ML23072A065
| ML23072A065 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar, Sequoyah  |
| Issue date: | 04/05/2023 |
| From: | Perry Buckberg Plant Licensing Branch II |
| To: | Jim Barstow Tennessee Valley Authority |
| Wentzel M | |
| References | |
| EPID L-2022-LLA-0103 | |
| Download: ML23072A065 (30) | |
Text
April 5, 2023
Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2; WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 364 AND 358; 160 AND 68 REGARDING A REVISION TO TECHNICAL SPECIFICATION 3.4.12 (EPID L-2022-LLA-0103)
Dear Mr. Barstow:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment Nos. 364 and 358 to Renewed Facility Operating License Nos. DPR-77 and DPR-79, for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively; and Amendment Nos. 160 and 68 to Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant (WBN), Units 1 and 2, respectively. The amendments consist of changes to each Plants Technical Specification (TS) 3.4.12 in response to your application dated July 27, 2022, as supplemented on January 4, 2023.
The amendments revise SQN Units 1 and 2 TS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, and the WBN Units 1 and 2 TS 3.4.12 Cold Overpressure Mitigation System (COMS), to add a note to the Limiting Condition for Operation that one safety injection pump and one centrifugal charging pump may be capable of injecting into the reactor coolant system for the purpose of testing in MODE 5 (cold shutdown) or MODE 6 (refueling) with the pressurizer manway cover removed to provide a vent path for adequate pressure relief.
J. Barstow
A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-327, 50-328, 50-390, and 50-391
Enclosures:
- 1. Amendment No. 364 to DPR-77
- 2. Amendment No. 358 to DPR-79
- 3. Amendment No. 160 to NPF-90
- 4. Amendment No. 68 to NPF-96
- 5. Safety Evaluation
cc: Listserv TENNESSEE VALLEY AUTHORITY
DOCKET NO. 50-327
SEQUOYAH NUCLEAR PLANT, UNIT 1
AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE
Amendment No. 364 Renewed License No. DPR-77
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (the licensee) dated July 27, 2022, as supplemented on January 4, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 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. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 364, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications
Date of Issuance: April 5, 2023
ATTACHMENT TO LICENSE AMENDMENT NO. 364
SEQUOYAH NUCLEAR PLANT, UNIT 1
RENEWED FACILITY OPERATING LICENSE NO. DPR-77
DOCKET NO. 50-327
Replace page 3 of Renewed Facility Operating License No. DPR-77 with the attached page 3.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A, Technical Specifications, with the attached page.
The revised page is identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.4.12-1 3.4.12-1
(3) 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;
(4) 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; and
(5) 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 Sequoyah and Watts Bar Unit 1 Nuclear Plants.
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 incorporated below:
(1) Maximum Power Level
The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.
(2) Technical Specifications
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 364 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Initial Test Program
The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authoritys Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
- a. Elimination of any test identified in Section 14 of TVAs Final Safety Analysis Report as amended as being essential;
- b. Modification of test objectives, methods, or acceptance criteria for any test identified in Section 14 of TVAs Final Safety Analysis Report as amended as being essential;
Amendment No. 364 Renewed License No. DPR-77 LTOP System 3.4.12
3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.12 Low Temperature Overpressure Protection (LTOP) System
LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
- a. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR; or
NOTES-------------------------------------------
- 1. Two charging pumps may be made capable of injecting for d 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
- 2. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
- 3. Two safety injection pumps and two charging pumps may be capable of injecting for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering MODE 4 from MODE 3 or prior to lowering temperature on any RCS loop below 325°F, whichever occurs first.
- 4. One safety injection pump and one charging pump may be capable of injecting into the RCS for the purpose of testing in MODE 5 or MODE 6 when the reactor vessel head is on, provided the pressurizer manway cover is removed to provide a vent path for adequate pressure relief.
APPLICABILITY: MODE 4 when any RCS cold leg temperature is LTOP arming temperature specified in the PTLR, MODE 5, MODE 6 when the reactor vessel head is on.
SEQUOYAH - UNIT 1 3.4.12-1 Amendment
TENNESSEE VALLEY AUTHORITY
DOCKET NO. 50-328
SEQUOYAH NUCLEAR PLANT, UNIT 2
AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE
Amendment No. 358 Renewed License No. DPR-79
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (the licensee) dated July 27, 2022, as supplemented on January 4, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 2
- 2 -
- 2. Accordingly, the license is amended by changes to the Technical Specif ications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-79 is hereby amended to read as follo ws:
(2) Technical Specifications
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 358, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications
Date of Issuance: April 5, 2023 ATTACHMENT TO LICENSE AMENDMENT NO. 358
SEQUOYAH NUCLEAR PLANT, UNIT 2
RENEWED FACILITY OPERATING LICENSE NO. DPR-79
DOCKET NO. 50-328
Replace page 3 of Renewed Facility Operating License No. DPR-79 with the attached page 3.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.4.12-1 3.4.12-1
(3) 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;
(4) 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; and
(5) 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 Sequoyah and Watts Bar Unit 1 Nuclear Plants.
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 incorporated below:
(1) Maximum Power Level
The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.
(2) Technical Specifications
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 358 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Initial Test Program
The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authoritys Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have b een identified and have received prior NRC approval. Major modifications are defined as:
- a. Elimination of any test identified in Section 14 of TVAs Final Safety Analysis Report as amended as being essential;
Amendment No. 358 Renewed License No. DPR-79 LTOP System 3.4.12
3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.12 Low Temperature Overpressure Protection (LTOP) System
LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
- a. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR; or
NOTES-------------------------------------------
- 1. Two charging pumps may be made capable of injecting for d 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
- 2. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
- 3. Two safety injection pumps and two charging pumps may be capable of injecting for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering MODE 4 from MODE 3 or prior to lowering temperature on any RCS loop below 325°F, whichever occurs first.
- 4. One safety injection pump and one charging pump may be capable of injecting into the RCS for the purpose of testing in MODE 5 or MODE 6 when the reactor vessel head is on, provided the pressurizer manway cover is removed to provide a vent path for adequate pressure relief.
APPLICABILITY: MODE 4 when any RCS cold leg temperature is LTOP arming temperature specified in the PTLR, MODE 5, MODE 6 when the reactor vessel head is on.
SEQUOYAH - UNIT 2 3.4.12-1 Amendment
TENNESSEE VALLEY AUTHORITY
DOCKET NO. 50-390
WATTS BAR NUCLEAR PLANT, UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 160 License No. NPF-90
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA) dated July 27, 2022, as supplemented on January 4, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 3
- 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 Facility Operating License No. NPF-90 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A as revised through Amendment No. 160 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications
Date of Issuance: April 5, 2023
ATTACHMENT TO AMENDMENT NO. 160
WATTS BAR NUCLEAR PLANT, UNIT 1
FACILITY OPERATING LICENSE NO. NPF-90
DOCKET NO. 50-390
Replace page 3 of Renewed Facility Operating License No. NPF-90 with the attached page 3.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A, Technical Specifications, with the attached page.
The revised page is identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.4-25 3.4-25
(4) TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and
(5) TVA, 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 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 incorporated below.
(1) Maximum Power Level
TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A as revised through Amendment No. 160 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Unit 1 Facility License No. NPF-90 Amendment No. 160 COMS 3.4.12
3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.12 Cold Overpressure Mitigation System (COMS)
LCO 3.4.12 A COMS System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and either a or b below.
D Two RCS relief valves, as follows:
Two power operated relief valves (PORVs) with lift settingswithin the limits specified in the PTLR, or
One PORV with a lift setting within the limits specified in thePTLR and the RHR suction relief valve with a setpoint t 436.5 psig and d 463.5 psig.
E The RCS depressurized and an RCS vent capable of relieving > 475JSP
water flow.
NOTES------------------------------------------------------- ------
- 1. Two charging pumps may be made capable of injecting for less than or equal to one hour for pump swap operations.
- 2. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS Pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
- 3. One safety injection pump and one charging pump may be capable of injecting into the RCS for the purpose of testing in MODE 5 or MODE 6 when the reactor vessel head is on, provided the pressurizer manway cover is removed to provide a vent path for adequate pressure relief.
APPLICABILITY: MODES 4 and 5, MODE 6 when the reactor vessel head is on.
Watts Bar-Unit 1 3.4-25 Amendment
TENNESSEE VALLEY AUTHORITY
DOCKET NO. 50-391
WATTS BAR NUCLEAR PLANT, UNIT 2
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 68 License No. NPF-96
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (TVA) dated July 27, 2022, as supplemented on January 4, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 4
- 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 Facility Operating License No. NPF-96 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A as revised through Amendment No. 68 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications
Date of Issuance: April 5, 2023
ATTACHMENT TO AMENDMENT NO. 68
WATTS BAR NUCLEAR PLANT, UNIT 2
FACILITY OPERATING LICENSE NO. NPF-96
DOCKET NO. 50-391
Replace page 3 of Facility Operating License No. NPF-96 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A, Technical Specifications, with the attached page.
The revised page is identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.4-23 3.4-23
C. The 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 incorporated below.
(1) Maximum Power Level
TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A as revised through Amendment No. 68 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) TVA shall implement permanent modifications to prevent overtopping of the embankments of the Fort Loudon Dam due to the Probable Maximum Flood by June 30, 2018.
(4) FULL SPECTRUM LOCA Methodology shall be implemented when the WBN Unit 2 steam generators are replaced with steam generators equivalent to the existing steam generators at WBN Unit 1.
(5) By December 31, 2019, the licensee shall report to the NRC that the actions to resolve the issues identified in Bulletin 2012-01, Design Vulnerability in Electrical Power System, have been implemented.
(6) The licensee shall maintain in effect the provisions of the physical security plan, security personnel training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90 and 50.54(p).
(7) TVA shall fully implement and maintain in effect all provisions of the Commission approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The TVA approved CSP was discussed in NUREG-0847, Supplement 28, as amended by changes approved in License Amendment No. 7.
(8) TVA shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility, as described in NUREG-0847, Supplement 29, subject to the following provision:
Unit 2 Facility Operating License No. NPF-96 Amendment No. 68 COMS 3.4.12
3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.12 Cold Overpressure Mitigation System (COMS)
LCO 3.4.12 A COMS System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and either a or b below.
- a. Two RCS relief valves, as follows:
- 1. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or
- 2. One PORV with a lift setting within the limits specified in the PTLR and the RHR suction relief valve with a setpoint t 436.5 psig and d 463.5 psig.
> 475 gpm water flow.
NOTE--------------------------------------------
- 1. Two charging pumps may be made capable of injecting for less than or equal to one hour for pump swap operations.
- 2. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
- 3. One safety injection pump and one charging pump may be capable of injecting into the RCS for the purpose of testing in MODE 5 or MODE 6 when the reactor vessel head is on, provided the pressurizer manway cover is removed to provide a vent path for adequate pressure relief.
APPLICABILITY: MODE 4 with any RCS cold leg temperature d to the COMS arming temperature specified in the PTLR, MODE 5, MODE 6 when the reactor vessel head is on.
Watts Bar - Unit 2 3.4-23 Amendment1R
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 364 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-77 AMENDMENT NO. 358 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-79 AMENDMENT NO. 160 TO FACILITY OPERATING LICENSE NO. NPF-90 AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. NPF-96 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-327, 50-328, 50-390, AND 50-391
1.0 INTRODUCTION
By letter dated July 27, 2022 (Reference 1), as supplemented by a letter dated January 4, 2023 (Reference 2), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, and the Watts Bar Nuclear Plant (WBN), Units 1 and 2 respectively, to th e U.S. Nuclear Regulatory Commission (NRC, the Commission).
The requested change would revise SQN Units 1 and 2 Technical Specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System, and the WBN Units 1 and 2 TS 3.4.12, Cold Overpressure Mitigation System (COMS), to add a note to the Limiting Condition for Operation (LCO) that one safety injection pump (SIP) and one centrifugal charging pump (CCP) may be capable of injecting into the reactor coolant system (RCS) for purpose of testing in MODE 5 (cold shutdown) or MODE 6 (refueling) with the pressurizer manway cover removed to provide a vent path for adequate pressure relief.
To support its review, the NRC staff request ed additional information from the licensee in an e-mail dated December 8, 2022 (Reference 3). The licensee responded to the request for additional information (RAI) in the January 4, 2023, supplemental letter. The supplemental letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on September 6, 2022 (87 FR 54554).
1.1 System Description
The LTOP System at SQN and the COMS at WBN controls the RCS pressure at low temperatures, so the integrity of the reactor coolant pressure boundary is not compromised by violating the pressure and temperature (P/T) limits.
For the SQN and the WBN units, the respective LCO 3.4.3, RCS Pressure and Temperature (P/T) Limits, require administrative control of the RCS pressure and temperature during heatup and cooldown to prevent exceeding the Pressure and Temperature Limits Report (PTLR) limits.
Further, the respective TS 3.4.12 for the SQN and the WBN units provide RCS overpressure protection by having a minimum coolant input capability and having adequate pressure relief
Enclosure 5
capacity. Limiting coolant input capability requires all SIPs and all but one CCP incapable of injection into the RCS and isolating the accumulators. The pressure relief capacity requires either two redundant power-operated relief valves (PORV) or a depressurized RCS and an RCS vent of sufficient size. One PORV or the open RCS vent is the overpressure protection device that acts to terminate an increasing pressure event.
The licensee describes the LTOP System at SQN in section 2.1 of the enclosure to the LAR as follows:
To provide a back-up to the operator and to minimize the possibility of RCS overpressurization, an automatic low temperature overpressure protection (LTOP) system, when manually armed from the main control room, will mitigate the pressure excursion within the allowable pressure lim its. The LTOP mitigation system is required only during low temperature operation and is manually enabled for automatic actuation.
The LTOP System for pressure relief consists of two PORVs with reduced lift settings, or depressurized RCS and an RCS vent of sufficient size.
Similarly, the licensee describes the COMS at WBN in section 2.2 of the enclosure to the LAR as follows:
To provide a back-up to the operator and to minimize the possibility of RCS overpressurization, an automatic COMS, when manually armed from the main control room, will mitigate the pressure excursion within the allowable pressure limits. The COMS is required only during low temperature operation and is manually enabled for automatic actuation. The COMS for pressure relief consists of two PORVs with reduced lift settings, or one PORV and the Residual Heat Removal (RHR) suction relief valve, or a depressurized RCS and an RCS vent of sufficient size.
1.2 Proposed Changes
The licensee proposed to add a note to SQN TS 3.4.12 and WBN TS 3.4.12 to permit one CCP and one safety injection system to be capable of injecting into RCS while in MODE 5 and MODE 6 for testing purposes. For SQN Unit 2, this new note will replace the note that was added as a one-time change under Amendment 350 (Reference 4).
This change will provide licensee with outage flexibility in scheduling periodic surveillances and critical-path activities during an outage.
Precedence for this change occurred when a one-time change to add a note to Sequoyah Unit 2 TS 3.4.12 was approved in Reference 4 for the purpose of testing the 2A-A SIP during the cycle 24 refueling outage.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.36, TSs for operating reactors are required, in part, to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
Paragraph 50.36(c)(2)(i) of 10 CFR states that LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility, and when an LCO of
a reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
SQN Units 1 and 2 were designed to meet the intent of the Proposed General Design Criteria for Nuclear Power Plant Construction Permits published in July 1967 (Proposed GDC). The SQN construction permit was issued in May 1970. Section 3.1.2 of the SQN Updated Final Safety Analysis Report (UFSAR) (ML22124A010), however, addresses the general design criteria published as Appendix A, General Design Criteria for Nuclear Power Plants (GDC), to 10 CFR Part 50 in July 1971.
WBN Units 1 and 2 were designed to meet the intent of the Proposed General Design Criteria for Nuclear Power Plant Construction Permits published in July 1968 (Proposed GDC). The WBN construction permit was issued in January 1973. Section 3.1.2 of the WBN UFSAR (ML22152A118), however, addresses the general design criteria published as Appendix A, GDC, to 10 CFR Part 50 in July 1971.
Each criterion is followed by a discussion of the design features and procedures that meet the intent of the criteria. Any exception to the 1971 GDC resulting from the earlier commitments is identified in the discussion of the corresponding criterion. However, the UFSARs for either plant indicated no exceptions to the 1971 GDC used by the staff in its review.
The 10 CFR Part 50, Appendix A, GDC applicable to this LAR are as follows:
GDC 14, Reactor Coolant Pressure Boundary, the reactor coolant pressure boundary shall be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture.
GDC 15, Reactor Coolant (RC) System Design, the RC System and associated auxiliary, control, and protection systems shall be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences.
GDC 31, Fracture Prevention of Reactor Coolant Pressure Boundary, the reactor coolant pressure boundary shall be designed with sufficient margin to assure that when stressed under operating, maintenance, testing, and postulated accident conditions (1) the boundary behaves in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized. The design shall reflect consideration of service temperatures and other conditions of the boundary material under operating, maintenance, testing, and postulated accident conditions and the uncertainties in determining (1) material properties, (2) the effects of irradiation on material properties, (3) residual, steady-state and transient stresses, and (4) size of flaws.
3.0 TECHNICAL EVALUATION
The NRC staff evaluated the LAR to determine if the proposed changes are consistent with the guidance, regulations, and plant-specific design and licensing basis information discussed in section 2.0 of this safety evaluation. The NRC staff reviewed the licensees statements in the LAR, the relevant sections of the licensees UFSAR, and TS Bases to determine if the proposed changes are acceptable.
3.1 Evaluation of SQN Proposed Configuration
The existing SQN TS 3.4.12 allows a maximum of one CCP and no SIPs capable of injecting into the RCS during MODES 4, 5, and 6. To provide overpressure protection, LCO 3.4.12 requires one of the following pressure relief capabilities:
The analyses described in section 5.2.2.4.2 of the SQN UFSAR demonstrate that a single PORV can maintain RCS pressure below limits when a single CCP is actuated. The NRC staff notes that two PORVs are required in the LCO to account for a single failure of one PORV.
Based on the UFSAR analysis, the current LCO allows only one CCP capable of injecting into the RCS when the LTOP System is required to be operable. As specified in LCO 3.4.12.b, in place of the PORVs, a depressurized RCS with a vent area of 3.0 square inches (in2) may also be used. Both a PORV and a 3.0 in 2 vent have limited overpressure relief capability and may not be capable of maintaining the pressure below the limits if additional mass is injected into the RCS. For the purposes of testing, the licensee is requesting the ability to have one SIP, in addition to the one CCP, capable of injecting into the RCS while the unit is in MODES 5 or 6 provided the pressurizer manway is opened as a vent.
Table 6.3.2-1 of the SQN UFSAR shows that the maximum flow rate for a CCP and a SIP are 550 gallons per minute (gpm) and 650 gpm, respectively. To accommodate this additional flow, the LTOP System would have to be capable of relieving both the mass input of its design basis transient from the CCP in addition to the SIP injection. Rather than performing a reanalysis of the LTOP System with potential changes to the setpoints for the pressurizer PORVs, the licensee stated that the RCS will instead be vented to the containment atmosphere through the pressurizer manway for the duration that the SIP will be capable of injecting into the RCS.
In the January 4, 2023, response to the NRC staffs RAI, the licensee performed an analysis for SQN to show that the pressurizer manway opening is sufficient to prohibit the overpressurization of the RCS if a SIP was also capable of injecting during the LTOP System modes of applicability. The licensee performed calculations for the backpressure that could be developed across the manway using the Westinghouse Electric Company (Westinghouse) provided flow resistance method as well as using two methods from the Crane Engineering Division Technical Paper No. 410, Flow of Fluids through Valves, Fittings, and Pipe. The analyses showed that the relief capacity of the pressurizer manway (approximately 16-inch diameter) is more than sufficient to address the combined multiple injection transient of the centrifugal CCP and SIP.
With the open pressurizer manway having a flow area of approximately 201 in 2, the combined maximum CCP and SIP flow rates vented through the open pressurizer manway would not be capable of inducing a backpressure that approaches the lowest PORV setpoint. The NRC staff finds that the RCS will not be challenged due to overpressure from the additional mass injected by the proposed additional SIP in MODES 5 or 6 at SQN.
3.2 Evaluation of WBN Proposed Configuration
The existing WBN TS 3.4.12 allows a maximum of one CCP and no SIP capable of injecting into the RCS during MODES 4, 5, and 6. To provide overpressure protection, LCO 3.4.12 requires one of the following pressure relief capabilities:
- a. Two RCS relief valves, as follows:
- 2. One PORV with a lift setting within the limits specified in the PTLR and the RHR suction relief valve with a setpoint 436.5 pounds per square inch gauge (psig) and 463.5 psig.
The analyses described in section 5.2.2.4.2 of the WBN UFSAR demonstrate that a single PORV can maintain RCS pressure below limits as per the single failure criteria. The NRC staff notes that either the two PORVs are required in the LCO to account for a single failure of one PORV or one PORV is required with a lift setting within the limits specified in the PTLR and the RHR suction relief valve with a setpoint 436.5 psig and 463.5 psig.
Based on the UFSAR analysis, the current LCO allows only one CCP capable of injecting into the RCS when the COMS is required to be operable. As specified in LCO 3.4.12.b, in place of the PORVs, a depressurized RCS with a vent capable of relieving > 475 gpm water flow may also be used. Both a PORV and the water flow relief have limited overpressure relief capability and may not be capable of maintaining the pressure below the limits if additional mass is injected into the RCS. For the purposes of testing, the licensee is requesting the ability to have one SIP, in addition to the one CCP, capable of injecting into the RCS while the unit is in MODES 5 or 6 provided the pressurizer manway is opened as a vent.
Table 6.3-1 of the WBN UFSAR shows that the maximum flow rate for a CCP and a SIP are 550 gpm and 650 gpm, respectively. To accommodate this additional flow, the COMS would have to be capable of relieving both the mass input of its design basis transient from the CCP in addition to the SIP injection. Rather than performing a reanalysis of the COMS with potential changes to the setpoints for the pressurizer PORVs, the licensee stated that the RCS will instead be vented to the containment atmosphere through the pressurizer manway for the duration that the SIP will be capable of injecting into the RCS.
In the January 4, 2023, response to the NRC staffs RAI, the licensee performed an analysis for WBN to show that the pressurizer manway opening is sufficient to prohibit the overpressurization of the RCS if a SIP was also capable of injecting during the COMS System modes of applicability. The licensee performed calculations for the backpressure that could be developed across the manway using the Westinghouse provided flow resistance method as well as using two methods from the Crane Engineering Division Technical Paper No. 410, Flow of Fluids through Valves, Fittings, and Pipe. The analyses showed that the relief capacity of the pressurizer manway (approximately 16-inch diameter) is more than sufficient to address the combined multiple injection transient of the CCP and SIP.
With the open pressurizer manway having a flow area of approximately 201 in 2, the combined maximum CCP and SIP flow rates vented through the open pressurizer manway would not be capable of inducing a backpressure that approaches the lowest PORV setpoint. The NRC staff finds that the RCS will not be challenged due to overpressure from the additional mass injected by the proposed additional SIP in MODES 5 or 6 at WBN.
3.3 Technical Conclusion
Based on the need to perform testing in MODES 5 or 6, the licensee proposed the addition of a note to SQN TS 3.4.12 and WBN TS 3.4.12, which would allow both a single CCP and a SIP to
be capable of injecting into the RCS provided the RCS is depressurized with the pressurizer manway cover removed. The licensee performed calculations to demonstrate that the relief capacity of the pressurizer manway is large enough to avoid overpressurization of the RCS during the combined multiple injection transient of the CCP and SIP. Based on its review, the NRC staff concludes that the proposed change is acce ptable, and that the TSs, as revised, will continue to meet the requirements of 10 CFR 50.36(c)(2)(i) in that the LCO will continue to be the lowest functional capability of equipment required for safe operation of the facility.
The GDCs applicable to this LAR are GDCs 14, 15, and 31, as identified above in section 2.0. In section 4.1 of the enclosure to the LAR, the licensee discussed that compliance with each of these GDCs is described in section 3.1.2 of the SQN UFSAR and section 3.1.2 of WBN USFAR, respectively. While the proposed change to TS 3.4.12 for either plant is not a design change, the addition of a SIP capable of injecting into the RCS during LTOP/COMS operation has the potential to challenge the RCS pressure boundary; therefore, the NRC staff considered the effect of the proposed change on these GDCs. The staff reviewed the appropriate section of the UFSAR for each plant and determined that the proposed change to the SQN TS 3.4.12 and the WBN TS 3.4.12 does not change how the licensee meets the requirements of the specific GDCs identified above in section 2.0. These GDCs are met primarily by material selection and fabrication techniques.
Therefore, the NRC staff finds that the licensee continues to meet the requirements of GDCs 14, 15, and 31.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendments on March 8, 2023. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, published in the Federal Register on September 6, 2022 (87 FR 54554), and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for catego rical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment(s) will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Tennessee Valley Authority (TVA) letter to NRC, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for WBN Nuclear Plant (WBN-TS-22-03), dated July 27, 2022 (Agencywide Documents Access and Management System Accession No. ML22209A002).
- 2. Tennessee Valley Authority (TVA) Letter to NRC, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2, Request to Revise Technical Specification 3.4.12 (EPID L-2022-LLA-0103),
dated December January 4, 2023 (ML23004A203).
- 3. Perry Buckberg, NRC, to Taylor, Andrew Charles, TVA, Request for Additional Information Related to Changes to Technical Specification 3.4.12 for Sequoyah Nuclear Plant, Units 1 &
2, And Watts Bar Nuclear Plant, Units 1 & 2, Docket Nos. Sequoyah: 50-327, 50-328 and Watts Bar: 50-390, 50-391, EPID: L-2022-LLA-0103 dated December 8, 2022 (ML22343A069).
Issuance of Amendment No. 350 Regarding One-Time Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System, dated October 27, 2021 (ML21298A031).
Principal Contributor: Santosh Bhatt, NRR/DSS
Date: April 5, 2023
ML23072A065 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DSS/SNSB/BC NRR/DSS/STSB/BC NAME PBuckberg RButler DWoodyatt VCusumano DATE 3/20/2023 3/20/2023 3/2/2023 3/16/2023 OFFICE OGC - NLO NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME STurk DWrona PBuckberg DATE 3/20/2023 3/30/2023 04/05/2023