, or H not met.

I.1 Declare associated supported features(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-42 Amendment No. 81, 193,

Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

4.

Automatic Depressurization System (ADS) Trip System A

a.

Reactor Vessel Water Level Low Low Low, Level 1 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

-147 inches

b.

Drywell Pressure High 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 1.88 psid

c.

ADS Initiation Timer 1,2(b),3(b) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 117 seconds

d.

Reactor Vessel Water Level Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 8.7 inches

e.

LPCS Pump Discharge Pressure High 1,2(b),3(b) 2 H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 130 psig

f.

LPCI Pump A Discharge Pressure High 1,2(b),3(b) 2 H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 120 psig

g.

ADS Bypass Timer (High Drywell Pressure) 1,2(b),3(b) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 5.5 minutes

h.

Manual Initiation 1,2(b),3(b) 2 per system H

SR 3.3.5.1.6 NA (continued)

(b) With reactor steam dome pressure > 100 psig.

ECCS Instrumentation 3.3.5.1 RIVER BEND 3.3-43 Amendment No. 81, 193,

Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5.

ADS Trip System B

a.

Reactor Vessel Water Level Low Low Low, Level 1 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

-147 Inches

b.

Drywell Pressure High 1,2(b),3(b) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 1.88 psid

c.

ADS Initiation Timer 1,2(b),3(b) 1 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 117 seconds

d.

Reactor Vessel Water Level Low, Level 3 (Confirmatory) 1,2(b),3(b) 1 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 8.7 Inches

e.

LPCI Pumps B & C Discharge Pressure High 1,2(b),3(b) 2 per pump H

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 120 psig

f.

ADS Bypass Timer (High Drywell Pressure) 1,2(b),3(b) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 5.5 minutes

g.

Manual Initiation 1,2(b),3(b) 2 per system H

SR 3.3.5.1.6 NA (b) With reactor steam dome pressure > 100 psig.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-29 AND AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION, UNIT 1 RIVER BEND STATION, UNIT 1 DOCKET NOS. 50-416 AND 50-458 Application Safety Evaluation Date

September 19, 2024, ML24263A271 April 10, 2025 Principal Contributor to Safety Evaluation

K. West

1.0 PROPOSED CHANGE

S Entergy Operations, Inc. (the licensee) requested changes to the technical specifications (TSs) for Grand Gulf Nuclear Station, Unit 1 (Grand Gulf), and River Bend Station, Unit 1 (River Bend), by license amendment request (LAR, application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF)

Traveler TSTF-592, Revision 2, Revise Automatic Depressurization System (ADS)

Instrumentation Requirements (TSTF-592) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23256A352), correction letter (ML23283A002), and the associated NRC staff safety evaluation (SE) of Traveler TSTF-592 (ML24029A148).

The proposed changes would revise the Emergency Core Cooling System (ECCS)

Instrumentation, TS Actions related to ADS instrumentation monitoring channels.

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System Description===

The purpose of the ECCS instrumentation is to initiate appropriate responses from systems to ensure that the fuel is adequately cooled in the event of a design basis accident or transient.

The ECCS uses two independent methods (flooding and spraying) to cool the core during a loss-of-coolant accident (LOCA).

The low-pressure ECCS subsystems are designed to mitigate a large break LOCA where reactor vessel pressure rapidly decreases to the point at which the low-pressure ECCS pumps can inject water. There are two redundant divisions for each of the low-pressure ECCS subsystems.

The high-pressure ECCS subsystem is designed to mitigate small break LOCAs during which reactor vessel pressure remains higher than the ability of the low-pressure ECCS pumps to inject water. There is a single high-pressure ECCS subsystem.

The ADS provides redundancy for the single high-pressure ECCS subsystem. In the event of a failure of the high-pressure ECCS subsystem, the ADS valves open to release reactor vessel pressure to the suppression pool, rapidly reducing the pressure to the point at which a low-pressure ECCS subsystem can inject water.

The ECCS instrumentation associated with ADS initiation uses sensor information such as reactor vessel water level, drywell pressure, and low-pressure pump discharge pressure, as well as timers (time delays) to automatically initiate ADS.

1.1 Proposed TS Changes to Adopt TSTF-592 In accordance with the NRC staff-approved TSTF-592, the licensee proposed changes that would revise TS 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation, for Grand Gulf and River Bend. Specifically, the licensee proposed the following changes to adopt TSTF-592:

1.1.1 Proposed Changes to TS 3.3.5.1 TS Table 3.3.5.1-1 is revised to reference Condition H instead of Condition G for Functions 4.e, 4.f, 4.h, 5.e, and 5.g.

TS 3.3.5.1, Required Action G.1, is revised to delete the Note.

TS 3.3.5.1 is revised to add a new Condition H and the following associated remedial actions.

o Condition H states, As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

o Required Action H.1 states, Declare ADS valves inoperable, and is modified by two Notes. The first Note limits the Required Action applicability to Functions 4.e, 4.f, and 5.e. The second Note limits the Required Action applicability to when both ADS trip systems are inoperable due to Low-Pressure Core Spray (LPCS)/Low-Pressure Coolant Injection (LPCI) Pump Discharge Pressure - High channels being

inoperable. The Completion Time is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems.

o Required Action H.2 states, Restore affected channels to OPERABLE status, and it is modified by two Notes. The first Note limits the Required Action applicability to Functions 4.e, 4.f, and 5.e. The second Note limits the Required Action applicability to when one ADS trip system is inoperable due to LPCS/LPCI Pump Discharge Pressure - High channels being inoperable. The Completion Time is 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channels concurrent with HPCS (high-pressure core spray) or RCIC (reactor core isolation cooling) inoperable, and 8 days from discovery of inoperable channels. The option of using a Risk Informed Completion Time is included.

o Required Action H.3 states, Restore channel to OPERABLE status, with a Completion Time of 30 days.

TS 3.3.5.1 current Action H is renamed Action I, and is modified to include the new Condition H.

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

1.2.1 Editorial Variations The licensee noted that the Grand Gulf and River Bend TS Bases have different numbering than the standard technical specifications (STS) Bases from TSTF-592.

2.0 REGULATORY EVALUATION

2.1 Applicable Regulatory Requirements and Guidance The regulation under Title 10 of the Code of Federal Regulations (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.

The categories of items required to be in the TS are listed in 10 CFR 50.36(c). The regulation at 10 CFR 50.36(c)(2) requires that TSs include limiting conditions for operations (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 [TS] until the condition can be met.

The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]

Edition (SRP), Section 16.0, Technical Specifications, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-14341.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-592 The regulatory framework the NRC staff used to determine the acceptability of the licensees proposed changes consisted of the requirements and guidance listed in Section 2.1 of this SE.

The NRC staff compared the licensees proposed TS changes summarized in Section1.1 of this SE against the changes approved in TSTF-592. In accordance with SRP Section 16.0, the NRC staff determined that the STS changes approved in TSTF-592 are applicable to Grand Gulf and River Bend TSs because Grand Gulf and River Bend are BWR/6 plants, and the NRC staff approved the TSTF-592 changes for BWR designs.

TSTF-592 revised the ADS instrumentation remedial action requirements contained in the ECCS instrumentation specification, STS 3.3.5.1, to correct overly restrictive action requirements, and to treat less significant channel inoperabilities consistently. The NRC staff finds that the licensees proposed changes to Grand Gulf and River Bend TS in Section 1.1 of this SE are consistent with those found acceptable in TSTF-592.

In the NRC staffs SE of TSTF-592, the NRC staff concluded that the proposed changes to STS 3.3.5.1 were acceptable because the remedial actions to be taken until the LCO can be met provided protection to the health and safety of the public. The NRC staff also concluded that there was reasonable assurance that proposed changes would continue to ensure that when STS LCO 3.3.5.1 was not met, the licensee shall shut down the reactor or follow any remedial action permitted by the STS until the condition could be met. For example, the proposed remedial actions continued to ensure that appropriate actions were taken for channel inoperabilities associated with pump pressure and manual initiation that resulted in (1) a loss of automatic initiation capability in both ADS trip systems, (2) a loss of automatic initiation capability for one ADS trip system, or (3) no loss of automatic initiation capability in either trip system but required restoration to ensure overall redundancy and diversity of the ADS trip system functions. Therefore, the NRC staff found that the proposed changes to STS 3.3.5.1 were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(2)(i) as discussed in Section 3.0 of the NRC staffs SE of TSTF-592. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Grand Gulf and River Bend TS in Section 1.1 of this SE continue to meet the requirements of 10 CFR 50.36(c)(2)(i).

3.2 Additional Proposed Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.2, the licensee proposed the variations below.

1U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric BWR[Boiling Water eactor]/6 Plants, NUREG-1434, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21271A582 and ML21271A596, respectively). NUREG-1434 provides the STS for BWR/6 plant designs but is also representative in some cases of the BWR/5 plant design.

3.2.1 Editorial Variations The LAR noted that the Grand Gulf and River Bend TS Bases have different numbering than the STS Bases from TSTF-592. The licensee processes changes to the Grand Gulf and River Bend TS Bases in accordance with the associated TS Bases Control Programs in TS 5.5.11. The NRC staff finds that the different TS Bases numbering changes are administrative in nature and do not alter the TS requirements and are therefore acceptable.

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

4.0 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.

NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-29 AND AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION, UNIT 1 RIVER BEND STATION, UNIT 1 DOCKET NOS. 50-416 AND 50-458 Application (i.e., initial and supplements)

Safety Evaluation Date

September 19, 2024, ML24263A271 April 10, 2025

1.0 INTRODUCTION

Entergy Operations, Inc. (the licensee) requested changes to the technical specifications (TSs) for Grand Gulf Nuclear Station, Unit 1 (Grand Gulf), and River Bend Station, Unit 1 (River Bend), by license amendment request (application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-592, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements (TSTF-592) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23256A352), correction letter (ML23283A002), and the associated NRC staff safety evaluation of Traveler TSTF-592 (ML24029A148).

2.0 STATE CONSULTATION

In accordance with the Commissions regulations, State officials for Mississippi and Louisiana were notified of the proposed issuance of the amendments on February 26, 2025. The State officials had no comments.

3.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements 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 November 26, 2024 (89 FR 93364), 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.

ML25059A409 NRR-058 OFFICE NRR/DORL/LPL/PM NRR/DORL/LPL/PM NRR/DORL/LPL4/LA NAME HMcLatchie MMahoney PBlechman (w/comments)

DATE 2/27/2025 2/28/2025 3/13/2025 OFFICE NRR/DSS/STSB/BC OGC - NLO NRR/DORL/LPL4/BC NAME SMehta MChwedczuk TNakanishi DATE 2/21/2025 4/8/2025 04/10/2025 OFFICE NRR/DORL/LPL/PM NAME MMahoney DATE 04/10/2025

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