Text

Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
	ML22069A004
Person / Time
Site:	Vogtle, Farley
Issue date:	04/27/2022
From:	John Lamb; Office of Nuclear Reactor Regulation
To:	Gayheart C; Southern Nuclear Operating Co
	Lamb J
Shared Package
ML22102A002	List: ML22069A004;
References
	EPID L-2021-LLA-0234, TSTF-269-A, Rev 2
	Download: ML22069A004 (36)
	v • d • e

April 27, 2022 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; AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REVISION TO TECHNICAL SPECIFICATIONS TO ADOPT TSTF-269-A, REVISION 2, ALLOW ADMINISTRATIVE MEANS OF POSITION VERIFICATION FOR LOCKED OR SEALED VALVES (EPID L-2021-LLA-0234)

Dear Ms. Gayheart:

The U. S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 242 to Renewed Facility Operating License No. NPF-2 and Amendment No. 239 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, respectively; and Amendment No. 214 to Renewed Facility Operating License NPF-68 and Amendment No. 197 to Renewed Facility Operating License NPF-81 for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, respectively. The amendments consist of changes to the License and Technical Specifications (TSs) in response to your application dated December 22, 2021.

The amendments would revise TSs to adopt Technical Specification Task Force (TSTF)-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves, as described in the enclosed safety evaluation.

A Notice of Issuance will be included in the Commission's monthly Federal Register notice.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

C.

If you have questions, you can contact me at 301-415-3100 or John.Lamb@nrc.gov.

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, 50-424, and 50-425

Enclosures:

1. Amendment No. 242 to NPF-2

2. Amendment No. 239 to NPF-8 3 Amendment No. 214 to NPF-68

4. Amendment No. 197 to NPF-81

5. Safety Evaluation for Farley

6. Safety Evaluation for Vogtle 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. 242 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 December 22, 2021, 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. 242, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ed Miller, Acting 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: April 27, 2022 Glenn E.

Miller Digitally signed by Glenn E. Miller Date: 2022.04.27 10:20:19 -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. 239 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 December 22, 2021, 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. 239, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ed Miller, Acting 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: April 27, 2022 Glenn E.

Miller Digitally signed by Glenn E. Miller Date: 2022.04.27 10:21:04 -04'00'

ATTACHMENT JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 TO LICENSE AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 TO LICENSE AMENDMENT NO. 239 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 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 3.6.3-2 3.6.3-2 3.6.3-4 3.6.3-4 3.6.3-5 3.6.3-5 3.6.3-6 3.6.3-6 3.6.3-7 3.6.3-7 3.6.3-8

Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 242 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242, 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. 239 (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 2821 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 239, 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

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-2 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Only applicable to penetration flow paths with two containment isolation valves.

One or more penetration flow paths with one containment isolation valve inoperable except for purge valve penetration leakage not within limit.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

AND A.2

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

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR In accordance with the Risk Informed Completion Time Program Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-4 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

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

Only applicable to penetration flow paths with only one containment isolation valve and a closed system.

One or more penetration flow paths with one containment isolation valve inoperable.

C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND C.2

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

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR In accordance with the Risk Informed Completion Time Program Once per 31 days

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-5 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more penetration flow paths containing containment purge valves, with penetration leakage such that the sum of the leakage for all Type B and C tests is not within limits.

D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND D.2

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

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued)

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-6 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

(continued)

D.3 Perform SR 3.6.3.5 for the penetrations containing resilient seal purge valves closed to comply with Required Action D.1.

Once per 92 days E.

Required Action and associated Completion Time of Condition A, B, C, or D not met.

E.1 Be in MODE 3.

AND E.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours F.

One or more penetration flow paths containing containment purge valves, with penetration leakage not within the penetration limits.

F.1 Reduce leakage to within limit.

Prior to entering MODE 4 from MODE 5 if the existing leakage is determined during quarterly testing per SR 3.6.3.5 OR Prior to entering MODE 4 if excess leakage is determined during MODE 5 per SR 3.6.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 48 inch purge valve is sealed closed, except for one purge valve in a penetration flow path while in Condition D of this LCO.

In accordance with the Surveillance Frequency Control Program

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-7 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2

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

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

In accordance with the Surveillance Frequency Control Program SR 3.6.3.3

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

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2.

The blind flange on the fuel transfer canal flange is only required to be verified closed after each draining of the canal.

Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR 3.6.3.4 Verify the isolation time of each automatic power operated containment isolation valve in the INSERVICE TESTING PROGRAM is within limits.

In accordance with the INSERVICE TESTING PROGRAM

Containment Isolation Valves 3.6.3 Farley Units 1 and 2 3.6.3-8 Amendment No. 242 (Unit 1)

Amendment No. 239 (Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.5 Perform leakage rate testing for containment penetrations containing containment purge valves with resilient seals.

In accordance with the Surveillance Frequency Control Program AND Within 92 days after opening the valve SR 3.6.3.6 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

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. 50-424 VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 214 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 December 22, 2021, 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. 214, 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.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ed Miller, Acting 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: April 27, 2022 Glenn E.

Miller Digitally signed by Glenn E. Miller Date: 2022.04.27 10:22:25 -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. 197 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 December 22, 2021, 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. 197, 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.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ed Miller, Acting 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: April 27, 2022 Glenn E.

Miller Digitally signed by Glenn E. Miller Date: 2022.04.27 10:23:13 -04'00'

ATTACHMENT VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 TO LICENSE AMENDMENT NO. 214 RENEWED FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 197 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 3.6.3-2 3.6.3-2 3.6.3-3 3.6.3-3 3.6.3-4 3.6.3-4 3.6.3-5 3.6.3-5 3.6.3-6 Renewed Operating License NPF-68 Amendment No. 214 (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. 214, 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. 197 (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. 197 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

Containment Isolation Valves 3.6.3 Vogtle Units 1 and 2 3.6.3-2 Amendment No. 214 (Unit 1)

Amendment No. 197 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

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

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued)

Containment Isolation Valves 3.6.3 Vogtle Units 1 and 2 3.6.3-3 Amendment No. 214 (Unit 1)

Amendment No. 197 (Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ----------NOTES-----------

1. Not applicable when the second containment isolation valve is intentionally made inoperable.

2. The following Section 5.5.22 constraints are applicable: parts b, c.2, c.3, d, e, f, g, and

h.

One or more penetration flow paths with two containment isolation valves inoperable except for purge valve leakage not within limit.

B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR In accordance with the Risk Informed Completion Time Program (continued)

Containment Isolation Valves 3.6.3 Vogtle Units 1 and 2 3.6.3-4 Amendment No. 214 (Unit 1)

Amendment No. 197 (Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ----------NOTES-----------

1. Not applicable when the second containment purge valve is intentionally made inoperable.

2. The following Section 5.5.22 constraints are applicable: parts b, c.2, c.3, d, e, f, g, and

h.

One or more penetration flow paths with one or more containment purge valves not within purge valve leakage limits.

C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND C.2

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

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR In accordance with the Risk Informed Completion Time Program Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued)

Containment Isolation Valves 3.6.3 Vogtle Units 1 and 2 3.6.3-5 Amendment No. 214 (Unit 1)

Amendment No. 197 (Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time not met.

D.1 Be in MODE 3.

AND D.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 24 inch purge valve is sealed closed, except for one purge valve in a penetration flow path while in Condition D of this LCO.

In accordance with the Surveillance Frequency Control Program SR 3.6.3.2 Verify each 14 inch purge valve is closed, except when the associated penetration(s) is (are) permitted to be open for purge or venting operations and purge system surveillance and maintenance testing under administrative control.

In accordance with the Surveillance Frequency Control Program SR 3.6.3.3

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

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

In accordance with the Surveillance Frequency Control Program (continued)

Containment Isolation Valves 3.6.3 Vogtle Units 1 and 2 3.6.3-6 Amendment No. 214 (Unit 1)

Amendment No. 197 (Unit 2)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.4

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

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2.

The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODE 5.

Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR 3.6.3.5 Verify the isolation time of each automatic power operated containment isolation valve is within limits.

In accordance with the INSERVICE TESTING PROGRAM SR 3.6.3.6 Perform leakage rate testing for containment purge valves with resilient seals.

In accordance with the Surveillance Frequency Control Program SR 3.6.3.7 Verify each automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NPF-2 AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

DOCKET NOS. 50-348, AND 50-364

1.0 INTRODUCTION

By application dated December 22, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21356B499), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2.

The LAR would revise Technical Specification (TS) 3.6.3, Containment Isolation Valves, Required Actions A.2, C.2 and D.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means.

The SNC stated that this change is consistent with Technical Specification Task Force (TSTF) Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves (ADAMS Accession No. ML040620100).

The U.S. Nuclear Regulatory Commission (NRC or the Commission) approved TSTF-269-A, Revision 2, in a letter dated July 26, 1999 (ADAMS Accession No. ML19067A141).

2.0 REGULATORY EVALUATION

2.1 Description of the Proposed TS Changes The proposed change to TS 3.6.3 is to add the following note under Required Actions A.2, C.2 and D.2:

2.

Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

In addition, the previous note for these three required actions will be revised to notes, and the existing note, Isolation devices in high radiation areas may be verified by use of administrative means, is re-numbered as Note 1.

The licensee also stated the following variance to TSTF-269-A:

TSTF-269-A identifies a change to TS 3.6.3 Required Action E.2. The equivalent action in the FNP [Farley Nuclear Plant] TS is Required Action D.2These Required Actions are equivalent, and the identifier differences do not affect the applicability of TSTF-269-A to FNP.

2.2 Regulatory Requirements and Guidance The regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, which requires that the TSs include items in five specific categories. These categories include:

(1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions of operation (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls. More specifically, the regulation in 10 CFR 50.36(c)(2)(i) states that, When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. Section 50.36 of 10 CFR does not specify which remedial actions are required or how quickly they must be completed.

The NRC staff used Revision 5.0 of NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1 (ADAMS Accession No. ML21259A155), Specifications, and NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 2, Bases (ADAMS Accession No. ML21259A159) in its review of the TS changes proposed for Farley, Units 1 and 2.

The regulatory requirements in 10 CFR 50.55a, Codes and standards, specify that licensees must implement the inservice testing (IST) provisions in the applicable edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) as incorporated by reference in 10 CFR 50.55a.

2.3 Administrative TS Changes The addition of the notes in TS 3.6.3 impacts the subsequent TS pages and results in an additional TS page.

3.0 TECHNICAL EVALUATION

The TSTF-269-A, Revision 2, revised Standard Technical Specification (STS) 3.6.3, Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual), by adding a note under Required Actions A.2, C.2, and E.2 that isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

The NRC staff has reviewed the proposed changes to the Farley, Units 1 and 2, TS 3.6.3 against this approved TSTF traveler and has determined that administrative controls for such isolation devices (i.e., isolation valves and dampers) have proven to be adequate to ensure the devices are maintained in the positions required by the plant safety analyses when primary and secondary containment is required to be operable.

Periodic verification is required for a penetration with an inoperable isolation device to detect and correct inadvertent repositioning of the isolation device. Because the purpose of locking, sealing, or securing components is to prevent inadvertent repositioning, the licensee proposed that periodic re-verification should be a verification of the administrative controls that ensures that the component remains in the required state.

TS LCO 3.6.3 states, Each containment isolation valve shall be OPERABLE. The OPERABILITY requirements for isolation devices ensure that components are capable of performing their safety functions within the time limits assumed in the safety analyses.

It is reasonable to assume that the initial establishment of component status (e.g., isolation valves closed) was performed correctly. Subsequent, verifications of the component status are intended to ensure the component has not been inadvertently repositioned. Given that the function of locking, sealing, or securing components is to ensure the same avoidance of inadvertent repositioning, the staff finds that periodic reverification using administrative means that ensure that the component remains in the required state is acceptable. Verification of the component status using administrative means avoids removing the lock, seal, or other means of securing the component solely to perform an active verification of the required state.

Verification of the inoperable containment penetrations using administrative means ensures the components will continue to be isolated, and thus, perform their isolation function. In addition, the proposed change does not involve a physical alteration to the plant (i.e., no new or different type of equipment will be installed) or a change to the methods governing normal plant operation.

Additionally, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2) will continue to be met because the minimum performance level of equipment needed for safe operation of the facility is contained in the LCO, and the appropriate remedial actions are specified if the LCO is not met.

The licensees proposed changes related to valve position verification in Farley, Units 1 and 2, TS 3.6.3, are distinct from the IST Program requirements for valve position verification at Farley, Units 1 and 2, specified in the ASME OM Code as incorporated by reference in 10 CFR 50.55a. Any proposed changes to the IST Program requirements for Farley, Units 1 and 2, must be submitted in accordance with 10 CFR 50.55a or as an exemption request.

Based on the above, the NRC staff concludes that the change is consistent with TSTF-269-A (since administrative means for isolation devices have proven to be adequate to ensure the devices are maintained in the positions required by the plant safety analyses).

In addition, the NRC staff determined the licensees proposed variance does not affect the applicability of TSTF-269-A to the proposed license amendments, because the equivalent of Required Action E.2 of TSTF-269-A is Required Action D.2 in the Farley, Units 1 and 2, TSs.

The change in identifier has no effect on the applicability of TSTF-269-A to Farley, Units 1 and 2. With the addition of the notes in TS 3.6.3, the subsequent TS pages are impacted resulting in an additional TS page 3.6.3-8; there are no technical changes with this administrative change. For reasons described above, the NRC staff finds the proposed changes to TS 3.6.3 acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Alabama State official was notified on March 11, 2022, of the proposed issuance of the amendments. On March 11, 2022, the State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 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 (87 FR 9652 dated February 22, 2022), and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Rob Elliott Date: April 27, 2022

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 AMENDMENT NO. 214 TO RENEWED FACILITY OPERATING LICENSE NPF-68 AMENDMENT NO. 197 TO RENEWED FACILITY OPERATING LICENSE NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

DOCKET NOS. 50-424 AND 50-425

1.0 INTRODUCTION

By application dated December 22, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21356B499), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2.

The LAR would revise Technical Specification (TS) 3.6.3, Containment Isolation Valves, Required Actions A.2, and C.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means.

The SNC stated that this change is consistent with Technical Specification Task Force (TSTF) Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves (ADAMS Accession No. ML040620100).

The U.S. Nuclear Regulatory Commission (NRC or the Commission) approved TSTF-269-A, Revision 2, in a letter dated July 26, 1999 (ADAMS Accession No. ML19067A141).

2.0 REGULATORY EVALUATION

2.1 Description of the Proposed TS Changes The proposed change to TS 3.6.3 is to add the following note under Required Actions A.2 and C.2:

2.

Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

In addition, the previous note for these two required actions will be revised to notes, and the existing note, Isolation devices in high radiation areas may be verified by use of administrative means, is re-numbered as Note 1.

The licensee also stated the following variance to TSTF-269-A:

There are two differences in the Required Action identifiers between TSTF-269-A andthe VEGP [Vogtle Electric Generating Plant] TS. TSTF-269-A identifies a change to TS 3.6.3 Required Action E.2The equivalent Required Action in the VEGP TS is C.2. These Required Actions are equivalent, and the identifier differences do not affect the applicability of TSTF-269-A toVEGP. In addition, the VEGP TS do not contain a Condition equivalent to Condition C in TSTF-269-A. Therefore, that change is not applicable to VEGP.

2.2 Regulatory Requirements and Guidance The regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, which requires that the TSs include items in five specific categories. These categories include:

(1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions of operation (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls. More specifically, the regulation in 10 CFR 50.36(c)(2)(i) states that, When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. Section 50.36 of 10 CFR does not specify which remedial actions are required or how quickly they must be completed.

The NRC staff used Revision 5.0 of NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1 (ADAMS Accession No. ML21259A155), Specifications, and NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 2, Bases (ADAMS Accession No. ML21259A159) in its review of the TS changes proposed for Vogtle, Units 1 and 2.

The regulatory requirements in 10 CFR 50.55a, Codes and standards, specify that licensees must implement the inservice testing (IST) provisions in the applicable edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) as incorporated by reference in 10 CFR 50.55a.

2.3 Administrative Changes The addition of the notes in TS 3.6.3 impacts the subsequent TS pages and results in an additional TS page.

3.0 TECHNICAL EVALUATION

The TSTF-269-A, Revision 2, revised STS 3.6.3, Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual), by adding a note under Required Actions A.2, C.2, and E.2 that isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

The NRC staff has reviewed the proposed changes to the Vogtle, Units 1 and 2, TS 3.6.3 against this approved TSTF traveler and has determined that administrative controls for such isolation devices (i.e., isolation valves and dampers) have proven to be adequate to ensure the devices are maintained in the positions required by the plant safety analyses when primary and secondary containment is required to be operable.

Periodic verification is required for a penetration with an inoperable isolation device to detect and correct inadvertent repositioning of the isolation device. Because the purpose of locking, sealing, or securing components is to prevent inadvertent repositioning, the licensee proposed that periodic reverification should be a verification of the administrative controls that ensures that the component remains in the required state.

The TS LCO 3.6.3 states, Each containment isolation valve shall be OPERABLE. The OPERABILITY requirements for isolation devices ensure that components are capable of performing their safety functions within the time limits assumed in the safety analyses.

It is reasonable to assume that the initial establishment of component status (e.g., isolation valves closed) was performed correctly. Subsequent, verifications of the component status are intended to ensure the component has not been inadvertently repositioned. Given that the function of locking, sealing, or securing components is to ensure the same avoidance of inadvertent repositioning, the staff finds that periodic reverification using administrative means that ensure that the component remains in the required state is acceptable. Verification of the component status using administrative means avoids removing the lock, seal, or other means of securing the component solely to perform an active verification of the required state.

Verification of the inoperable containment penetrations using administrative means ensures the components will continue to be isolated, and thus, perform their isolation function. In addition, the proposed change does not involve a physical alteration to the plant (i.e., no new or different type of equipment will be installed) or a change to the methods governing normal plant operation.

Additionally, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2) will continue to be met because the minimum performance level of equipment needed for safe operation of the facility is contained in the LCO, and the appropriate remedial actions are specified if the LCO is not met.

The licensees proposed changes related to valve position verification in Vogtle, Units 1 and 2, TS 3.6.3, are distinct from the IST Program requirements for valve position verification at Vogtle, Units 1 and 2, specified in the ASME OM Code as incorporated by reference in 10 CFR 50.55a. Any proposed changes to the IST Program requirements for Vogtle, Units 1 and 2, must be submitted in accordance with 10 CFR 50.55a or as an exemption request.

Based on the above, the NRC staff concludes that the change is consistent with TSTF-269-A (since administrative means for isolation devices have proven to be adequate to ensure the devices are maintained in the positions required by the plant safety analyses). In addition, the NRC staff determined the licensees proposed variance do not affect the applicability of TSTF-269-A to the proposed license amendments, because the equivalent of Required Action E.2 of TSTF-269-A in the Vogtle, Units 1 and 2, TSs is Required Action C.2. This does not affect the applicability of TSTF-269-A to Vogtle, Units 1 and 2, so the associated change is acceptable for Vogtle, Units 1 and 2, TS C.2. The second variance for the Vogtle TS is that they do not contain a Condition equivalent to Condition C in TSTF-269-A. With the addition of the notes in TS 3.6.3, the subsequent TS pages are impacted resulting in an additional TS page 3.6.3-6; there are no technical changes with this administrative change.

For reasons described above, the NRC staff finds the proposed changes to TS 3.6.3 acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Georgia State official was notified on March 11, 2022, of the proposed issuance of the amendments. On March 11, 2022, the State official stated that he had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 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 (87 FR 9652 dated February 22, 2022), and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Rob Elliott Date: April 27, 2022

ML22069A004 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NRR/DSS/SCPB/BC NAME JLamb KGoldstein VCusumano BWittick DATE 3/9/2022 03/14/2022 3/9/2022 3/10/ 2022 OFFICE OGC - NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME JEzell EMiller for MMarkley JLamb DATE 4/1/2022 4/27/2022 4/27/2022

v t e Letter Sequence Approval
EPID:L-2021-LLA-0234, TSTF-269 (Approved, Closed)
Initiation Acceptance Administration Questions Answers Results Approval Other: NL-21-0925, Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
MONTHYEAR2022-01-13 [Table View]

ML22069A004

Text

SUBJECT:

Dear Ms. Gayheart:

Enclosures:

Attachment:

Attachment:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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