ML23289A163

Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action

ML23289A163
Person / Time
Site:	Vogtle
Issue date:	11/28/2023
From:	Gleaves W NRC/NRR/VPOB
To:	Coleman J City of Dalton, GA, Georgia Power Co, MEAG Power, Oglethorpe Power Corp, Southern Nuclear Operating Co
Gleaves W
Shared Package
ML23326A154	List: ML23289A163 ML23326A136
References
EPID L-2023-LLA-0072
Download: ML23289A163 (13)

Text

November 28, 2023 Ms. Jamie M. Coleman, Director Fleet Regulatory Affairs Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway, Bin N-274-EC Birmingham, AL 35243

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4-ISSUANCE OF AMENDMENTS REGARDING LICENSE AMENDMENT REQUEST: MORE RESTRICTIVE ACTION FOR TECHNICAL SPECIFICATION 3.1.9 (EPID L-2023-LLA-0072)

Dear Ms. Coleman:

The U.S. Nuclear Regulatory Commission (the Commission or NRC) has issued the enclosed Amendment Nos. 195 and 192 to Combined License (COL) Nos. NPF-91 and NPF-92 for the Vogtle Electric Generating Plant (VEGP), Units 3 and 4, respectively. The amendments consist of changes to COL Appendix A, Technical Specifications (TS),

designated by Southern Nuclear Operating Company as License Amendment Request 23-006R1 in its application dated May 17, 2023. The amendments involve changes to the VEGP, Units 3 and 4, COL Appendix A, to revise TS 3.1.9, Required Action B.1 to impose a more restrictive action and add an allowance (a note) for separate TS Condition entry along with associated clarifying and consistency changes in that TS section.

A copy of the related Safety Evaluation, which includes the evaluation of the changes, is also enclosed. A Notice of Issuance associated with the amendment will be published in the Federal Register.

In accordance with Title 10 of the Code of Federal Regulations, Part 2, Agency Rules of Practice and Procedure, a copy of this letter and enclosures will be available electronically for public inspection in the NRC Public Document Room or from the publicly Enclosure 1

J. Coleman Available records component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html.

Sincerely,

/RA/

William (Billy) Gleaves, Senior Project Manager Vogtle Project Office Office of Nuclear Reactor Regulation Docket Nos.: 52-025,52-026

Enclosures:

1. Amendment No. 195 to VEGP Unit 3 COL NPF-91

2. Amendment No. 192 to VEGP Unit 4 COL NPF-92

3. Safety Evaluation cc: ListServ

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 3 DOCKET NO.52-025 AMENDMENT TO FACILITY COMBINED LICENSE Amendment No. 195 License No. NPF-91

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.,

(SNC), dated May 17, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will be constructed and will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Combined License Condition 2.D.(8) as well as Appendix A of the facility Combined License as indicated in the attachment to this license amendment. Paragraph 2.D(8) of facility Combined License No. NPF-91 is hereby amended to read as follows:

(8) Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 195, are hereby incorporated into this license.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION:

/RA/

Lauren A. Nist, Director Vogtle Project Office Office of Nuclear Reactor Regulation Date of Issuance: November 28, 2023

Attachment:

1. Page 7 of the facility Combined License and affected pages of Appendix A of the facility Combined License

ATTACHMENT TO LICENSE AMENDMENT NO. 195 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-91 REMOVE INSERT 7 7 Facility Combined License No. NPF-91, Appendix A REMOVE INSERT 3.1.9-1 3.1.9-1 3.1.9-2 3.1.9-2

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3), Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 195, are hereby incorporated into this license.

(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 195

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 DOCKET NO.52-026 AMENDMENT TO FACILITY COMBINED LICENSE Amendment No. 192 License No. NPF-92

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

A. The application for amendment by Southern Nuclear Operating Company, Inc., (SNC), dated May 17, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will be constructed and will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable requirements have been satisfied.

Enclosure 2

2. Accordingly, the license is amended by changes to the Combined License Condition 2.D.(8) as well as Appendix A of the facility Combined License as indicated in the attachment to this license amendment. Paragraph 2.D(8) of facility Combined License No. NPF-92 is hereby amended to read as follows:

(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively, of this license, as revised through Amendment No. 192, are hereby incorporated into this license.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION:

/RA/

Lauren A. Nist, Director Vogtle Project Office Office of Nuclear Reactor Regulation Date of Issuance: November 28, 2023

Attachment:

1. Page 7 of the facility Combined License and affected pages of Appendix A of the facility Combined License

ATTACHMENT TO LICENSE AMENDMENT NO. 192 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Facility Combined License No. NPF-92, Appendix A REMOVE INSERT 3.1.9-1 3.1.9-1 3.1.9-2 3.1.9-2

(7) Reporting Requirements (c) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(d) SNC shall report any violation of a requirement in Section 2.D.(3), Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 192, are hereby incorporated into this license.

(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g) with the following exceptions:

(a) Prior to initial criticality of the reactor core while operating plant operational Mode 5 (Cold Shutdown) or Mode 6 (Refueling) the following TS are temporarily excluded from becoming effective:

• TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation, Table 3.3.8-1 o Function 14, RCS Wide Range Pressure - Low o Function 14, Core Makeup Tank (CMT) Level - Low 3 o Function 16, CMT Level - Low 6 o Function 18, IRWST Lower Narrow Range Level - Low 3

• TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)

Manual Initiation, Table 3.3.9-1 o Function 1, Safeguards Actuation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 9, Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation 7 Amendment No. 192

Technical Specifications CVS Demineralized Water Isolation Valves and Makeup Line Isolation Valves 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves and Makeup Line Isolation Valves LCO 3.1.9 Two CVS Demineralized Water Isolation Valves and two CVS Makeup Line Isolation Valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTIONS

- NOTES -

1. Flow path(s) may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One CVS A.1 Restore isolation valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> demineralized water OPERABLE status.

isolation valve inoperable.

OR One CVS makeup line isolation valve inoperable.

VEGP Units 3 and 4 3.1.9 -1 Amendment No. 195 (Unit 3)

Amendment No. 192 (Unit 4)

Technical Specifications CVS Demineralized Water Isolation Valves and Makeup Line Isolation Valves 3.1.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Isolate the affected flow 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion path(s) to the Reactor Time of Condition A not Coolant System by use of at met. least one closed manual or one closed and de-activated OR automatic valve.

Two CVS demineralized water isolation valves inoperable.

OR Two CVS makeup line isolation valves inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify two CVS demineralized water isolation valves In accordance with and two CVS makeup line isolation valves stroke the Inservice closed. Testing Program SR 3.1.9.2 Verify closure time of each CVS makeup isolation In accordance with valve is within limits on an actual or simulated the Inservice actuation signal. Testing Program SR 3.1.9.3 Verify each CVS demineralized water isolation valve 24 months actuates to the isolation position on an actual or simulated actuation signal.

VEGP Units 3 and 4 3.1.9 -2 Amendment No. 195 (Unit 3)

Amendment No. 192 (Unit 4)

Package: ML23326A154 Letter: ML23289A163 Safety: Evaluation: ML23326A136 *via email NRR-106 OFFICE NRR/VPO/PM NRR/DORL/LPL2-2/LA NRR/VPO/PM NRR/DSS/STSB/ABC NAME BGleaves RButler (KGoldstein for) CSantos RElliott DATE 10/23/2023 10/26/2023 10/30/2023 10/13/2023 OFFICE NRR/DEX/EMIB OGC NRR/VPO/BC NAME SBailey MSpencer LNist DATE 10/26/2023 11/21/2023 11/28/2023