ML24330A123
| ML24330A123 | |
| Person / Time | |
|---|---|
| Site: | Farley, Vogtle  |
| Issue date: | 12/20/2024 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| Turner, Zachary | |
| References | |
| EPID L-2024-LLA-0090 | |
| Download: ML24330A123 (1) | |
Text
December 20, 2024 Jamie M. Coleman 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 AMENDMENT NOS. 251, 248, 226, AND 208 RE: REVISING TECHNICAL SPECIFICATIONS TO ADOPT TSTF-589, ELIMINATE AUTOMATIC DIESEL GENERATOR START DURING SHUTDOWN (EPID L-2024-LLA-0090)
Dear Jamie Coleman:
The U. S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 251 to Renewed Facility Operating License No. NPF-2 and Amendment No. 248 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, respectively, and Amendment No. 226 to Renewed Facility Operating License NPF-68 and Amendment No. 208 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 June 28, 2024.
For Farley, Units 1 and 2, and Vogtle, Units 1 and 2, the amendments revise the TSs to adopt Technical Specification Task Force (TSTF)-589, Eliminate Automatic Diesel Generator Start During Shutdown, which is an approved change to the Standard Technical Specifications (STS), into the Farley, Units 1 and 2, and the Vogtle, Units 1 and 2, TSs. TSTF-589 eliminates the TS requirements for automatic diesel generator (DG) start and loading during shutdown.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424, and 50-425
Enclosures:
- 1. Amendment No. 251 to NPF-2
- 2. Amendment No. 248 to NPF-8
- 3. Amendment No. 226 to NPF-68
- 4. Amendment No. 208 to NPF-81
- 5. Safety Evaluation for Farley and Vogtle, Units 1 and 2 cc: Listserv
SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 251 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 June 28, 2024, 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. 251, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Michael 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: December 20, 2024 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2024.12.20 13:10:38 -05'00'
SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 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 June 28, 2024, 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. 248, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Michael 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: December 20, 2024 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2024.12.20 13:11:41 -05'00'
ATTACHMENT JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 TO LICENSE AMENDMENT NO. 251 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 TO LICENSE AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Licenses 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 3.3.5-4 3.3.5-4 3.3.5-5 3.3.5-5 3.8.2-3 3.8.2-3
Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 251 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, 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. 248 (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. 248, 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
LOP DG Start Instrumentation 3.3.5 Farley Units 1 and 2 3.3.5-4 Amendment No. 251 (Unit 1)
Amendment No. 248 (Unit 2)
Table 3.3.5-1 (page 1 of 1)
Loss of Power Diesel Generator Start Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRAIN SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE TRIP SETPOINT
SR 3.3.5.1 SR 3.3.5.2 SR 3.3.5.3 3222 V and 3418 V 3255 V
- 2. 4.16 kV Emergency Bus Degraded Grid Voltage Actuation 1,2,3,4 3
SR 3.3.5.1 SR 3.3.5.2 SR 3.3.5.3 3638 V and 3749 V 3675 V
- 3. 4.16 kV Emergency Bus Degraged Grid Voltage Alarm 1,2,3,4 1
SR 3.3.5.1 SR 3.3.5.2 3835 V 3850 V
LOP DG Start Instrumentation 3.3.5 Farley Units 1 and 2 3.3.5-5 Amendment No. 251 (Unit 1)
Amendment No. 248 (Unit 2)
Table 3.3.5-2 (page 1 of 1)
Loss of Power Diesel Generator Start Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRAIN SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE DELAY TIME
SR 3.3.5.1 SR 3.3.5.2 SR 3.3.5.3 3222 V and 3418 V NA
- 2. 4.16 kV Emergency Bus Degraded Grid Voltage Actuation 1,2,3,4 3
SR 3.3.5.1 SR 3.3.5.2 SR 3.3.5.3 Bus 1F: 3761 V Bus 1G: 3752 V Bus 2F: 3757 V Bus 2G: 3778 V 11.4 sec 11.4 sec 9.9 sec 9.9 sec
AC Sources Shutdown 3.8.2 Farley Units 1 and 2 3.8.2-3 Amendment No. 251 (Unit 1)
Amendment No. 248 (Unit 2)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE-------------------------------
The following SRs are applicable but are not required to be performed: SR 3.8.1.8, SR 3.8.1.12, SR 3.8.1.14, and SR 3.8.1.18.
For AC sources required to be OPERABLE, the following SRs are applicable and required to be performed: SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.4, and SR 3.8.1.5.
In accordance with applicable SRs
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. 226 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 June 28, 2024, 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. 226, 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 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION Michael 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: December 20, 2024 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2024.12.20 13:12:46 -05'00'
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. 208 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 June 28, 2024, 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. 208, 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 successfully demonstrated prior to the time and condition specified below for each:
a) DELETED b) DELETED c) SR 3.8.1.20 shall be successfully demonstrated at the first regularly scheduled performance after implementation of this license amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION Michael 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: December 20, 2024 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2024.12.20 13:13:54 -05'00'
ATTACHMENT VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 TO LICENSE AMENDMENT NO. 226 RENEWED FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 TO LICENSE AMENDMENT NO. 208 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 3.3.5-1 3.3.5-1 3.3.5-2 3.3.5-2 3.8.2-3 3.8.2-3 Renewed Operating License NPF-68 Amendment No. 226 (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. 226, 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. 208 (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. 208 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
LOP Instrumentation 3.3.5 Vogtle Units 1 and 2 3.3.5-1 Amendment No. 226 (Unit 1)
Amendment No. 208 (Unit 2) 3.3 INSTRUMENTATION 3.3.5 4.16 kV ESF Bus Loss of Power (LOP) Instrumentation LCO 3.3.5 Four channels per bus of the loss of voltage Function and four channels per bus of the degraded voltage Function shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4 ACTIONS
NOTE------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Functions with only one channel on one or both buses inoperable.
NOTE-------------------
A channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing.
A.1 Place channel in trip.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.
One or more Functions with two or more channels on one bus inoperable.
B.1 Restore at least three channels to OPERABLE status.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C.
One or more Functions with two or more channels on two buses inoperable.
C.1 Restore at least three channels on one bus to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)
LOP Instrumentation 3.3.5 Vogtle Units 1 and 2 3.3.5-2 Amendment No. 226 (Unit 1)
Amendment No. 208 (Unit 2)
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Actions and associated Completion Times not met in MODES 1, 2, 3, or 4.
D.1 Be in MODE 3.
AND D.2 Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform COT.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Perform CHANNEL CALIBRATION with Nominal Trip Setpoint and Allowable Value as follows:
A.
Loss of voltage Allowable Value 2958.2 V with a time delay of 0.8 second.
Loss of voltage Nominal Trip Setpoint 2975 V with a time delay of 0.8 second.
B.
Degraded voltage Allowable Value 3729.2 V with a time delay of 20 seconds.
Degraded voltage Nominal Trip Setpoint 3746 V with a time delay of 20 seconds.
In accordance with the Surveillance Frequency Control Program (continued)
AC Sources Shutdown 3.8.2 Vogtle Units 1 and 2 3.8.2-3 Amendment No. 226 (Unit 1)
Amendment No. 208 (Unit 2)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE----------------------------
The following SRs are applicable but not required to be performed:
SR 3.8.1.3 SR 3.8.1.8 SR 3.8.1.9 SR 3.8.1.13 SR 3.8.1.15 SR 3.8.1.19 For AC sources required to be OPERABLE, the following SRs of Specification 3.8.1 are applicable:
SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 (see Note)
SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.8 (see Note)
SR 3.8.1.9 (see Note)
SR 3.8.1.13 (see Note)
SR 3.8.1.15 (see Note)
SR 3.8.1.19 (see Note)
In accordance with applicable SRs
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AMENDMENT NO. 251 TO RENEWED FACILITY OPERATING LICENSE NPF-2 AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NPF-8 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 AMENDMENT NO. 226 TO RENEWED FACILITY OPERATING LICENSE NPF-68 AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NOS. 50-348, 50-364, 50-424, AND 50-425
1.0 PROPOSED CHANGE
S By letter dated June 28, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24180A236), Southern Nuclear Operating Company (SNC, the licensee) requested changes to the technical specifications (TSs) for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, and Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, by license amendment request (LAR, application). In its LAR, SNC requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed LAR under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TS based on Technical Specifications Task Force (TSTF) Traveler TSTF-589, Revision 0, Eliminate Automatic Diesel Generator [DG] Start During Shutdown (TSTF-589)
(ML22034A015), and the associated NRC staff safety evaluation (SE) of TSTF-589 (ML23241B040).
The proposed changes would eliminate the TS requirements for the automatic DG start and loading capability to be OPERABLE during shutdown and modifies which DG surveillance requirements (SRs) are required during shutdown.
=
System Description===
This system description applies to both Farley, Units 1 and 2, and Vogtle, Units 1 and 2, unless noted otherwise.
The Class 1E alternating current (AC) electrical power system provides a reliable source of power to the engineered safety feature (ESF) systems. The design provides independence and redundancy to ensure a reliable source of power to the Class 1E system. The AC electrical power system includes offsite power sources and Class 1E onsite standby power sources (i.e.,
DGs) that supply electrical power to independent ESF load groups, with each load group consisting of one or more Class 1E ESF buses. Each load group has connections to offsite power sources and one or more DGs.
The DGs provide AC power during a loss of offsite power (LOOP). A DG starts automatically on a LOOP signal based on an ESF bus degraded voltage or undervoltage signal, or an ESF (safety injection) signal. After the DG starts, it automatically ties to its respective Class 1E ESF bus in case of LOOP signal, or coincident with an ESF signal. In the event of a LOOP or LOOP coincident with an accident, the ESF electrical loads are automatically connected to the DG in time to provide for safe reactor shutdown and to mitigate the consequences of a design-basis accident such as a loss of coolant accident.
1.1 Proposed TS Changes to Adopt TSTF-589 Proposed Changes to Instrumentation, TS 3.3 The licensee proposed the following changes to the Farley, Units 1 and 2, and Vogtle, Units 1 and 2, TSs consistent with TSTF-589.
Farley In Farley, Units 1 and 2, TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, SNC is proposing to delete footnote (a) of TS Tables 3.3.5-1 and 3.3.5-2, which state: When associated DG is required to be OPERABLE by LCO 3.8.2, AC Sources -
Shutdown.
Vogtle In Vogtle, Units 1 and 2, TS 3.3.5, 4.16 kV ESF Bus Loss of Power (LOP) Instrumentation, SNC proposes to delete from the APPLICABILITY statement the following: When associated Diesel Generator is required to be OPERABLE by LCO 3.8.2, AC Sources - Shutdown. The deleted phrase would change the Limiting Condition for Operation (LCO) by no longer requiring the automatic start and loading signals for the DGs to be OPERABLE during shutdown.
SNC also proposes to delete CONDITION E of TS 3.3.5, which states: Required Action and associated Completion Time not met when the associated DG is required OPERABLE by LCO 3.8.2.
SNC proposes to delete REQUIRED ACTION E.1 of TS 3.3.5, which states: Enter applicable Condition(s) and Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.
SNC proposes to delete COMPLETION TIME E of TS 3.3.5, which states: Immediately.
Proposed Changes to Alternating Current Sources - Shutdown, TS 3.8.2 The following are the proposed changes to AC Sources - Shutdown in TS 3.8.2.
Farley In Farley, Units 1 and 2, TS 3.8.1, AC Sources - Operating, SNC proposes to delete the following text from SR 3.8.2.1 shown in strikethrough format:
NOTE-------------------------------
The following SRs are applicable but are not required to be performed: SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.14, and SR 3.8.1.18.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC SourcesOperating,"
except SR 3.8.1.3, SR 3.8.1.7, SR 3.8.1.10, SR 3.8.1.15, SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.19, are applicable. The following SRs are applicable and required to be performed: SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.4, and SR 3.8.1.5, and SR 3.8.1.6.
TS 3.8.1, AC Sources - Operating, contains requirements on AC sources (offsite power and DGs) in MODES 1, 2, 3, and 4. Currently, TS 3.8.2, AC Sources - Shutdown SR 3.8.2.1 requires most of the TS 3.8.1 SRs to be applicable during shutdown, except for a list of excepted SRs. Farley, Units 1 and 2, SR 3.8.2.1 would be revised to state which of the TS 3.8.1 SRs are applicable instead of which of the TS 3.8.1 SRs that are not applicable.
The automatic start and loading capabilities of the DGs are no longer required to be OPERABLE during shutdown and the SRs that test the automatic start are no longer applicable during shutdown. Therefore, the following TS 3.8.1 SR would no longer be applicable (required to be met or performed): Farley, Units 1 and 2, SR 3.8.1.6.
Additionally, TS SR 3.8.2.1 currently has a Note that lists the TS 3.8.1 SRs that are applicable (i.e., must be met) but are not required to be performed. The TS 3.8.2.1 Note stating which of the TS 3.8.1 SRs are applicable (must be met) but not required to be performed, would be revised to delete the SRs that are no longer appliable because the automatic start and loading signals for the DGs are not required during shutdown. The capability to meet the acceptance criteria in the remaining SRs must be present, but SNC would not be required to perform the SRs. Farley, Units 1 and 2, SR 3.8.2.1 Note would be revised to delete following SRs (no longer applicable): SR 3.8.1.9, SR 3.8.1.11, and SR 3.8.1.13.
Vogtle For Vogtle, Units 1 and 2, TS 3.8.1, AC Sources - Operating, SNC proposes to delete the following text from SR 3.8.2.1 shown in strikethrough format:
NOTE----------------------------
The following SRs are applicable but not required to be performed:
SR 3.8.1.3 SR 3.8.1.8 SR 3.8.1.9 SR 3.8.1.10 (except 3.8.1.10.c.2)
SR 3.8.1.13 SR 3.8.1.14 SR 3.8.1.15 SR 3.8.1.19 For AC sources required to be OPERABLE, the following SRs of Specification 3.8.1 are applicable:
SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 (see Note)
SR 3.8.1.4 SR 3.8.1.5 SR 3.8.1.6 SR 3.8.1.7 SR 3.8.1.8 (see Note)
SR 3.8.1.9 (see Note)
SR 3.8.1.10 (except 3.8.1.10.c2)
(see Note)
SR 3.8.1.13 (see Note)
SR 3.8.1.14 (see Note)
SR 3.8.1.15 (see Note)
SR 3.8.1.19 (see Note)
The automatic start and loading capabilities of the DGs are no longer required to be OPERABLE during shutdown and the SRs that test the automatic start are no longer applicable during shutdown. Therefore, the following TS 3.8.1 SRs would no longer be applicable (required to be met or performed): Vogtle, Units 1 and 2, SR 3.8.1.7, SR 3.8.1.10, and SR 3.8.1.14.
Additionally, TS SR 3.8.2.1 currently has a Note that lists the TS 3.8.1 SRs that are applicable (i.e., must be met) but are not required to be performed. The TS 3.8.2.1 Note stating which of the TS 3.8.1 SRs are applicable (must be met) but not required to be performed, would be revised to delete the SRs that are no longer appliable because the automatic start and loading signals for the DGs are not required during shutdown. The capability to meet the acceptance criteria in the remaining SRs must be present, but SNC would not be required to perform the SRs. Vogtle, Units 1 and 2, SR 3.8.2.1 Note would be revised to delete the following SRs (no longer applicable): SR 3.8.1.10, and SR 3.8.1.14.
1.2 Additional Proposed TS Changes 1.2.1 Variations from TSTF-589 That Do Not Affect the Applicability of the Traveler In some cases, Farley, Units 1 and 2, and Vogtle, Units 1 and 2, TS utilize different numbering than the STS on which TSTF-589 was based.
Farley The existing TS 3.3.5 is different from the STS TS 3.3.5. Specifically, the Applicability of Farleys TS 3.3.5 refers to Tables for applicability of the TS to the LCO Functions.
Although contained in Tables, the Applicability portion of the Tables includes MODES 1, 2, 3, 4 and references a Table footnote that addresses the applicability when an associated DG is required to be OPERABLE by TS 3.8.2. This is equivalent to the STS Applicability. The Table footnote is proposed to be deleted in place of the marked-up Applicability in TSTF-589.
The existing SR 3.8.2.1 differs from the STS SR 3.8.2.1. The existing SR 3.8.2.1 contains differences in the applicable 3.8.1 SRs which must be met or performed.
Specifically, SR 3.8.1.3 must be met but not performed for the STS. For Farley, SR 3.8.1.3 is not required to be met. Also, STS SR 3.8.1.5 is not applicable to Farley and does not appear in SR 3.8.2.1. Additionally, SR 3.8.1.18 in the STS must be met but not performed; however, the equivalent Farley SR 3.8.1.16 is not required to be met.
Vogtle The existing TS 3.3.5 is different from the STS TS 3.3.5. Specifically, Condition E provides the Required Actions for an associated DG that is required to be OPERABLE by LCO 3.8.2. This provision does not directly appear in the STS. The STS contains one Condition (Condition C) that addresses DG OPERABILITY in both MODES 1 through 4 and MODES 5 and 6. Although the STS Condition is not changed by this TSTF, the related TS Bases remove the reference to a DG required to be OPERABLE in TS 3.8.2.
To accomplish the same change, Condition E and its related TS Bases must be deleted from the Vogtle TS 3.3.5.
The existing SR 3.8.2.1 differs from the STS SR 3.8.2.1. The existing SR 3.8.2.1 contains differences in the applicable 3.8.1 SRs which must be met or performed.
Specifically, STS 3.8.1.8 is not applicable to Vogtle and does not appear in SR 3.8.2.1.
Also, SR 3.8.1.13 must be met but not performed for the STS. For Vogtle, the equivalent SR 3.8.1.12 is not required to be met. Additionally, SR 3.8.1.18 in the STS must be met but not performed, however the equivalent Vogtle SR 3.8.1.17 is not required to be met.
The existing SR 3.8.2.1 lists one different applicable 3.8.1 SR than the STS. Vogtle has SR 3.8.1.19 to verify the fuel transfer pump transfers fuel via a cross connect line. This SR is not contained in the STS. Vogtle SR 3.8.1.19 must be met, but not performed in SR 3.8.2.1.
2.0 REGULATORY EVALUATION
The categories of items required to be in the TSs are listed in Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c). The regulation at 10 CFR 50.36(c)(2) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that
[w]hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
The regulation at 10 CFR 50.36(c)(3) requires that TSs include items in the category of SRs, which 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 limiting conditions for operation 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 (ML100351425).
As described therein, the NRC staff has prepared STSs for each of the LWR nuclear designs.
Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21259A155 and ML21259A159, respectively), as modified by NRC-approved travelers. The NRC staff approved TSTF-589, under the CLIIP on September 11, 2023 (ML23241B051).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-589 The NRC staff compared the proposed TS changes described in section 1.1 of this SE against the changes approved in TSTF-589. In accordance with the SRP chapter 16.0, the NRC staff determined that TSTF-589 is applicable to the proposed TS changes because Farley, Units 1 and 2, and Vogtle, Units 1 and 2, are a pressurized-water reactor (PWR) design plant and the NRC staff approved the TSTF-589 changes for PWR designs. The NRC staff finds that the proposed changes to the Farley, Units 1 and 2, and Vogtle, Units 1 and 2, TSs described in section 1.1 of this SE are consistent with those found acceptable in TSTF-589.
In the NRC SE of TSTF-589, the NRC staff concluded that the proposal to eliminate the TS requirements for the automatic DG start and loading capability to be operable during shutdown and the modification of which DG SRs are applicable during shutdown, is acceptable. Testing of the DG automatic start and load capabilities is not required to demonstrate the operability of the DG during shutdown conditions, because the DG automatic start is not required to mitigate the consequences of postulated events in shutdown conditions. Therefore, 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3) will continue to be met because the revised TS 3.3.5, and SR 3.8.2.1 will continue to assure that the necessary quality of the onsite standby power systems and components is maintained, that facility operation will be within safety limits, and that the associated LCOs will be met. Thus, the proposed changes continue to meet the requirements of 10 CFR 50.36(c) as discussed in section 3.0 of the NRC staffs SE of TSTF-589.
3.2 Additional Proposed TS Changes 3.2.1 Variations That Do Not Affect the Applicability of the Traveler
- 1. In the LAR, SNC noted that the existing Farley TS 3.3.5 is different from the STS TS 3.3.5 because the applicability of TS 3.3.5 refers to Tables 3.3.5-1 and 3.3.5-2.
Although contained in Tables, the Applicability portion of the Tables includes MODES 1, 2, 3, 4 and references a Table footnote that addresses the applicability when an associated DG is required to be OPERABLE by TS 3.8.2. The NRC staff finds the proposed difference is acceptable, because the tables contain the MODES of applicability and address when the associated DG is required to be OPERABLE and is
equivalent to the STS applicability. These differences continue to meet the intent of TSTF-589.
- 2. In the LAR, the licensee noted that the existing Farley SR 3.8.1.3 is not required to be met, even though SR 3.8.1.3 must be met but not performed for the STS. Also, STS SR 3.8.1.5 is not applicable to Farley and does not appear in SR 3.8.2.1. Additionally, SR 3.8.1.18 in the STS must be met but not performed; however, the equivalent Farley SR 3.8.1.16 is not required to be met. The NRC staff finds that the proposed change does not include SR 3.8.1.3, SR 3.8.1.5, or SR 3.8.1.16 in the SR 3.8.2.1. However, the NRC staff finds these differences are acceptable, because currently the Farley SR 3.8.1.3 and SR 3.8.1.16 are not required to be met and SR 3.8.1.5 is not applicable to Farley; therefore, they do not need to be included in the changes to SR 3.8.2.1. These differences continue to meet the intent of TSTF-589.
- 3. In the LAR, SNC noted that existing Vogtle TS 3.3.5 is different from the STS, because it contains a Condition E which provides the Required Actions for an associated DG that is required to be OPERABLE by LCO 3.8.2. This provision does not directly appear in the STS because it contains one Condition (Condition C) that addresses DG OPERABILITY in both MODES 1 through 4 and MODES 5 and 6. SNC is proposing to delete Vogtle TS 3.3.5 Condition E. The NRC staff finds the proposed change to delete TS 3.3.5 Condition E is acceptable because Vogtle has a separate Condition D which will continue to include Required Actions for associated Completion Times that are not met in MODES 1, 2, 3, or 4. Current Condition E is only associated with the Required Action and Completion Time that are not met when the associated DG is required OPERABLE by LCO 3.8.2, which is removed by TSTF-589.
- 4. In the LAR, SNC noted that the existing Vogtle SR 3.8.2.1 contains differences in the applicable 3.8.1 SRs which must be met or performed. Specifically, STS 3.8.1.8 is not applicable to Vogtle and does not appear in SR 3.8.2.1. Also, SR 3.8.1.13 and SR 3.8.1.18 must be met but not performed for the STS; however, the equivalent Vogtle SR 3.8.1.12 and 3.8.1.17 are not required to be met. The NRC staff finds that the proposed change does not include SR 3.8.1.8, SR 3.8.1.12, or SR 3.8.1.17 in the SR 3.8.2.1. However, the NRC staff finds these differences are acceptable, because currently the Vogtle SR 3.8.1.12 and SR 3.8.1.17 are not required to be met and SR 3.8.1.8 is not applicable to Vogtle; therefore, they do not need to be included in the changes to SR 3.8.2.1. These differences continue to meet the intent of TSTF-589.
- 5. In the LAR, the licensee noted that Vogtle has SR 3.8.1.19 to verify the fuel transfer pump transfers fuel via a cross connect line. This SR is not contained in the STS.
Currently, Vogtle SR 3.8.2.1 lists SR 3.8.1.19 to be applicable but not required to be performed. The NRC staff finds this difference to include SR 3.8.1.19 is acceptable because it is currently listed as an SR that must be met but not performed and continues to meet the intent of TSTF-589.
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 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia and Alabama State officials were notified of the proposed issuance of the amendments on November 4, 2024. The Alabama State official replied on November 5, 2024, and had no comments. The Georgia State official replied on December 10, 2024, and had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements 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, published in the Federal Register on August 6, 2024 (89 FR 63993), and there has been no public comment on such finding.
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Tarico Sweat Date: December 20, 2024
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