Text

Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227)
	ML22293A030
Person / Time
Site:	Hatch
Issue date:	11/07/2022
From:	John Lamb; NRC/NRR/DORL/LPL2-1
To:	Gayheart C; Southern Nuclear Operating Co
	Lamb J, NRR/DORL/LPL2-1
References
	EPID L-2021-LLA- 0227
	Download: ML22293A030 (27)
	v • d • e

November 7, 2022 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS NOS. 318 AND 263, REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT

[TECHNICAL SPECIFICATION TASK FORCE TRAVELER] TSTF-227, REVISION TO EOC-RPT [END OF CYCLE RECIRCULATION PUMP TRIP]

PUMP ACTIONS, AND TSTF-297, ENHANCEMENTS TO REQUIRED ACTIONS FOR FEEDWATER AND MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION EOC-RPT INSTRUMENTATION, AND ATWS-RPT

[ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP] INSTRUMENTATION (EPID L-2021-LLA-0227)

Dear Ms. Gayheart:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 318 to Renewed Facility Operating License No. DPR-57 and Amendment No. 263 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 13, 2021, as supplemented by letter dated February 1, 2022.

The proposed license amendment request (LAR) would revise TSs for Hatch, Units 1 and 2, to adopt (Technical Specification Task Force Traveler) TSTF-227, involving changes to the End of Cycle Reactor Pump Trip (EOC-RPT) Instrumentation TS, and TSTF-297, involving enhancements to Feedwater and Main Turbine High Water Level Trip, EOC-RPT, and Anticipated Transient Without Scram (ATWS)-RPT TS. Specifically, the proposed LAR would add Notes and a new Required Action to allow affected feedwater pump(s) and main turbine valve(s) to be removed from service.

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

Sincerely,

/RA/

John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 318 to DPR-57

2. Amendment No. 263 to NPF-5

3. Safety Evaluation cc w/encls: Listserv

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 318 Renewed License No. DPR-57

1. The Nuclear Regulatory Commission (NRC, the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated December 13, 2021, as supplemented by letter dated February 1, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I; Enclosure 1

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 hereby amended by page 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-57 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 318, are hereby incorporated in the renewed license. Southern Nuclear 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 Michael T. Digitally signed by Michael T. Markley Date: 2022.11.07 12:16:06 -05'00' Markley Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-57 and Technical Specifications Date of Issuance: November 7, 2022

ATTACHMENT TO LICENSE AMENDMENT NO. 318 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4 4 TSs TSs 3.3-21 3.3-21 3.3-28 3.3-28 3.3-29 3.3-29 3.3-30 3.3-30 3.3-32 3.3-32 3.3-33 3.3-33

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine Trip High Water Level Instrumentation LCO 3.3.2.2 Three channels of feedwater and main turbine trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER 24% RTP ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.1 Place channel in trip. 7 days turbine high water level trip channel inoperable.

B. Two or more feedwater and B.1 Restore feedwater and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months main turbine high water main turbine high water level trip channels level trip capability.

inoperable.

C. Required Action and C.1 ----------NOTE----------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable feedwater pump valve or main turbine stop valve.

Remove affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months feedwater pump(s) and main turbine valves(s) from service.

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 24% RTP.

HATCH UNIT 1 3.3-21 Amendment No. 318

EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV) - Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure - Low.

OR

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for inoperable EOC-RPT as specified in the COLR are made applicable.

APPLICABILITY: THERMAL POWER 27.6% RTP.

ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channels inoperable. OPERABLE status.

OR A.2 -----------NOTE------------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

HATCH UNIT 1 3.3-28 Amendment No. 318

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months EOC-RPT trip capability not capability.

maintained.

OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months MCPR limit for inoperable for inoperable EOC-RPT not made EOC-RPT as specified applicable. in the COLR.

C. Required Action and C.1 ---------NOTE-------------

associated Completion Time Only applicable if not met. inoperable channel is the result of an inoperable RPT breaker.

Remove the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months recirculation pump from service.

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 27.6%

RTP.

SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (Continued)

HATCH UNIT 1 3.3-29 Amendment No. 318

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.2 Verify TSV - Closure and TCV Fast Closure, Trip In accordance with Oil Pressure - Low Functions are not bypassed the Surveillance when THERMAL POWER is 27.6% RTP. Frequency Control Program SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control TSV - Closure: 10% closed; and Program TCV Fast Closure, Trip Oil Pressure - Low: 600 psig.

SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.5 ---------------------------NOTE------------------------------

Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME In accordance with is within limits. the Surveillance Frequency Control Program SR 3.3.4.1.6 Determine RPT breaker interruption time. In accordance with the Surveillance Frequency Control Program HATCH UNIT 1 3.3-30 Amendment No. 318

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability capability for one not maintained. Function.

D. Required Action and D.1 ----------NOTE----------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable RPT breaker.

Remove the affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months recirculation pump from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 1 3.3-32 Amendment No. 318

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control

a. Reactor Vessel Water Level - Program ATWS-RPT Level: -73 inches; and

b. Reactor Steam Dome Pressure -

High: 1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including breaker actuation. the Surveillance Frequency Control Program HATCH UNIT 1 3.3-33 Amendment No. 318

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 Renewed License No. NPF-5

1. The Nuclear Regulatory Commission (NRC, the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated December 13, 2021, as supplemented by letter dated February 1, 2022, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I; Enclosure 2

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 hereby amended by page 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-5 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 263 are hereby incorporated in the renewed license. Southern Nuclear 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 Michael T. Digitally signed by Michael T. Markley Date: 2022.11.07 12:18:22 -05'00' Markley Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-5 and Technical Specifications Date of Issuance: November 7, 2022

ATTACHMENT TO LICENSE AMENDMENT NO. 263 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4 4 TSs TSs 3.3-21 3.3-21 3.3-28 3.3-28 3.3-29 3.3-29 3.3-30 3.3-30 3.3-32 3.3-32 3.3-33 3.3-33

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine Trip High Water Level Instrumentation LCO 3.3.2.2 Three channels of feedwater and main turbine trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER 24% RTP.

ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.1 Place channel in trip. 7 days turbine high water level trip channel inoperable.

B. Two or more feedwater and B.1 Restore feedwater and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months main turbine high water main turbine high water level trip channels level trip capability.

inoperable.

C. Required Action and C.1 ------------NOTE--------------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable feedwater pump valve or main turbine stop valve.

Remove affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months feedwater pump(s) and main turbine valve(s) from service.

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 24% RTP.

HATCH UNIT 2 3.3-21 Amendment No. 263

EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV) - Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure - Low.

OR

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for inoperable EOC-RPT as specified in the COLR are made applicable.

APPLICABILITY: THERMAL POWER 27.6% RTP.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channels inoperable. OPERABLE status.

OR A.2 ------------NOTE-----------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

HATCH UNIT 2 3.3-28 Amendment No. 263

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months EOC-RPT trip capability not capability.

maintained.

OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months MCPR limit for inoperable for inoperable EOC-RPT not made EOC-RPT as specified applicable. in the COLR.

C. Required Action and C.1 ---------NOTE-------------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable RPT breaker.

Remove the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months recirculation pump from service.

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 27.6%

RTP.

SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 2 3.3-29 Amendment No. 263

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.2 Verify TSV - Closure and TCV Fast Closure, Trip In accordance with Oil Pressure - Low Functions are not bypassed the Surveillance when THERMAL POWER is 27.6% RTP. Frequency Control Program SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control TSV - Closure: 10% closed; and Program TCV Fast Closure, Trip Oil Pressure - Low: 600 psig.

SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.5 ---------------------------NOTE-------------------------------

Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME In accordance with is within limits. the Surveillance Frequency Control Program SR 3.3.4.1.6 Determine RPT breaker interruption time. In accordance with the Surveillance Frequency Control Program HATCH UNIT 2 3.3-30 Amendment No. 263

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability capability for one not maintained. Function.

D. Required Action and D.1 ----------NOTE------------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable RPT breaker.

Remove the affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months recirculation pump from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 2 3.3-32 Amendment No. 263

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The In accordance with Allowable Values shall be: the Surveillance Frequency Control

a. Reactor Vessel Water Level - Program ATWS-RPT Level: -73 inches; and

b. Reactor Steam Dome Pressure -

High: 1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including breaker actuation. the Surveillance Frequency Control Program HATCH UNIT 2 3.3-33 Amendment No. 263

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 318 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366

1.0 INTRODUCTION

Southern Nuclear Operating Company (SNC, the licensee) requested changes to the technical specifications (TSs) for Edwin I. Hatch Nuclear Plant (Hatch), Units 1 and 2, by license amendment request (LAR), dated December 13, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21347A385), as supplemented by letter dated February 1, 2022 (ML22033A073).

The LAR proposed TS changes are consistent with the following Technical Specifications Task Force (TSTF) Travelers:

TSTF-227, Revision 0, Revision to EOC-RPT [End of Cycle-Recirculation Pump Trip]

pump actions, approved by the U.S. Nuclear Regulatory Commission (NRC) on August 16, 1999 (ML040570183), and TSTF-297, Revision 1, Enhancements to Required Actions for Feedwater and Main Turbine High Water Level Trip Instrumentation, EOC-RPT Instrumentation, and ATWS-RPT [Anticipated Transient Without Scram Recirculation Pump Trip]

Instrumentation, approved by NRC on February 16, 2000 (ML003683642).

The supplement dated February 1, 2022, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published the Federal Register on January 25, 2022 (87 FR 3848).

Enclosure 3

2.0 REGULATORY EVALUATION

2.1 Description of the Proposed TS Changes The proposed changes would revise Hatch TS 3.3.2.2, Feedwater and Main Turbine Trip High Water Level Instrumentation, TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation, and 3.3.4.2, Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT).

Proposed Change related to TSTF-227 In TS 3.3.4.1, the description for condition A would change from one or more channels inoperable to one or more required channels inoperable.

Proposed Changes related to TSTF-297 As shown in the following tables, the proposed changes would affect terminal action statements, which apply when their preceding Conditions required actions or completion times are not met.

Current TS 3.3.3.2 states:

REQUIRED ACTION COMPLETION TIME C.1 Reduce THERMAL POWER to < 24% RTP [rated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thermal power].

Revised TS 3.3.3.2 would state:

REQUIRED ACTION COMPLETION TIME C.1 -------------------NOTE---------------------

Only applicable if inoperable channel is the result of an inoperable feedwater pump valve or main turbine stop valve.

Remove affected feedwater pump(s) and main turbine 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valve(s) from service.

OR C.2 Reduce THERMAL POWER to < 24% RTP. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Current TS 3.3.4.1 states:

CONDITION A. One or more channels inoperable

REQUIRED ACTION COMPLETION TIME C.1 Remove the associated recirculation pump from service. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Revised TS 3.3.4.1 would state:

CONDITION A. One or more required channels inoperable.

REQUIRED ACTION COMPLETION TIME C.1 -------------------NOTE---------------------

Only applicable if inoperable channel is the result of an inoperable RPT breaker.

Remove the affected recirculation pump from service. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Current TS 3.3.4.2 states:

REQUIRED ACTION COMPLETION TIME D.1 Remove the associated recirculation pump from service. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Revised TS 3.3.4.2 would state:

REQUIRED ACTION COMPLETION TIME D.1 -------------------NOTE---------------------

Only applicable if inoperable channel is the result of an inoperable RPT breaker.

Remove the affected recirculation pump from service. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 2.2 Proposed Changes to TS Bases Consistent with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(a)(1), the licensee submitted corresponding changes to the TS Bases that provide the reasons for the proposed TSs changes. The regulation at 10 CFR 50.36(a)(1) states that a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TSs. The licensee shall make changes to the Hatch TS Bases in accordance with TS 5.5.11, TS Bases Control Program. The Bases are a licensee-controlled document. The NRC reviewed the proposed TS Bases as they support the requested TS changes but does not approve the Bases.

2.3 Regulatory Requirements and Guidance Used in the Evaluation of the Changes 2.3.1 Regulatory Requirements The regulation at 10 CFR 50.36, Technical specifications, provides the regulatory requirements for the content of the TSs and requires, in part, that a summary statement of the bases for such specifications shall be included by applicants for a license authorizing operation of a production or utilization facility. Specifically, 10 CFR 50.36(c)(2)(i), Limiting conditions for operation, states, in part, that TSs will include (LCOs) [limiting condition for operation], which are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

Section 50.36(c)(2)(i) further states 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.

2.3.2 Guidance Although the proposed TSTF Travelers were developed based on changes to Revision 1 of NUREG-1433, the NRC staffs review of this LAR includes consideration of whether the proposed changes are consistent with the latest revision. NUREG-1433, Revision 5, Standard Technical Specifications for General Electric BWR [Boiling-Water Reactor]/4 Plants (ML21272A357), provides example TS LCOs and acceptable remedial actions that meet the requirements in 10 CFR 50.36(c)(2)(i) for a standard plant design.

3.0 TECHNICAL EVALUATION

3.1 Evaluation of Changes related to TSTF-227, Revision 0 The NRC-approved TSTF-227 revises Standard TS (STS) 3.3.4.1, EOC-RPT Instrumentation, by clarifying that Condition A only applies to inoperable EOC-RPT channels that LCO 3.3.4.1 requires to be operable. Hatch LCO 3.3.4.1 currently requires that either: (a) two channels per trip system for each EOC-RPT instrumentation function (Turbine Stop Valve (TSV) - closure, and turbine control valve fast closure, trip oil pressure - low) shall be operable, or (b) LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR), limits for inoperable EOC-RPT as specified in the COLR [core operating limits report] are made applicable.

In its LAR, the licensee proposed to modify TS 3.3.4.1 Condition A (currently, one or more channels inoperable) to apply only when meeting the LCO based on operable EOC-RPT instrumentation rather than on the specified core operating limits. The MCPR limits for an inoperable EOC-RPT are sufficient to mitigate pressurization transient effects; thus, under that condition, the channels would not be required to be operable. To clarify this intent, SNC proposed to revise condition A to state, One or more required channels inoperable.

The NRC staff reviewed the LAR and determined the proposed change to TS 3.3.4.1 Condition A is acceptable because it is administrative, non-technical, and it clarifies the intended applicability of Condition A with consideration for whether LCO 3.3.4.1 (a) or (b) is met.

3.2 Evaluation of Changes related to TSTF-297, Revision 1 The NRC-approved TSTF-297, Revision 1, revises STS 3.3.2.2, Feedwater and Main Turbine High Water Level Trip Instrumentation, by adding a Required Action and a Note to Condition C, Required Action and associated Completion Time not met. Similarly, in Hatch TS 3.3.3.2, if an inoperable channel is not placed in trip within 7 days (Condition A), or if trip capability is lost but not restored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (Condition B), Condition C applies. The licensee proposed a new Required Action C.1 as an alternative action (remove the affected feedwater pump(s) and main turbine valve(s) from service within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). New Required Action C.1 is modified by a Note that states it is only applicable if the channel inoperability is caused by an inoperable feedwater pump valve or main turbine stop valve. For Condition C, the other option is Required Action C.2 (renumbered existing C.1), which requires power reduction to less than 24 percent of the rated thermal power (RTP) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Similar to the Note for new Required Action C.1 in Hatch TS 3.3.2.2, SNC proposed Notes for TS 3.3.4.1 and TS 3.3.4.2. The Notes, which would modify TS 3.3.4.1 Required Action C.1 and TS 3.3.4.2 Required Action D.1, state each associated Required Action applies only if the inoperable channel (EOC-RPT or ATWS-RPT Instrumentation) is the result of an inoperable RPT breaker.

Additionally, the licensee proposed to modify the two Required Actions to indicate that the affected recirculation pump instead of associated recirculation pump be removed from service.

The NRC staff reviewed the LAR and determined that the proposed changes associated with TSTF-297, Revision 1, satisfy the safety function while providing the requested operational flexibility of the change. New TS 3.3.2.2 Required Action C.1 and its associated Note would allow the licensee to fulfill the safety function of the instrumentation by removing the components from service without requiring a reduction in power to less than 24 percent RTP or further compensatory actions. The NRC staff finds these proposed changes acceptable because they provide the licensee with an appropriate alternative remedial action, consistent with 50.36I(2)(i).

Regarding the proposed Notes in TS 3.3.2.2, TS 3.3.4.1, and 3.3.4.2, the NRC staff determined that they clarify the situations in which the associated required actions would be appropriate, i.e., specified equipment is inoperable. The NRC staff finds these administrative, non-technical changes acceptable because the Notes add clarity to the TS requirements.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the State of Georgia official was notified of the proposed issuance of the amendment on August 8, 2022. The State official confirmed the State of Georgia had no comments on August 9, 2022.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components 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 on January 25, 2022 (87 FR 3848), 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: K. West NRR/DSS/STSB Date: November 7, 2022

ML22293A030 *via email OFFICE NRR/DORL/LPL2-1/PM* NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME JLamb KGoldstein VCusumano DATE 10/17/2022 11/1/2022 10/17/2022 OFFICE NRR/DSS/SCPB/BC NRR/DEX/EICB/BC OGC - NLO NAME BWittick MWaters BAyersman DATE 10/20/2022 10/19/2022 11/1/2022 OFFICE NRR/DORL/LPL2-1/BC* NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 11/7/2022 11/7/2022

ML22293A030

Contents

Text

SUBJECT:

Dear Ms. Gayheart:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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ML22293A030

Text

SUBJECT:

Dear Ms. Gayheart:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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