Text

Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position
	ML21167A315
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	07/30/2021
From:	John Lamb; Plant Licensing Branch II
To:	Gayheart C; Southern Nuclear Operating Co
	Lamb J
References
	EPID L-2020-LLA-0232
	Download: ML21167A315 (63)
	v • d • e

July 30, 2021 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2; EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2; AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING REVISION TO TECHNICAL SPECIFICATIONS TO ADOPT TSTF-541, REVISION 2, ADD EXCEPTIONS TO SURVEILLANCE REQUIREMENTS FOR VALVES AND DAMPERS LOCKED IN THE ACTUATED POSITION (EPID L-2020-LLA-0232)

Dear Ms. Gayheart:

The U. S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 234 to Renewed Facility Operating License No. NPF-2 and Amendment No. 231 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant (Farley, FNP), Units 1 and 2, respectively; Amendment No. 309 to Renewed Facility Operating License No. DPR-57 and Amendment No. 255 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch, HNP), Units 1 and 2, respectively; and Amendment No. 205 to Renewed Facility Operating License NPF-68 and Amendment No. 188 to Renewed Facility Operating License NPF-81 for the Vogtle Electric Generating Plant (Vogtle, VEGP),

Units 1 and 2, respectively. The amendments consist of changes to the License and Technical Specifications (TSs) in response to your application dated October 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20304A232).

The amendments would revise certain Surveillance Requirements (SRs) in the TSs by adding an exception to the SR for automatic valves or dampers that are locked, sealed, or otherwise secured in the actuated position.

The proposed amendments are based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, dated August 28, 2019 (ADAMS Accession No. ML19240A315). The NRC approved TSTF-541, Revision 2, by letter dated December 10, 2019.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly 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. 50-348, 50-364, 50-321, 50-366, 50-424, and 50-425

Enclosures:

1. Amendment No. 234 to NPF-2

2. Amendment No. 231 to NPF-8 3 Amendment No. 309 to DPR-57

4. Amendment No. 255 to NPF-5

5. Amendment No. 205 to NPF-68

6. Amendment No. 188 to NPF-81

7. FNP Safety Evaluation

8. HNP Safety Evaluation

9. VEGP Safety Evaluation

10. Notices and Environmental Consideration cc: Listserv

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 Renewed License No. NPF-2

1.

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

A.

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

(Southern Nuclear), dated October 30, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-2 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:20:25 -04'00'

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 231 Renewed License No. NPF-8

1.

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

A.

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

(Southern Nuclear), dated October 30, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-8 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 231, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:21:17 -04'00'

ATTACHMENT JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 TO LICENSE AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 TO LICENSE AMENDMENT NO. 231 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the License and Appendix A Technical Specifications (TSs) with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Pages Insert Pages License License License No. NPF-2, page 4 License No. NPF-2, page 4 License No. NPF-8, page 3 License No. NPF-8, page 3 TSs TSs 3.7.10-4 3.7.10-4 3.7.12-2 3.7.12-2

Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 234 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

(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 the 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.

a.

Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.

b.

Deleted per Amendment 13

c.

Deleted per Amendment 2

d.

Deleted per Amendment 2

e.

Deleted per Amendment 152 Deleted per Amendment 2

f.

Deleted per Amendment 158

g.

Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shall include:

1)

Identification of a sampling schedule for the critical parameters and control points for these parameters;

2)

Identification of the procedures used to quantify parameters that are critical to control points;

3)

Identification of process sampling points;

4)

A procedure for the recording and management of data;

5)

Procedures defining corrective actions for off control point chemistry conditions; and

Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 231 (2)

Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license.

(3)

Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and 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)

Southern Nuclear, 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)

Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproducts, 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)

Southern Nuclear, pursuant to 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.

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 incorporate below:

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 231, are hereby incorporated in the renewed license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

(3)

Delete per Amendment 144 (4)

Delete Per Amendment 149 (5)

Delete per Amend 144

CREFS 3.7.10 Farley Units 1 and 2 3.7.10-4 Amendment No. 234 (Unit 1)

Amendment No. 231 (Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.3

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

Not required to be performed in MODES 5 and 6.

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

In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

In accordance with the Control Room Envelope Habitability Program

PRF 3.7.12 Farley Units 1 and 2 3.7.12-2 Amendment No. 234 (Unit 1)

Amendment No. 231 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

Two PRF trains inoperable during movement of recently irradiated fuel assemblies in the SFPR.

E.1 Suspend movement of recently irradiated fuel assemblies in the SFPR.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1

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

Only required to be met during movement of recently irradiated fuel assemblies in the SFPR.

Verify two PRF trains aligned to the SFPR.

In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Operate each PRF train for 15 minutes in the applicable mode of operation (post LOCA and/or refueling accident).

In accordance with the Surveillance Frequency Control Program SR 3.7.12.3 Perform required PRF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.12.4 Verify each PRF train actuates and the normal spent fuel pool room ventilation system isolates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.7.12.5 Verify one PRF train can maintain a pressure

-0.125 inches water gauge with respect to adjacent areas during the post LOCA mode of operation at a flow rate 5500 cfm.

In accordance with the Surveillance Frequency Control Program SR 3.7.12.6 Verify one PRF train can maintain a slightly negative pressure with respect to adjacent areas during the fuel handling accident mode of operation at a flow rate 5500 cfm.

In accordance with the Surveillance Frequency Control Program

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. 309 Renewed License No. DPR-57

1.

The Nuclear Regulatory Commission (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 October 30, 2020, 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; 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. 309, are hereby incorporated in the renewed license. The licensee 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. 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: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:22:06 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 309 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 License No. DPR-57, page 4 License No. DPR-57, page 4 TSs TSs 3.5-5 3.5-5 3.5-9 3.5-9 3.5-11 3.5-11 3.6-42 3.6-42 3.7-5 3.7-5 3.7-10 3.7-10

Renewed License No. DPR-57 Amendment No. 309 for sample analysis or instrumentation calibration, or associated with radioactive apparatus or components; (6)

Southern Nuclear, 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 the 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below:

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not in excess of 2804 megawatts thermal.

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Plan Protection (Appendix B), as revised through Amendment No. 309 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:

SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.

(3)

Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained in the updated Fire Hazards Analysis and Fire Protection Program for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes

ECCS - Operating 3.5.1 HATCH UNIT 1 3.5-5 Amendment No. 309 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 4250 gpm against a system head corresponding to reactor system pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.10

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

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.11

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

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator strokes when manually actuated.

In accordance with the Surveillance Frequency Control Program

RPV Water Inventory Control 3.5.2 HATCH UNIT 1 3.5-9 Amendment No. 309 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.5 Deleted SR 3.5.2.6

NOTES-----------------------------

1. Operation may be through the test return line.

2. Credit may be taken for normal system operation to satisfy this SR.

Operate the required ECCS injection/spray subsystem for 10 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.8

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

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray subsystem can be manually operated.

In accordance with the Surveillance Frequency Control Program

RCIC System 3.5.3 HATCH UNIT 1 3.5-11 Amendment No. 309 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.2

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

Not required to be met for system vent flowpaths opened under administrative control.

Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.3

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 1058 psig and 920 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.4

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.3.5

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

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

SGT System 3.6.4.3 HATCH UNIT 1 3.6-42 Amendment No. 309 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Two or more required SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment.

F.1

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

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in secondary containment.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for 15 continuous minutes.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.6.4.3.3 Verify each required SGT subsystem actuates on an actual or simulated initiation signal, except for dampers that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

PSW System and UHS 3.7.2 HATCH UNIT 1 3.7-5 Amendment No. 309 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of the intake structure is 60.5 ft mean sea level (MSL).

In accordance with the Surveillance Frequency Control Program AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when water level is 61.7 ft MSL SR 3.7.2.2

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

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power operated, and automatic valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.7.2.3 Verify each PSW subsystem actuates on an actual or simulated initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

MCREC System 3.7.4 HATCH UNIT 1 3.7-10 Amendment No. 309 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Two MCREC subsystems inoperable during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

OR One or more MCREC subsystems inoperable due to an inoperable CRE boundary during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

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

LCO 3.0.3 is not applicable.

F.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND F.2 Suspend CORE ALTERATIONS.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.4.3 Verify each MCREC subsystem actuates on an actual or simulated initiation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program (continued)

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. 255 Renewed License No. NPF-5

1.

The Nuclear Regulatory Commission (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 October 30, 2020, 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; 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. 255 are hereby incorporated in the renewed license. The licensee 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. 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: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:23:13 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 255 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 License No. NPF-5, page 4 License No. NPF-5, page 4 TSs TSs 3.5-5 3.5-5 3.5-10 3.5-10 3.5-13 3.5-13 3.6-42 3.6-42 3.7-5 3.7-5 3.7-10 3.7-10

Renewed License No. NPF-5 Amendment No. 255 (6) Southern Nuclear, 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, the 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions2 specified or incorporated below:

(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady sate reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B); as revised through Amendment No. 255 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) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.

(a) Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility with Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

ECCS - Operating 3.5.1 HATCH UNIT 2 3.5-5 Amendment No. 255 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 4250 gpm against a system head corresponding to reactor system pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.10

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

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.11

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

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve relief mode actuator strokes when manually actuated.

In accordance with the Surveillance Frequency Control Program

RPV Water Inventory Control 3.5.2 HATCH UNIT 2 3.5-10 Amendment No. 255 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.5 Deleted SR 3.5.2.6

NOTES-------------------------------

1. Operation may be through the test return line.

2. Credit may be taken for normal system operation to satisfy this SR..

Operate the required ECCS injection/spray subsystem for 10 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.8

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

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray subsystem can be manually operated.

In accordance with the Surveillance Frequency Control Program

RCIC System 3.5.3 HATCH UNIT 2 3.5-13 Amendment No. 255 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5

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

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

SGT System 3.6.4.3 HATCH UNIT 2 3.6-42 Amendment No. 255 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.3 Verify each required SGT subsystem actuates on an actual or simulated initiation signal, except for dampers that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

PSW System and UHS 3.7.2 HATCH UNIT 2 3.7-5 Amendment No. 255 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in each PSW pump well of the intake structure is 60.5 ft mean sea level (MSL).

In accordance with the Surveillance Frequency Control Program AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when water level is 61.7 ft MSL SR 3.7.2.2

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

Isolation of flow to individual components or systems does not render PSW System inoperable.

Verify each PSW subsystem manual, power operated, and automatic valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.7.2.3 Verify each PSW subsystem actuates on an actual or simulated initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program

MCREC System 3.7.4 HATCH UNIT 2 3.7-10 Amendment No. 255 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Two MCREC subsystems inoperable during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

OR One or more MCREC subsystems inoperable due to an inoperable CRE boundary during movement of irradiated fuel assemblies in the secondary containment or during CORE ALTERATIONS.

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

LCO 3.0.3 is not applicable.

F.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND F.2 Suspend CORE ALTERATIONS.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem 15 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.4.3 Verify each MCREC subsystem actuates on an actual or simulated initiation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program (continued)

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-424 VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 205 Renewed License No. NPF-68

1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Renewed Facility Operating License No. NPF-68 filed by the 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 October 30, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is 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-68 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee 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 of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-68 and the Technical Specifications Date of Issuance: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:24:10 -04'00'

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-425 VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 188 Renewed License No. NPF-81

1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Renewed Facility Operating License No. NPF-81 filed by the 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 October 30, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is 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-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee 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 of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-81 and the Technical Specifications Date of Issuance: July 30, 2021 Michael T.

Markley Digitally signed by Michael T. Markley Date: 2021.07.30 09:24:48 -04'00'

ATTACHMENT VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 TO LICENSE AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 TO LICENSE AMENDMENT NO. 188 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Licenses 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 License No. NPF-68, page 4 License No. NPF-68, page 4 License No. NPF-81, page 3 License No. NPF-81, page 3 TSs TSs 3.7.10-5 3.7.10-5 3.7.13-2 3.7.13-2 Renewed Operating License NPF-68 Amendment No. 205 (1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent 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. 205, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.

(4)

Deleted (5)

Deleted (6)

Deleted (7)

Deleted (8)

Deleted (9)

Deleted (10)

Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training and response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for Implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy Renewed Operating License NPF-81 Amendment No. 188 (2)

Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, pursuant to the Act and 10 CFR Part 50, to possess but not operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license; (3)

Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess, and 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)

Southern Nuclear, 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)

Southern Nuclear, 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; (6)

Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as my be produced by the operation of the facility authorized herein.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter 1 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 Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent 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. 188 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be

CREFS - Both Units Operating 3.7.10 Vogtle Units 1 and 2 3.7.10-5 Amendment No. 205 (Unit 1)

Amendment No. 188 (Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify control room air temperature 85°F.

In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Operate each CREFS train for 15 continuous minutes with the heater control circuit energized.

In accordance with the Surveillance Frequency Control Program SR 3.7.10.3 Perform required CREFS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.10.4 Verify each CREFS train actuates (switches to emergency mode) on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

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

In accordance with the Control Room Envelope Habitability Program

PPAFES 3.7.13 Vogtle Units 1 and 2 3.7.13-2 Amendment No. 205 (Unit 1)

Amendment No. 188 (Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each PPAFES train for 15 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.7.13.2 Perform required PPAFES filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.13.3 Verify each PPAFES train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

In accordance with the Surveillance Frequency Control Program SR 3.7.13.4 Verify one PPAFES train can maintain a negative pressure 0.250 inches water gauge relative to atmospheric pressure during the post accident mode of operation at a flow rate of 15,500 cfm +/- 10%.

In accordance with the Surveillance Frequency Control Program

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ADOPTION OF TSTF-541, REVISION 2 FOR JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT NO. 234 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND AMENDMENT NO. 231 TO FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-364

1.0 PROPOSED CHANGE

S Southern Nuclear Operating Company (SNC, the licensee) requested changes to the technical specifications (TSs) for Joseph M. Farley Nuclear Plant; Units 1 and 2 (FNP, Farley), Edwin I.

Hatch Nuclear Plant, Units 1 and 2 (HNP, Hatch) and Vogtle Electric Generating Plant, Units 1 and 2 (VEGP, Vogtle) by a license amendment request (LAR, application). This Safety Evaluation (SE) pertains only to the changes proposed for Farley TSs. The proposed amendment is based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19240A315), and the associated Nuclear Regulatory Commission (NRC) staffs SE of TSTF-541 (ADAMS Accession No. ML19323E926).

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

The proposed amendment is based on TSTF Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ADAMS Accession No. ML19240A315), and the associated NRC staff safety evaluation (SE) of TSTF-541 (ADAMS Accession No. ML19323E926). Section 1.1 of the NRC staffs SE of TSTF-541 discusses the reason for the proposed changes.

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

The Penetration Room Filtration (PRF) System filters airborne radioactive particulates from the area of the fuel pool following a fuel handling accident or emergency core cooling system (ECCS) pump rooms and penetration area of the Auxiliary Building following a loss of coolant accident (LOCA). The PRF System consists of two independent and redundant trains. Each train consists of a heater, a prefilter, a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodines), and a recirculation fan and an exhaust fan. Ductwork, valves or dampers, and instrumentation also form part of the system. The heater is not credited in the analysis but serves to reduce the relative humidity of the air stream. The system initiates filtered ventilation of the spent fuel pool room following receipt of a high radiation signal or a low air flow signal from the normal ventilation system. The system initiates filtered ventilation of the ECCS pump rooms and penetration area following receipt of a containment isolation actuation system (CIAS) Phase B signal and manual isolation of the spent fuel pool room. The PRF System is a standby system normally aligned to filter the spent fuel pool room. During emergency operation the PRF System filters the spent fuel pool room or the ECCS pump rooms and penetration area with fan actuation signals and damper re-alignments to the ECCS pump rooms and penetration area (to support each respective area). Upon receipt of the actuating Engineering Safety Feature Actuation System signal for post LOCA conditions or upon receipt of a high radiation signal or a low air flow signal from the normal spent fuel pool room ventilation system, the PRF fans are started and the ventilation air stream discharges through the system filter trains. The prefilters remove any large particles in the air to prevent excessive loading of the HEPA filters and charcoal adsorbers. The purpose of SR 3.7.12.4 is to verify that each PRF train starts and operates on an actual or simulated Phase B actuation signal. In addition, the normal spent fuel pool ventilation system must be verified to isolate on an actual or simulated spent fuel pool ventilation low differential pressure signal and on an actual or simulated spent fuel pool high radiation signal.

1.2 Description of Proposed Changes The licensee proposed to revise TS SRs 3.7.10.3 and 3.7.12.4 by adding exceptions to the SRs for automatic valves or dampers that are locked, sealed or otherwise secured in the actuated position. The proposed revision, therefore, allows the licensee to meet the limiting conditions for operation (LCOs) without having to test for actuation of those valves or dampers that are already secured in the actuated position. Specifically, the revised TS SRs would add the following text shown in italics:

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

SR 3.7.12.4 Verify each PRF train actuates and the normal spent fuel pool room ventilation system isolates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

The licensee provided the TS Bases for informational use only. The corresponding TS Bases changes adds the following description for each of the applicable SRs:

The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the nonactuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.

1.3 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.2 of this SE, the licensee noted the following in Section 2.2 of the LAR.

1.3.1 Editorial Variations The licensee noted that Farley TSs have different numbering and titles than Standard Technical Specifications (STSs).

1.3.2 Other Variations The licensee proposed the following variations from the TS changes described in TSTF-541 or the applicable parts of the NRC staffs SE of TSTF-541. The licensee stated that these variations do not affect the applicability of TSTF-541 or the associated NRC staffs SE.

The licensee did not propose changes to all SRs in STS modified by TSTF-541. The licensee stated Farley TSs do not contain SRs equivalent to the following SRs in STSs affected by TSTF-541:

SR 3.6.11.3, Iodine Cleanup System (ICS)

SR 3.6.11.4, Iodine Cleanup System (ICS)

SR 3.6.13.3, Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser)

SR 3.6.13.4, Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser)

SR 3.7.12.3, Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (ECCS PREACS)

SR 3.7.12.5, Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (ECCS PREACS)

SR 3.7.13.5, Fuel Building Air Cleanup System (FBACS)

SR 3.7.14.3, Penetration Room Exhaust Air Cleanup System (PREACS)

SR 3.7.14.5, Penetration Room Exhaust Air Cleanup System (PREACS)

The licensee identified a variation from changes approved in TSTF-541 in which the exception inserted into certain SRs would be applied to Farley SR 3.7.12.4. The licensee stated that the PRF system at Farley accomplishes the function of the systems in STS known as the ECCS Pump Room Exhaust Air Cleanup System (ECCS PREACS) and the Penetration Room Exhaust Air Cleanup System (PREACS).

Farley TSs contain a Surveillance Frequency Control Program (SFCP).

2.0 REGULATORY EVALUATION

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

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

Additionally, under 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The considerations for issuance of operating licenses in 10 CFR 50.57(a)(3) provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public. The LAR asks for changes to SRs, which are controlled by 10 CFR 50.36(c)(3) (saying that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met). Accordingly, the amended SRs that no longer require verification of valves and dampers already in, and secured in, their actuated positions, must continue to provide reasonable assurance that the LCOs will be met and the other standards of 10 CFR 50.36(c)(3) will be met.

The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), March 2010 (ADAMS Accession No. ML100351425). The NRC staffs review included consideration of whether the proposed changes are consistent with NUREG-14311, as modified by NRC-approved travelers, and any proposed variations and deviations.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-541, Revision 2 The NRC staff compared the licensees proposed TS SR changes against the changes approved in TSTF-541. In accordance with the SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-541 are applicable to Farley TSs. Farley is a Westinghouse plant design, and the NRC staff approved the TSTF-541 changes for Westinghouse plant designs. The licensees proposed changes to the Farley TS SRs are consistent with TSTF-541 with the above noted variations.

As defined in TS 1.1 OPERABLE - OPERABILITY, (TS 1.1-4) states, in part, that a train shall be OPERABLE or have OPERABILITY:

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

The proposed SRs would exclude the need to verify actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal. The licensees LAR contains the following statements:

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

As stated in the FNP [Farley], HNP [Hatch] and VEGP [Vogtle] SR 3.0.1 Bases, Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs.

SNC acknowledges that under the proposed change, the affected valves and dampers may be excluded from the SR when locked, sealed or otherwise secured in the actuated position. However, if the safety analysis assumes movement from the actuated position following an event, or the system is 1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG 1431, Volume 1, Specifications, and Volume 2, Bases, Revision 4.0, dated April 2012 (ADAMS Accession Nos.

ML12100A222 and ML12100A228, respectively).

rendered inoperable by locking, sealing, or otherwise securing the valve or damper in the actuated position, then the system cannot perform its specified safety function and is inoperable regardless of whether the SR is met.

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

Based on the above, the NRC staff determined that there is reasonable assurance that the licensee will continue to properly control affected equipment in accordance with existing regulations and requirements when using the exceptions added to the respective SRs.

Revised SRs 3.7.10.3 and 3.7.12.4 will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position. NRC staff finds, however, that it is not necessary to verify actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions.

Therefore, the NRC staff determined that the amended Farley TSs will continue to meet 10 CFR 50.36(c)(3) because the revised SRs will continue to provide reasonable assurance that necessary safety function and quality of systems and components is maintained and that the LCOs will be met and is, therefore, acceptable.

3.2 Additional Proposed TS Changes 3.2.1 Editorial The licensee noted that Farley TSs have different numbering and titles than STS. The NRC staff finds that the different TS numbering and title changes are administrative and do not alter TS requirements under the current licensing basis.

3.2.2 Other Variations The staff reviewed the variations from TSTF-541 changes described in Section 1.3.2. The NRC staff determined that since Farley TSs do not contain SRs equivalent to the listed STS SRs in Section 1.3.2, the variation from TSTF-541 changes is acceptable.

The staff reviewed the variation from TSTF-541 in which the licensee stated Farley SR 3.7.12.4 would be modified by the TSTF-541 exception. This SR is for the FNP PRF System, which includes the functions of the STSs for the Penetration Room Exhaust Air Cleanup System (PREACS) and the Fuel Building Air Cleanup System (FBACS). As a result, this SR contains additional requirements than the requirements of STTSs SR 3.7.13.3. The staff determined the variation is acceptable because, per Chapter 16.0 of the SRP, the additional SR requirements are not germane to this change.

The NRC staff reviewed the licensees statement regarding the Farley SFCP and determined that the existence of a SFCP in Farley TSs has no effect on the applicability of the proposed change and is, therefore, 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 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(s) will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

Matthew Hamm, NRR Date issued:

07/30/2021

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ADOPTION OF TSTF-541, REVISION 2 FOR EDWIN I. HATCH NUCLEAR PLANT, UNIT 1 AMENDMENT NO. 309 TO FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 AND AMENDMENT NO. 255 TO FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY EDWIN I. HATCH NUCLEAR PLANT, UNITS 2 DOCKET NO. 50-366

1.0 PROPOSED CHANGE

S Southern Nuclear Operating Company (SNC, the licensee) requested changes to the technical specifications (TSs) for Joseph M. Farley Nuclear Plant; Units 1 and 2 (FNP, Farley), Edwin I.

Hatch Nuclear Plant, Units 1 and 2 (HNP, Hatch) and Vogtle Electric Generating Plant, Units 1 and 2 (VEGP, Vogtle) by license amendment request (LAR, application). This Safety Evaluation (SE) pertains only to the changes proposed for Hatch TSs. The proposed amendment is based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML19240A315), and the associated Nuclear Regulatory Commission (NRC) staffs SE of TSTF-541 (ADAMS Accession No. ML19323E926).

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

The proposed amendment is based on TSTF Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ADAMS Accession No. ML19240A315), and the associated NRC staffs SE of TSTF-541 (ADAMS Accession No. ML19323E926). Section 1.1 of the NRC staffs SE of TSTF-541 discusses the reason for the proposed changes.

1.1 System Descriptions The emergency core cooling system (ECCS) is designed to limit the release of radioactive materials to the environment following a loss-of-coolant accident (LOCA) and consists of the high pressure coolant injection system, the core spray system, the low pressure coolant injection mode of the residual heat removal (RHR) system, and the automatic depressurization system. The purpose of SR 3.5.1.10 is to verify the automatic initiation logic of high pressure coolant injection, core spray, and low pressure coolant injection will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup, and actuation of all automatic valves to their required positions on receipt of an actual or simulated actuation signal.

The Reactor Pressure Vessel (RPV) contains penetrations below the top of the active fuel (TAF) that have the potential to drain the reactor coolant inventory to below the TAF. If the water level should drop below the TAF, the ability to remove decay heat is reduced. Reduced decay heat removal could lead to elevated cladding temperatures and clad perforation. The purpose of SR 3.5.2.7 is to verify that each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated RPV water level isolation signal.

This is required to prevent RPV water inventory from dropping below the TAF, should an unexpected draining event occur.

The function of the Reactor Core Isolation Cooling (RCIC) system is to respond to transient events by providing makeup coolant to the reactor. The purpose of SR 3.5.3.5 is to verify the system operates as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions on receipt of an actual or simulated actuation signal.

The function of the standby gas treatment (SGT) system is to ensure that radioactive materials that leak from the primary containment into the secondary containment following a design basis accident (DBA) are filtered and adsorbed prior to exhausting to the environment. The purpose of SR 3.6.4.3.3 is to verify that each SGT subsystem starts on receipt of an actual or simulated initiation signal.

The Plant Service Water (PSW) System and Ultimate Heat Sink (UHS) are designed to provide cooling water for the removal of heat from equipment, such as the diesel generators, RHR pump coolers and heat exchangers, and room coolers for ECCS equipment, required for a safe reactor shutdown following a DBA or transient. The PSW system also provides cooling to unit components, as required, during normal shutdown and reactor isolation modes. During a DBA, the equipment required only for normal operation is isolated and cooling is directed to only safety-related equipment. The purpose of SR 3.7.2.3 is to verify the systems will automatically switch to the position to provide cooling water exclusively to safety-related equipment during an accident.

The Main Control Room Environmental Control (MCREC) System provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The purpose of SR 3.7.4.3 is to verify that each train/subsystem starts and operates on an actual or simulated actuation signal.

1.2 Description of Proposed Changes In accordance with NRC staff-approved TSTF-541, the licensee proposed to revise TS SRs 3.5.1.10, 3.5.2.7, 3.5.3.5, 3.6.4.3.3, 3.7.2.3, and 3.7.4.3 by adding exceptions to the SRs for automatic valves or dampers that are locked, sealed or otherwise secured in the actuated position. The proposed revisions, therefore, allow the licensee to meet the LCOs without having to test for actuation those valves or dampers that are already secured in the actuated position.

Specifically, the revised TS SRs would add the following text shown in italics:

SR 3.5.1.10 Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.5.3.5 Verify the RCIC System actuates on an actual or simulated automatic initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.6.4.3.3 Verify each required SGT subsystem actuates on an actual or simulated initiation signal, except for dampers that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.2.3 Verify each PSW subsystem actuates on an actual or simulated initiation signal, except for valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.4.3 Verify each MCREC subsystem actuates on an actual or simulated initiation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

The licensee provided the TS Bases for informational use only. The corresponding TS Bases changes adds the following description for each of the applicable SRs:

The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the nonactuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.

1.3 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.2 of this SE, the licensee noted the following in Section 2.2 of the LAR.

1.3.1 Editorial Variations The licensee noted that Hatch TSs have different numbering and titles than Standard Technical Specifications (STSs).

1.3.2 Other Variations The licensee proposed the following variations from the TS changes described in TSTF-541 or the applicable parts of the NRC staffs SE of TSTF-541. The licensee stated that these variations do not affect the applicability of TSTF-541 or the associated NRC staffs SE.

The licensee identified a variation from changes approved in TSTF-541 in which the exception inserted into certain SRs would be applied to Hatch SR 3.5.2.7. SR 3.5.2.7 had not been incorporated into the version of STS on which TSTF-541 was based.

The licensee did not propose changes to all SRs in STS modified by TSTF-541. The licensee stated Hatch TSs do not contain a SR equivalent to STS SR 3.6.4.3.4.

Hatch TSs contain a Surveillance Frequency Control Program (SFCP).

2.0 REGULATORY EVALUATION

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

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

Additionally, under 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The considerations for issuance of operating licenses in 10 CFR 50.57(a)(3) provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.

The LAR asks for changes to SRs, which are controlled by 10 CFR 50.36(c)(3) (saying that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met). Accordingly, the amended SRs that no longer require verification of valves and dampers already in, and secured in, their actuated positions, must continue to provide reasonable assurance that the LCOs will be met and the other standards of 10 CFR 50.36(c)(3) will be met.

The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), March 2010 (ADAMS Accession No. ML100351425). The NRC staffs review included consideration of whether the proposed changes are consistent with NUREG-14332, as modified by NRC-approved travelers, and any proposed variations and deviations.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-541 The NRC staff compared the licensees proposed TS SR changes against the changes approved in TSTF-541. In accordance with the SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-541 are applicable to Hatchs TSs. Hatch is a General Electric BWR/4 plant design and the NRC staff approved the TSTF-541 changes for General Electric BWR/4 plant designs. The licensees proposed changes to the Hatch TS SRs are consistent with TSTF-541 with the above noted variations.

As defined in TS 1.1 OPERABLE - OPERABILITY, (TS 1.1-5) states, in part, that a train shall be OPERABLE or have OPERABILITY:

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

The proposed SRs would exclude the need to verify actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal. The licensees LAR contains the following statements:

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

As stated in the FNP, HNP and VEGP SR 3.0.1 Bases, Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs.

SNC acknowledges that under the proposed change, the affected valves and dampers may be excluded from the SR when locked, sealed or otherwise secured in the actuated position. However, if the safety analysis assumes movement from the actuated position following an event, or the system is 2 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric BWR/4 Plants NUREG 1433, Volume 1, Specifications, and Volume 2, Bases, Revision 4.0, dated April 2012 (ADAMS Accession Nos. ML12104A192 and ML12104A193, respectively).

rendered inoperable by locking, sealing, or otherwise securing the valve or damper in the actuated position, then the system cannot perform its specified safety function and is inoperable regardless of whether the SR is met.

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

Based on the above, the NRC staff determined that there is reasonable assurance that the licensee will continue to properly control affected equipment in accordance with existing regulations and requirements when using the exceptions added to the respective SRs.

Revised SRs 3.5.1.10, 3.5.2.7, 3.5.3.5, 3.6.4.3.3, 3.7.2.3, and 3.7.4.3 will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position. The NRC staff finds, however, that it is not necessary to verify actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions.

Therefore, the NRC staff determined that the amended Hatch TSs will continue to meet 10 CFR 50.36(c)(3) because the revised SRs will continue to provide reasonable assurance that necessary safety function and quality of systems and components is maintained and that the LCOs will be met and is, therefore, acceptable.

3.2 Additional Proposed TS Changes 3.2.1 Editorial The licensee noted that Hatch TSs have different numbering and titles than STS. The NRC staff finds that the different TS numbering and titles changes are administrative and do not alter TS requirements under the current licensing basis.

3.2.2 Other Variations The NRC staff reviewed the variations from TSTF-541 changes described in Section 1.3.2.

The NRC staff reviewed the variation from changes approved in TSTF-541 in which the exception inserted into certain SRs would be applied to Hatch SR 3.5.2.7. The staff determined that SR 3.5.2.7, which was proposed for addition to the TSs via TSTF-542, had not been incorporated into the version of STS on which TSTF-541 was based because the SR was created after TSTF-541 development began. As the licensee has already adopted TSTF-542, which replaced this SR with a more explicit requirement, exclusion of this SR from the proposed changes is appropriate.

The staff determined that since Hatch TSs do not contain SRs equivalent to the listed STS SRs in Section 1.3.2, the variation from TSTF-541 changes is acceptable because, per Chapter 16.0 of the SRP, there is no expectation to adopt STS requirements not represented in existing TS.

The NRC staff reviewed the licensees statement regarding the Hatch SFCP and determined that the existence of a SFCP in Hatch TSs has no effect on the applicability of the proposed change and is, therefore, 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 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(s) will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

Matthew Hamm, NRR Date issued:

07/30/2021

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ADOPTION OF TSTF-541, REVISION 2 FOR VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT NO. 205 TO FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 DOCKET NO. 50-425

1.0 PROPOSED CHANGE

S Southern Nuclear Operating Company (the licensee) requested changes to the technical specifications (TSs) for Joseph M. Farley Nuclear Plant; Units 1 and 2 (FNP, Farley), Edwin I.

Hatch Nuclear Plant, Units 1 and 2 (HNP, Hatch) and Vogtle Electric Generating Plant, Units 1 and 2 (VEGP, Vogtle) by a license amendment request (LAR, application). This Safety Evaluation pertains only to the changes proposed for Vogtle TSs. The proposed amendment is based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML19240A315), and the associated Nuclear Regulatory Commission (NRC) staffs SE of TSTF-541 (ADAMS Accession No. ML19323E926).

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

The proposed amendment is based on TTSTF Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ADAMS Accession No. ML19240A315), and the associated NRC staffs SE of TSTF-541 (ADAMS Accession No. ML19323E926). Section 1.1 of the NRC staffs SE of TSTF-541 discusses the reason for the proposed changes.

1.1 System Descriptions The Control Room Emergency Filtration System (CREFS) provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The purpose of SR 3.7.10.4 is to verify that each train/subsystem starts and operates on an actual or simulated actuation signal.

The Piping Penetration Area Filtration and Exhaust System (PPAFES) consists of two independent and redundant trains. Each train consists of a heater, a prefilter or demister, a HEPA filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodines), and a fan. Ductwork, valves or dampers, and instrumentation, as well as demisters, functioning to reduce the relative humidity of the air stream, also form part of the system. The PPAFES is a standby system, parts of which may also operate during normal unit operations.

Upon receipt of the actuating signal(s), the PPAFES dampers are realigned and fans are started to initiate filtration. The purpose of SR 3.7.13.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal.

1.2 Description of Proposed Changes The licensee proposed to revise TS SRs 3.7.10.4 and 3.7.13.3 by adding exceptions to the SRs for automatic valves or dampers that are locked, sealed or otherwise secured in the actuated position. The proposed revisions, therefore, allow the licensee to meet the LCOs without having to test for actuation those valves or dampers that are already secured in the actuated position.

Specifically, the revised TS SRs would add the following text shown in italics:

SR 3.7.10.4 Verify each CREFS train actuates (switches to emergency mode) on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

SR 3.7.13.3 Verify each PPAFES train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.

The licensee provided the TS Bases for informational use only. The corresponding TS Bases changes adds the following description for each of the applicable SRs:

The SR excludes automatic dampers and valves that are locked, sealed, or otherwise secured in the actuated position. The SR does not apply to dampers or valves that are locked, sealed, or otherwise secured in the actuated position since the affected dampers or valves were verified to be in the actuated position prior to being locked, sealed, or otherwise secured. Placing an automatic valve or damper in a locked, sealed, or otherwise secured position requires an assessment of the operability of the system or any supported systems, including whether it is necessary for the valve or damper to be repositioned to the nonactuated position to support the accident analysis. Restoration of an automatic valve or damper to the non-actuated position requires verification that the SR has been met within its required Frequency.

1.3 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.2 of this SE, the licensee proposed the following variations.

1.3.1 Editorial Variations The licensee noted that Vogtle TSs have different numbering and titles than Standard Technical Specifications (STSs).

1.3.2 Other Variations The licensee did not propose changes to all SRs in STS modified by TSTF-541. The licensee stated Vogtle Unit 1 and Unit 2 TS do not contain SRs equivalent to the following SRs affected by TSTF-541:

SR 3.6.11.3, Iodine Cleanup System (ICS)

SR 3.6.11.4, Iodine Cleanup System (ICS)

SR 3.6.13.3, Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser)

SR 3.6.13.4, Shield Building Air Cleanup System (SBACS) (Dual and Ice Condenser)

SR 3.7.12.3, ECCS Penetration Room Exhaust Air Cleanup System (ECCS PREACS)

SR 3.7.12.5, ECCS Penetration Room Exhaust Air Cleanup System (ECCS PREACS)

SR 3.7.13.3, Fuel Building Air Cleanup System (FBACS)

SR 3.7.13.5, Fuel Building Air Cleanup System (FBACS)

SR 3.7.14.5, Penetration Room Exhaust Air Cleanup System (PREACS)

Vogtle TSs contain a Surveillance Frequency Control Program (SFCP).

2.0 REGULATORY EVALUATION

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

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

Additionally, under 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. The considerations for issuance of operating licenses in 10 CFR 50.57(a)(3) provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public. The LAR asks for changes to SRs, which are controlled by 10 CFR 50.36(c)(3) (saying that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met). Accordingly, the amended SRs that no longer require verification of valves and dampers already in, and secured in, their actuated positions, must continue to provide reasonable assurance that the LCOs will be met and the other standards of 10 CFR 50.36(c)(3) will be met.

The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), March 2010 (ADAMS Accession No. ML100351425). The NRC staffs review included consideration of whether the proposed changes are consistent with NUREG-14311, as modified by NRC-approved travelers, and any proposed variations and deviations.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-541 The NRC staff compared the licensees proposed TS SR changes against the changes approved in TSTF-541. In accordance with the SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-541 are applicable to Vogtles TSs. Vogtle is a Westinghouse plant design and the NRC staff approved the TSTF-541 changes for Westinghouse plant designs. The licensees proposed changes to the Vogtle TS SRs are consistent with TSTF-541 with the above noted variations.

As defined in TS 1.1 OPERABLE - OPERABILITY, (TS 1.1-4) states, in part, that a train shall be OPERABLE or have OPERABILITY:

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

The proposed SRs would exclude the need to verify actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal. The licensees LAR contains the following statements:

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

As stated in the FNP [Farley], HNP [Hatch] and VEGP [Vogtle] SR 3.0.1 Bases, Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when: a. The systems or components are known to be inoperable, although still meeting the SRs.

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

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

Based on the above, the NRC staff determined that there is reasonable assurance that the licensee will continue to properly control affected equipment in accordance with existing regulations and requirements when using the exceptions added to the respective SRs.

Revised SRs 3.7.10.4 and 3.7.13.3 will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position. The NRC staff finds, however, that it is not necessary to verify actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions.

Therefore, the NRC staff determined that the amended Vogtle TSs will continue to meet 10 CFR 50.36(c)(3) because the revised SRs will continue to provide reasonable assurance that necessary safety function and quality of systems and components is maintained and that the LCOs will be met and is, therefore, acceptable.

3.2 Additional Proposed TS Changes 3.2.1 Editorial The licensee noted that Vogtle TSs have different numbering and titles than STS. The NRC staff finds that the different TS numbering and titles changes are administrative and do not alter TS requirements under the current licensing basis.

3.2.2 Other Variations The staff reviewed the variations from TSTF-541 changes described in Section 1.3.2. The NRC staff determined that since Vogtle TSs do not contain SRs equivalent to the listed STS SRs in Section 1.3.2, the variation from TSTF-541 changes is acceptable.

The NRC staff reviewed the licensees statement regarding the Vogtle SFCP and determined that the existence of a SFCP in the Vogtle TSs has no effect on the applicability of the proposed change and is, therefore, 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 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(s) will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

Matthew Hamm, NRR Date issued:

07/30/2021

0 NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO ADOPTION OF TSTF-541, REVISION 2 FOR JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2; EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2; AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 AMENDMENT NO. 234 TO FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 231 TO FACILITY OPERATING LICENSE NO. NPF-8 AMENDMENT NO. 309 TO FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 255 TO FACILITY OPERATING LICENSE NO. NPF-5 AMENDMENT NO. 205 TO FACILITY OPERATING LICENSE NO. NPF-68 AND AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT; UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 EDWIN I. HATCH NUCLEAR PLANT; UNITS 1 AND 2 DOCKET NOS. 50-321 AND 50-366 VOGTLE ELECTRIC GENERATING PLANT; UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425

1.0 INTRODUCTION

Southern Nuclear Operating Company (SNC, the licensee) requested changes to the technical specifications (TSs) for Joseph M. Farley Nuclear Plant; Units 1 and 2 (FNP, Farley), Edwin I.

Hatch Nuclear Plant, Units 1 and 2 (HNP, Hatch) and Vogtle Electric Generating Plant, Units 1 and 2 (VEGP, Vogtle) by a 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 amendment is based on Technical Specifications Task Force (TSTF)

Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (TSTF-541) (ADAMS Accession No. ML19240A315),

and the associated NRC staff safety evaluation (SE) of TSTF-541 (ADAMS Accession No. ML19323E926).

2.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Georgia State and Alabama State officials were notified on April 12, 2021, of the proposed issuance of the amendments. The State officials had no comments.

3.0 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 and change surveillance requirements. 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 and there has been no public comment on such finding (published in the Federal Register on December 29, 2020 (85 FR 85678)). 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.

ML21167A315

via SE Input OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC*

NAME JLamb KGoldstein VCusumano*

DATE 06/10/2021 06/22/2021 05/21/2021 OFFICE OGC - NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME KGamin MMarkley JLamb DATE 07/02/2021 07/30/2021 07/30/2021

v t e Letter Sequence Approval
EPID:L-2020-LLA-0232, TSTF-541, TSTF-542 (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval, Approval Other:
MONTHYEAR2020-11-12 [Table View]

ML21167A315

Text

SUBJECT:

Dear Ms. Gayheart:

Enclosures:

Attachment:

Attachment:

Attachment:

Attachment:

Attachment:

Attachment:

1.0 PROPOSED CHANGE

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

1.0 PROPOSED CHANGE

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

1.0 PROPOSED CHANGE

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

1.0 INTRODUCTION

2.0 STATE CONSULTATION

3.0 ENVIRONMENTAL CONSIDERATION

Navigation menu

Search