ML26014A150
| ML26014A150 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, Watts Bar  |
| Issue date: | 01/29/2026 |
| From: | Kimberly Green NRC/NRR/DORL/LPL2-2 |
| To: | Erb D Tennessee Valley Authority |
| Green K, NRR/DORL/LPL2-2 | |
| References | |
| EPID L-2025-LLA-0135 | |
| Download: ML26014A150 (0) | |
Text
January 29, 2026 Mr. Delson C. Erb Vice President, OPS Support 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. 375, 370, 180, AND 85 REGARDING ADOPTION OF TSTF-599, REVISION 1 (EPID L-2025-LLA-0135)
Dear Mr. Erb:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 375 to Renewed Facility Operating License No. DPR-77, and Amendment No. 370 to Renewed Facility Operating License No. DPR-79, for the Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah), respectively; and Amendment No. 180 to Facility Operating License No. NPF-90, and Amendment No. 85 to Facility Operating License No. NPF-96, for the Watts Bar Nuclear Plant, Units 1 and 2 (Watts Bar), respectively. These amendments are in response to your application dated August 19, 2025.
The amendments revise Sequoyahs and Watts Bars technical specifications by eliminating the periodic surveillance requirement to verify that all required diesel generators achieve rated frequency and voltage within the specified time period when started simultaneously, consistent with Technical Specifications Task Force (TSTF)-599-A, Revision 1, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators. Additionally, the amendments revise another surveillance requirement to eliminate the reference to the deleted surveillance requirement.
D. Erb A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, 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. 375 to DPR-77
- 2. Amendment No. 370 to DPR-79
- 3. Amendment No. 180 to NPF-90
- 4. Amendment No. 85 to NPF-96
- 5. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 375 Renewed License No. DPR-77
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 19, 2025, 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.
- 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. 375 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David 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: January 29, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.29 13:08:11 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 375 SEQUOYAH NUCLEAR PLANT, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace page 3 of the Renewed Facility Operating License 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 pages of Appendix A, Technical Specifications, with the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.8.1-15 3.8.1-15 3.8.1-16 3.8.2-3 3.8.2-3 (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. 375 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. 375 Renewed License No. DPR-77
AC Sources - Operating 3.8.1 SEQUOYAH - UNIT 1 3.8.1-15 Amendment 334, 341, 375 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.18
NOTES-----------------------------
1.
All DG starts may be preceded by an engine prelube period.
2.
For DGs 1A-A and 1B-B, this Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
a.
De-energization of shutdown boards, b.
Load shedding from shutdown boards, and c.
DG auto-starts from standby condition and:
1.
Energizes permanently connected loads in 10 seconds, 2.
Energizes auto-connected emergency loads through load sequence timers, 3.
Achieves steady state voltage 6800 V and 7260 V, 4.
Achieves steady state frequency 59.8 Hz and 60.2 Hz, and 5.
Supplies permanently connected and auto-connected emergency loads for 5 minutes.
In accordance with the Surveillance Frequency Control Program
AC Sources - Shutdown 3.8.2 SEQUOYAH - UNIT 1 3.8.2-3 Amendment 334, 369, 375 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.9 through SR 3.8.1.11, and SR 3.8.1.13 through SR 3.8.1.17.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources - Operating,"
except SR 3.8.1.12 and SR 3.8.1.18, are applicable.
In accordance with applicable SRs
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 370 Renewed License No. DPR-79
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 19, 2025, 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 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.
- 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-79 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 370 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David 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: January 29, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.29 13:09:17 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 370 SEQUOYAH NUCLEAR PLANT, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace page 3 of the Renewed Facility Operating License 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 pages of Appendix A, Technical Specifications, with the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.8.1-15 3.8.1-15 3.8.1-16 3.8.2-3 3.8.2-3 (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 Commission's 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. 370 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 Authority's 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 TVA's Final Safety Analysis Report as amended as being essential; Amendment No. 370 Renewed License No. DPR-79
AC Sources - Operating 3.8.1 SEQUOYAH - UNIT 2 3.8.1-15 Amendment 327, 334, 370 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.18
NOTES-----------------------------
1.
All DG starts may be preceded by an engine prelube period.
2.
For DGs 2A-A and 2B-B, this Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
a.
De-energization of shutdown boards, b.
Load shedding from shutdown boards, and c.
DG auto-starts from standby condition and:
1.
Energizes permanently connected loads in 10 seconds, 2.
Energizes auto-connected emergency loads through load sequence timers, 3.
Achieves steady state voltage 6800 V and 7260 V, 4.
Achieves steady state frequency 59.8 Hz and 60.2 Hz, and 5.
Supplies permanently connected and auto-connected emergency loads for 5 minutes.
In accordance with the Surveillance Frequency Control Program
AC Sources - Shutdown 3.8.2 SEQUOYAH - UNIT 2 3.8.2-3 Amendment 327, 363, 370 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.9 through SR 3.8.1.11, and SR 3.8.1.13 through SR 3.8.1.17.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources - Operating,"
except SR 3.8.1.12 and SR 3.8.1.18, are applicable.
In accordance with applicable SRs
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 180 License No. NPF-90
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated August 19, 2025, 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 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.
- 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. 180 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 its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David 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: January 29, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.29 13:09:53 -05'00'
ATTACHMENT TO AMENDMENT NO. 180 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Facility Operating License No. NPF-90 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 pages of Appendix A, Technical Specifications, with the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3.8-15 3.8-15 3.8-16 3.8-16 3.8-20 3.8-20
Facility License No. NPF-90 Amendment No. 180 (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. 180 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.
AC Sources-Operating 3.8.1 Watts Bar-Unit 1 3.8-15 Amendment 89, 102, 110, 132,180 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.19
NOTE--------------------------------
For DGs 1A-A and 1B-B, this Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
a.
De-energization of emergency buses; b.
Load shedding from emergency buses; c.
DG auto-starts from standby condition and:
1.
energizes permanently connected loads in 10 seconds, 2.
energizes auto-connected emergency loads through load sequencer, 3.
achieves steady state voltage:
6800 V and 7260 V, 4.
achieves steady state frequency 59.8 Hz and 60.1 Hz, and 5.
supplies permanently connected and auto-connected emergency loads for 5 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.20 Verify during idle operation that any automatic or emergency start signal disables the idle start circuitry and commands the engine to full speed.
In accordance with the Surveillance Frequency Control Program
AC Sources-Operating 3.8.1 Watts Bar-Unit 1 3.8-16 Amendment 102, 103, 132, 136,180 THIS PAGE INTENTIONALLY LEFT BLANK
AC Sources-Shutdown 3.8.2 Watts Bar-Unit 1 3.8-20 Amendment 180 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE-----------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.6, SR 3.8.1.9 through SR 3.8.1.16, SR 3.8.1.18 and SR 3.8.1.19.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources-Operating,"
except SR 3.8.1.8 and SR 3.8.1.17, are applicable.
In accordance with applicable SRs
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. NPF-96
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated August 19, 2025, 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 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.
- 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. 85 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 its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David 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: January 29, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.29 13:10:21 -05'00'
ATTACHMENT TO AMENDMENT NO. 85 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 pages of Appendix A, Technical Specifications, with the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3.8-13 3.8-13 3.8-17 3.8-17 Unit 2 Facility Operating License No. NPF-96 Amendment No. 85 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. 85 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:
AC Sources - Operating 3.8.1 Watts Bar - Unit 2 3.8-13 Amendment 36, 41, 80, 85 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.19
NOTE------------------------------
For DGs 2A-A and 2B-B, this Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
a.
De-energization of emergency buses; b.
Load shedding from emergency buses; and c.
DG auto-starts from standby condition and:
1.
energizes permanently connected loads in 10 seconds, 2.
energizes auto-connected emergency loads through load sequencer, 3.
achieves steady state voltage:
6800 V and 7260 V, 4.
achieves steady state frequency 59.8 Hz and 60.1 Hz, and 5.
supplies permanently connected and auto-connected emergency loads for 5 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.20 Verify during idle operation that any automatic or emergency start signal disables the idle start circuitry and commands the engine to full speed.
In accordance with the Surveillance Frequency Control Program
AC Sources - Shutdown 3.8.2 Watts Bar - Unit 2 3.8-17 Amendment 85 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE------------------------------
The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.6, SR 3.8.1.9 through SR 3.8.1.16, SR 3.8.1.18 and SR 3.8.1.19.
For AC sources required to be OPERABLE, the SRs of Specification 3.8.1, "AC Sources-Operating,"
except SR 3.8.1.8 and SR 3.8.1.17, are applicable.
In accordance with applicable SRs
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 375 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-77 AMENDMENT NO. 370 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-79 AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-90 AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. NPF-96 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391 TENNESSEE VALLEY AUTHORITY
1.0 INTRODUCTION
By application dated August 19, 2025 (Agencywide Documents Access and Management System Accession Nos. ML25231A300), the Tennessee Valley Authority (TVA or the licensee) requested changes to the technical specifications (TSs) for Sequoyah Nuclear Plant, Units 1 and 2 (SQN or Sequoyah), and Watts Bar Nuclear Plant, Units 1 and 2 (WBN or Watts Bar).
The proposed changes would revise the TSs for each facility based on Technical Specifications Task Force (TSTF) Traveler TSTF-599, Revision 1, Eliminate Periodic Surveillance Test of Simultaneous Start of Redundant Diesel Generators (hereafter referred to as TSTF-599)
(ML25093A204), and the associated U.S. Nuclear Regulatory Commission (NRC or the Commission) staff final safety evaluation (SE) for Traveler TSTF-599 (ML25119A288).
Specifically, the proposed change would delete a surveillance requirement (SR) in TS 3.8.1, AC [alternating current] Sources - Operating, to verify that diesel generators (DG) achieve a specific frequency and voltage within a specified time period when started simultaneously. An associated editorial change was also proposed eliminating reference to the deleted SR found in another TS SR.
2.0 REGULATORY EVALUATION
2.1
System Description
The Class 1E AC electrical power distribution systems onsite standby power sources provide independence and redundancy to ensure an available source of power to the engineered safety feature (ESF) systems when the offsite or preferred power sources are unavailable. Specifically, the onsite standby power source consists of emergency DGs to power ESF buses. A safety injection (SI) signal or a loss of offsite power (i.e., an ESF bus degraded voltage or undervoltage) signal will automatically start the DGs. If DGs start due to a loss of offsite power signal (independent of or coincident with an SI signal), the DGs will automatically tie to their respective ESF buses. If the DGs receive an SI signal alone, they will start and operate in standby mode (i.e., without tying to the ESF buses). Following the trip of offsite power, nonpermanent loads are stripped from the ESF buses. When the DGs are tied to the ESF buses, emergency loads are then sequentially connected to their respective ESF buses by the automatic load sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading the DGs by automatic load application.
In the event of a loss of preferred (offsite) power, the ESF electrical loads are automatically connected to the DGs in sufficient time to provide for safe reactor shutdown and to mitigate the consequences of a design basis accident, such as a loss-of-coolant accident.
2.2 Requested Changes The licensee proposed deleting SRs 3.8.1.19 (Sequoyah) and 3.8.1.21 (Watts Bar) that require simultaneous starting of the DGs.
The current requirement for Sequoyah states:
SR 3.8.1.19
NOTE---------------------------------
All DG starts may be preceded by an engine prelube period.
Verify when started simultaneously from standby condition, each DG achieves, in 10 seconds, voltage 6800 V and frequency 58.8 Hz.
The current requirement for Watts Bar states:
SR 3.8.1.21 Verify when started simultaneously from standby condition, each DG achieves, in 10 seconds, voltage 6800 V and frequency 58.8 Hz.
Verify after DG fast start from standby conditions that the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60.1 Hz.
In addition to the DG simultaneous start test, TSTF-599 also deletes from Standard TS (STS) any references to STS SR 3.8.1.20 located in other STS. Likewise, the licensee requested to delete from TS 3.8.2, AC Sources - Shutdown, reference to SR 3.8.1.19 and SR 3.8.1.21, for Sequoyah and Watts Bar, respectively. The reference to the deleted SRs would be deleted from each units SR 3.8.2.1, which lists the SRs required for AC sources during shutdown.
Proposed Changes to Technical Specification Bases Consistent with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(a)(1), the licensee submitted corresponding changes to the TS Bases, for information only, that provide the reasons for the proposed TS changes. The regulation at 10 CFR 50.36(a)(1) states that a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TS. The licensee shall make changes to the plant TS Bases in accordance with the TS Bases Control Program, found at TS 5.5.12 for Sequoyah and at TS 5.6 for Watts Bar.
2.3 Applicable Regulatory Requirements and Guidance The regulation in 10 CFR 50.36, Technical specifications, provides the regulatory requirements for the content of the TS. It requires, in part, that a summary statement of the bases for such specifications shall be included by applicants for a license authorizing operation of a production or utilization facility. Specifically, the regulation in 10 CFR 50.36(c)(3),
Surveillance requirements, states that [s]urveillance requirements are requirements related 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.
3.0 TECHNICAL EVALUATION
The NRC staff compared the licensees proposed TS changes in section 2.2 of this SE against the changes approved in TSTF-599. The NRC staff finds that the licensees proposed changes to the Sequoyah and Watts Bar TSs in section 2.2 of this SE are consistent with those found acceptable in TSTF-599.
In the NRC SE of TSTF-599, the NRC staff considered common-cause failure a very low likelihood event and, therefore, concluded that the performance of STS SR 3.8.1.20 does not enhance safety over the increased risk of equipment inoperability. Additionally, in recent decades, industry operating experience during loss of offsite power events has demonstrated consistent performance of the DG simultaneous start function. Therefore, as discussed in section 4.0 of the NRC staffs SE of TSTF-599, the NRC staff found the proposed deletion of STS SR 3.8.1.20, along with the associated changes to STS TS 3.8.2 were acceptable because the TS would continue to meet 10 CFR 50.36(c)(3) since the remaining STS 3.8.1 DG SRs provide assurance that the necessary quality of systems and components are maintained. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Sequoyah and Watt Bar TS in section 1.2 of this SE continue to meet the requirements of 10 CFR 50.36(c)(3).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendment on January 12, 2026. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration published in the Federal Register on November 25, 2025 (90 FR 53396). One public comment was received; however, it was unrelated to this request. Accordingly, the amendment meets 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 bef prepared in connection with the issuance of the amendment.
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: K. West, NRR Date: January 29, 2026
ML26014A150 NRR-058 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DSS/STSB/BC NAME KGreen ABaxter SMehta DATE 01/13/2026 01/21/2026 12/19/2025 OFFICE NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME DWrona KGreen DATE 01/29/2026 01/29/2026