ML25051A210
| ML25051A210 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, Watts Bar  |
| Issue date: | 03/31/2025 |
| From: | Kimberly Green NRC/NRR/DORL/LPL2-2 |
| To: | Erb D Tennessee Valley Authority |
| Buckberg, P | |
| References | |
| EPID L-2023-LLA-0175 | |
| Download: ML25051A210 (1) | |
Text
March 31, 2025 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; AND WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 371, 365, 173 AND 78 REGARDING REVISION TO TECHNICAL SPECIFICATION TABLE 3.3.2-1, FUNCTION 5 (EPID L-2023-LLA-0175)
Dear Mr. Erb:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 371 and 365 to Renewed Facility Operating License Nos. DPR-77 and DPR-79, for the Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2, respectively, and Amendment Nos. 173 and 78 to Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, respectively. These amendments are in response to your application dated December 18, 2023, as supplemented by letters dated August 19, 2024, November 27, 2024, and February 12, 2025.
The amendments revise Functions 5a and 5b in the Sequoyah and Watts Bar Technical Specification (TS) Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, by adding a note related to the turbine trip function. The amendments also revise note (f) in the Watts Bar, Unit 1, and note (h) in Watts Bar, Unit 2, TS Table 3.3.2-1.
A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, 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, 50-391
Enclosures:
- 1. Amendment No. 371 to DPR-77
- 2. Amendment No. 365 to DPR-79
- 3. Amendment No. 173 to NPF-90
- 4. Amendment No. 78 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. 371 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 December 18, 2023, as supplemented by letters dated August 19, 2024, November 27, 2024, and February 12, 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. 371, 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: March 31, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.03.31 15:36:36 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 371 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 the 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 3.3.2-14 3.3.2-14 3.3.2-17 3.3.2-17
(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. 371 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. 371 Renewed License No. DPR-77
ESFAS Instrumentation 3.3.2 SEQUOYAH - UNIT 1 3.3.2-14 Amendment 334, 371 Table 3.3.2-1 (page 4 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 5.
Turbine Trip and Feedwater Isolation a.
Automatic Actuation Logic and Actuation Relays 1(j), 2(i)(j),3(i)(j) 2 trains H
SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.5 NA NA b.
SG Water Level -
High High (P-14) 1(j),2(i)(j),3(i)(j) 3 per SG D
SR 3.3.2.1 SR 3.3.2.4(b)(c)
SR 3.3.2.8(b)(c)
SR 3.3.2.9 81.7%
81%
c.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
6.
Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains H
SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.5 NA NA (b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.
(i)
Except when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve.
(j)
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
ESFAS Instrumentation 3.3.2 SEQUOYAH - UNIT 1 3.3.2-17 Amendment 334, 358, 371 Table 3.3.2-1 (page 7 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 6.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
d.
Loss of Offsite Power (1) Voltage Sensors 1,2,3 3 per shutdown board(k)
L,M SR 3.3.2.6 SR 3.3.2.8(b)(c)
SR 3.3.2.9 Refer to Function 1 of Table 3.3.5-1 for setpoints and allowable values.
(2) Load Shed Timer 1,2,3 1 per shutdown board(k)
M SR 3.3.2.8(b)(c)
SR 3.3.2.9 Refer to Function 1 of Table 3.3.5-1 for setpoints and allowable values.
e.
Trip of all Main Feedwater Pumps 1,2(l) 1 per pump N
SR 3.3.2.7 SR 3.3.2.9 NA NA f.
Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low 1,2,3 3 per pump P
SR 3.3.2.8(b)(c) 2.44 psig (motor driven pump) 12 psig (turbine driven pump) 3.21 psig (motor driven pump) 13.9 psig (turbine driven pump)
(b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.
(k)
Unit 1 shutdown boards only.
(l)
When one or more Main Feedwater Pump(s) are supplying feedwater to steam generators.
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 365 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 December 18, 2023, as supplemented by letters dated August 19, 2024, November 27, 2024, and February 12, 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-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. 365, 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: March 31, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.03.31 15:37:05 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 365 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 the 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 3.3.2-14 3.3.2-14 3.3.2-17 3.3.2-17 (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. 365 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. 365 Renewed License No. DPR-79
ESFAS Instrumentation 3.3.2 SEQUOYAH - UNIT 2 3.3.2-14 Amendment 327, 365 Table 3.3.2-1 (page 4 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 5.
Turbine Trip and Feedwater Isolation a.
Automatic Actuation Logic and Actuation Relays 1(j), 2(i)(j),3(i)(j) 2 trains H
SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.5 NA NA b.
SG Water Level -
High High (P-14) 1(j),2(i)(j),3(i)(j) 3 per SG D
SR 3.3.2.1 SR 3.3.2.4(b)(c)
SR 3.3.2.8(b)(c)
SR 3.3.2.9 81.7%
81%
c.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
6.
Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains H
SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.5 NA NA (b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.
(i)
Except when all MFIVs, MFRVs, and MFRV bypass valves are closed or isolated by a closed manual valve.
(j)
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
ESFAS Instrumentation 3.3.2 SEQUOYAH - UNIT 2 3.3.2-17 Amendment 327, 352, 365 Table 3.3.2-1 (page 7 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 6.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
d.
Loss of Offsite Power (1) Voltage Sensors 1,2,3 3 per shutdown board(k)
L,M SR 3.3.2.6 SR 3.3.2.8(b)(c)
SR 3.3.2.9 Refer to Function 1 of Table 3.3.5-1 for setpoints and allowable values.
(2) Load Shed Timer 1,2,3 1 per shutdown board(k)
M SR 3.3.2.8(b)(c)
SR 3.3.2.9 Refer to Function 1 of Table 3.3.5-1 for setpoints and allowable values.
e.
Trip of all Main Feedwater Pumps 1,2(l) 1 per pump N
SR 3.3.2.7 SR 3.3.2.9 NA NA f.
Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low 1,2,3 3 per pump P
SR 3.3.2.8(b)(c) 2.44 psig (motor driven pump) 12 psig (turbine driven pump) 3.21 psig (motor driven pump) 13.9 psig (turbine driven pump)
(b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and as-left tolerances are specified in UFSAR, Section 7.1.2.
(k)
Unit 2 shutdown boards only.
(l)
When one or more Main Feedwater Pump(s) are supplying feedwater to steam generators.
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 173 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, the licensee) dated December 18, 2023, as supplemented by letters dated August 19, 2024, November 27, 2024, and February 12, 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 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. 173 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 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: March 31, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.03.31 15:37:37 -04'00'
ATTACHMENT TO AMENDMENT NO. 173 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 the 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 3.3-36 3.3-36 3.3-38 3.3-38
Facility License No. NPF-90 Amendment No. 173 (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. 173 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.
ESFAS Instrumentation 3.3.2 Watts Bar-Unit 1 3.3-36 Amendment 23, 173 Table 3.3.2-1 (page 3 of 7)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 4.
Steam Line Isolation (continued) c.
Containment 1, 2(c), 3(c) 4 E
SR 3.3.2.1 2.9 psig 2.8 psig Pressure-SR 3.3.2.4 High High SR 3.3.2.9 SR 3.3.2.10 d.
Steam Line Pressure (1)
Low 1, 2(c), 3(a) (c) 3 per steam D
SR 3.3.2.1 666.6(b) psig 675(b) psig line SR 3.3.2.4 SR 3.3.2.9 SR.3.2.10 (2)
Negative 3(d) (c) 3 per steam D
SR 3.3.2.1 108.5(e) psi 100(e) psi Rate-High line SR 3.3.2.4 SR 3.3.2.9 SR 3.3.2.10 5.
Turbine Trip and Feedwater Isolation a.
Automatic 1(i), 2(f)(i), 3(f)(i) 2 trains H
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays b.
SG Water 1(i), 2(f)(i), 3(f)(i) 3 per SG I
SR 3.3.2.1 83.1%
82.4%
Level-High SR 3.3.2.4 High(P-14)
SR 3.3.2.9 SR 3.3.2.10 (h) c.
Safety Refer to Function 1 (Safety Injection) for all initiation Injection functions and requirements.
d.
North MSV Vault 1, 2(f), (g) 3/vault O
SR 3.3.2.6 5.31 inches 4 inches Room Water Room SR 3.3.2.9 Level - High e.
South MSV Vault 1, 2(f), (g) 3/vault O
SR 3.3.2.6 4.56 inches 4 inches Room Water Room SR 3.3.2.9 Level - High (continued)
(a)
Above the P-11 (Pressurizer Pressure) interlock.
(b)
Time constants used in the lead/lag controller are t1 50 seconds and t2 5 seconds.
(c)
Except when all MSIVs are closed and de-activated.
(d)
Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked.
(e)
Time constants utilized in the rate/lag controller are t3 and t4 50 seconds.
(f)
Except when all MFIVs, MFRVs, and associated bypass valves are closed or isolated by a closed manual valve.
(g)
MODE 2 if Turbine Driven Main Feed Pumps are operating.
(h)
For the time period between February 23, 2000, and prior to turbine restart (following the next time the turbine is removed from service), the response time test requirement of SR 3.3.2.10 is not applicable for 1-FSV-47-027.
(i)
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
ESFAS Instrumentation 3.3.2 Watts Bar-Unit 1 3.3-38 Amendment 1, 75, 104, 148, 154,173 Table 3.3.2-1 (page 5 of 7)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 6.
Auxiliary Feedwater (continued) c.
Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Injection d.
Loss of Offsite 1, 2,3 4 per bus F
Refer to Function 4 of Table 3.3.5-1 for Power SRs and Allowable Values e.
Trip of all Main Feedwater Pumps (1)
Turbine Driven Main Feedwater Pumps 1( j ), 2 1 per pump J
SR 3.3.2.8 SR 3.3.2.9 SR 3.3.2.10 43.3 psig 50 psig and (2)
Standby Main Feedwater Pump 1, 2 1
P SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 NA NA f.
Auxiliary Feedwater Pumps Train A and B Suction Transfer on Suction Pressure - Low 1, 2, 3, 4(k) 3 B
SR 3.3.2.6 SR 3.3.2.9 SR 3.3.2.10 A) 0.5 psig A) 1.2 psig B) 1.33 psig B) 2.0 psig 7.
Automatic Switchover to Containment Sump a.
Automatic 1, 2, 3, 4 2 trains C
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (continued)
( j )
Entry into Condition J may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing a Turbine Driven Main Feedwater (TDMFW) Pump in service or removing a TDMFW pump from service.
( k )
When steam generators are relied on for heat removal.
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 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, the licensee) dated December 18, 2023, as supplemented by letters dated August 19, 2024, November 27, 2024, and February 12, 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 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. 78 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 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: March 31, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.03.31 15:38:02 -04'00'
ATTACHMENT TO AMENDMENT NO. 78 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 the 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 3.3-37 3.3-37 3.3-39 3.3-39 Unit 2 Facility Operating License No. NPF-96 Amendment No. 78 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. 78 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:
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
Watts Bar - Unit 2 3.3-37 Amendment 55, 78 Table 3.3.2-1 (page 4 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 5.
Turbine Trip and Feedwater Isolation a.
Automatic Actuation Logic and Actuation Relays 1(j), 2 (h)(j), 3 (h)(j) 2 trains H
SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5 b.
SG Water Level -
High High (P-14) 1(j), 2 (h)(j), 3 (h)(j) 3 per SG I
SR 3.3.2.1 83.1%
82.4%
SR 3.3.2.4 (b) (c)
SR 3.3.2.9 (b) (c)
SR 3.3.2.10 c.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
d.
North MSV Vault Room Water Level - High 1, 2 (h)(i) 3 per vault room O
SR 3.3.2.6 5.31 inches 4 inches SR 3.3.2.9 e.
South MSV Vault Room Water Level - High 1, 2 (h)(i) 3 per vault room O
SR 3.3.2.6 4.56 inches 4 inches SR 3.3.2.9 (continued)
(b)
If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.
(h)
Except when all MFIVs, MFRVs, and associated bypass valves are closed or isolated by a closed manual valve.
(i)
MODE 2 if Turbine Driven Main Feed Pumps are operating.
(j)
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
Watts Bar - Unit 2 3.3-39 Amendment 55, 78 Table 3.3.2-1 (page 6 of 9)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT 6.
Auxiliary Feedwater (continued) d.
Loss of Offsite Power 1, 2, 3 4 per bus F
Refer to Function 4 of Table 3.3.5-1 for SRs and Allowable Values. Notes (b) and (c) are applicable to SR 3.3.5.2 for this function.
e.
Trip of all Main Feedwater Pumps (1)
Turbine Driven Main Feedwater Pumps 1 (k), 2 1 per pump J
SR 3.3.2.8 (b)(c) 43.3 psig 50 psig SR 3.3.2.9 (b)(c)
SR 3.3.2.10 and (2) Standby Main Feedwater Pumps 1, 2 1
P SR 3.3.2.8 NA NA SR 3.3.2.10 SR 3.3.2.12 f.
Auxiliary Feedwater Pumps Train A and B Suction Transfer on Suction Pressure - Low 1, 2, 3, 4(l) 3 B
SR 3.3.2.6 A) 0.5 psig A) 1.2 psig SR 3.3.2.9 (b) (c)
SR 3.3.2.10 B) 1.33 psig B) 2.0 psig (continued)
(b)
If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.
(k)
Entry into Condition J may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing a Turbine Driven Main Feedwater (TDMFW) Pump in service or removing a TDMFW pumps from service.
(l)
When steam generators are being relied on for heat removal.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 371 TO RENEWED FACILITY OPERATING LICENSE DPR-77 AMENDMENT NO. 365 TO RENEWED FACILITY OPERATING LICENSE DPR-79 AMENDMENT NO. 173 TO FACILITY OPERATING LICENSE NPF-90 AMENDMENT NO. 78 TO FACILITY OPERATING LICENSE 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 letter to the U.S. Nuclear Regulatory Commission (NRC or Commission) dated December 18, 2023 (Agencywide Documents Access and Management System Accession No. ML23352A298), as supplemented by letters dated August 19, 2024 (ML24232A071), November 27, 2024 (ML24332A140), and February 12, 2025 (ML25043A280), the Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2, and the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2. Specifically, the proposed amendments would revise Sequoyah and Watts Bar Technical Specification (TS) Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, by adding a note to Functions 5a and 5b related to the turbine trip function.
The amendments for Watts Bar, Units 1 and 2, would also revise note (f) of Watts Bar, Unit 1, TS Table 3.3.2-1 and note (h) of Watts Bar, Unit 2, TS Table 3.3.2-1. Additionally, the proposed amendments would re-letter the notes in Sequoyah, Units 1 and 2, TS Table 3.3.2-1 due to the addition of the new note, and delete note (j) and note (k) from Watts Bar, Units 1 and 2, respectively, as well as re-letter the remaining notes accordingly.
The supplemental \
letter dated August 19, 2024, corrected TVAs response to Question 1 in the no signification hazards consideration (NSHC), and corrected the reference to note (i) of Sequoyah, Unit 2, TS Table 3.3.2-1, Functions 5a and 5b. The supplemental letters dated November 27, 2024, and February 12, 2025, 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 proposed NSHC determination as published in the Federal Register on October 1, 2024 (89 FR 79971), which considered the licensees corrected response to Question 1 of the NSHC.
2.0 REGULATORY EVALUATION
2.1 System Description The Sequoyah and Watts Bar Updated Final Safety Analysis Reports (UFSARs) (ML23349A014 and ML23346A225, respectively) describe the Engineered Safety Features Actuation System (ESFAS) as a functionally defined system that senses selected plant parameters, determines whether predetermined safety limits are being exceeded and, if they are, combines the signals into logic matrices sensitive to combinations indicative of primary or secondary system boundary ruptures (Class III or IV faults). Once the required logic combination is completed, the system sends actuation signals to those ESFAS components whose aggregate function best serves the requirements of the accident.
Two of the functions that rely on the ESFAS for initiation are the reactor trip, provided one has not already been generated by the reactor trip system, and main feedwater (MFW) isolation as required to prevent or mitigate the effect of excessive cooldown and the effects of main steam valve vault flooding due to an MFW line break. The latter is accomplished by the Turbine Trip and Feedwater Isolation signals.
The Sequoyah and Watts Bar UFSARs (section 7.2.1.1.2) state that the reactor trip on a turbine trip is actuated by emergency trip header pressure signals or by closed signals from all four turbine steam stop (throttle) valves. A turbine trip causes a direct reactor trip above P-9 set point. Section 7.2.1.1.3 states that the P-9 interlock blocks a reactor trip on a turbine trip when the plant is below approximately 50 percent of full power. Below the P-9 setpoint, the reactor will not trip directly from a turbine trip signal but will allow the reactor control system, utilizing steam dump to the condenser as an artificial load, to bring the reactor to zero power.
According to the Sequoyah UFSAR section 7.2.1.1.2, the reactor trip on turbine trip is an anticipatory trip input signal to the reactor protection system. This trip is anticipatory in that it is not assumed to occur in any of the Chapter 15 accident analyses. Watts Bar UFSAR section 7.2.1.1.2 states that the reactor trip on turbine trip provides additional protection and conservatism beyond that required for the health and safety of the public. This trip is included as part of good engineering practice and prudent design. No credit is taken in any of the accident analyses (Chapter 15) for this trip.
Section 10.2 of the UFSARs state that the purpose of the turbine-generator is to use steam supplied by the reactor in the conversion of thermal energy to electrical energy, and to provide extraction steam for feedwater heating. Turbine valves control the admission of steam to the high-and low-pressure turbines. The Watts Bar UFSAR states that four main stop (throttle) valves supply steam to the high-pressure turbine through the governor valves. The stop (throttle) valves are generally fully open or fully closed, except for a brief period during startup when the main stop (throttle) valves are used for initial speed control. The four control (governor) valves are positioned in any intermediate position to proportionally regulate the steam flow to the required amount.
The turbine is protected by a turbine overspeed protection system and a turbine trip system.
One of the protective trips that will automatically trip the turbine due to turbine mechanical abnormalities includes the steam generator high-high level trip (i.e., TS Table 3.3.2-1, Function 5.b).
The Watts Bar TS Bases for Table 3.3.2-1, Function 5.b (shown in Enclosure 4 to the LAR) states that the Turbine Trip and Feedwater Isolation-Steam Generator Water Level - High High (P-14) Function is actuated when the level in any steam generator (SG) exceeds the high high setpoint, and performs the following functions:
Trips the main turbine, Trips the MFW pumps, Initiates feedwater isolation (FWI), and Shuts the MFW regulating valves (MFRVs) and the MFRV bypass valves.
Section 10.2.2 of the Sequoyah and Watts Bar UFSARs describe the turbine trip system as being equipped with solenoid-operated trip devices, which provide the means to initiate direct tripping of the turbine upon receipt of appropriate electrical signals. The turbine can also be tripped manually on detection of various conditions. When a turbine trip is initiated, the extraction system nonreturn valves are tripped closed either by means of a pilot dump valve connected to the turbine trip system, on electrical trip signal generated by the turbine trip, or by both means. Section 10.2.2 of the Sequoyah UFSAR states that the electrohydraulic control system, composed of solid-state electronic devices coupled through suitable electrohydraulic transducers to a high-pressure hydraulic fluid system, provides control of the main stop, governing, intercept, and reheat stop valves of the turbine. Section 10.2.4 of the Watts Bar UFSAR states that the main steam stop (throttle) and control (governor) valves, which supply steam to the high-pressure turbine, and reheat stop and interceptor valves, which supply steam to the low-pressure turbines, are capable of fast closure upon receipt of a closure signal. Each of the four throttle valves is arranged with a paired governor valve and each of the six reheat stop valves is arranged in series with an interceptor valve.
2.2 Requested Changes As described in LAR, section 2.3, as supplemented, the licensee requested the following changes to Sequoyah, Units 1 and 2, TS Table 3.3.2-1:
Addition of note (j) to Functions 5.a and 5.b, which states:
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
Re-lettering of existing note (j) to note (k) for Functions 6.d.(1) and (2) and from note (k) to note (l) for Function 6.e.
The licensee requested the following changes to Watts Bar, Unit 1, TS Table 3.3.2-1:
Addition of note (i) to Functions 5.a and 5.b, which states:
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
Deletion of existing note (j), which says Deleted.
Re-lettering of existing note (i) to note (j) for Function 6.e.(1)
Revision to existing note (f) for Functions 5.a and 5.b, as follows:
Except when all MFIVs, MFRVs, and associated bypass valves are closed or isolated by a closed manual valve.
The licensee requested the following changes to Watts Bar, Unit 2, TS Table 3.3.2-1:
Addition of note (j) to Functions 5.a and 5.b, which states:
Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
Deletion of existing note (k), which says Deleted.
Re-lettering of existing note (j) to note (k) for Function 6.e.(1).
Re-lettering of existing note (m) to note (l) for Function 6.f.
Revision to existing note (h) for Functions 5.a and 5.b, as follows:
Except when all MFIVs, MFRVs, and associated bypass valves are closed or isolated by a closed manual valve.
The NRC staff notes that the licensee did not propose any changes to the ALLOWABLE VALUE and NOMINAL TRIP SETPOINT for TS Table 3.3.2-1, Functions 5.a and 5.b for Sequoyah, Units 1 and 2, and Watts Bar, Units 1 and 2.
2.3 Regulatory Requirements and Guidance Under Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of a license wishes to amend the license, including TSs in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public, and that the applicant will comply with the Commissions regulations.
Appendix A, General Design Criteria [GDC] for Nuclear Power Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes the minimum requirements for the principal design criteria for water-cooled nuclear power plants. The principal design criteria establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.
According to section 3.1.2 of the Sequoyah UFSAR, and section 3.1.1 of the Watts Bar Nuclear Plant Dual-Unit UFSAR, the plants were designed to meet the intent of the Proposed General Design Criteria for Nuclear Power Plant Construction Permits, published in July 1967. The Sequoyah construction permits were issued in May 1970, and the Watts Bar construction permits were issued in January 1973. The Sequoyah and Watts Bar plants, in general, meet the intent of the NRC GDC published as Appendix A to 10 CFR Part 50 in July 1971, as discussed in UFSAR section 3.1.2.
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36, Technical specifications, which require, in pertinent part, that the TSs include: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls.
Section 50.36(c)(2)(i) of 10 CFR requires that TSs must include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. That provision also requires that when an LCO of a nuclear reactor is not met, the licensee must shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water-Reactor]
Edition (SRP), Chapter 16.0, Technical Specifications, Revision 3, dated March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications for each of the LWR nuclear designs.
Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-14311, as modified by NRC-approved travelers.
3.0 TECHNICAL EVALUATION
The NRC staff evaluated the licensees application, as supplemented, to determine whether the proposed changes are consistent with the regulations, guidance, and plant-specific design and licensing basis information discussed in section 2.3 of this safety evaluation.
The NRC staff reviewed the acceptability of the proposed changes to the TSs by evaluating whether, among other things, the changes provide reasonable assurance of public health and safety. The NRC staff also verified that the proposed changes to the TSs assure that the LCOs will be met.
3.1 Evaluation of Proposed Addition of Note Regarding Turbine Trip Function The licensee has proposed the addition of a note to Sequoyah and Watts Bar TS Table 3.3.2-1 for Functions 5.a and 5.b. The proposed note would state that the turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening.
As explained in the LAR, a turbine trip signal into the digital electric hydraulics system must be present for the turbine stop and governor valves to be closed and incapable of opening. While the turbine is in the tripped state, the trip block solenoid valves will de-energize and remain 1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21259A155 and ML21259A159, respectively).
open removing hydraulic fluid pressure needed for valve movement. The trip block solenoid valves will energize only when all turbine trips are clear and the turbine is latched. These actions will allow system pressure to build therefore enabling valve movement when demand is present.
As described in section 2.1 above, upon receipt of a closure signal, all four stop valves, all four governor valves, and the reheat stop and interceptor valves will close. Closure of all four turbine stop (throttle valves) or their paired governor valves will prevent entry of steam into the high-pressure turbine, thereby accomplishing the purpose of the turbine trip.
The NRC staff evaluated the proposed addition of note (j) to Sequoyah, Units 1 and 2, TS Table 3.3.2-1, note (i) to Watts Bar, Unit 1, TS Table 3.3.2-1, and note (j) to Watts Bar, Unit 2, TS Table 3.3.2-1, regarding the turbine trip function.
The current Sequoyah and Watts Bar TS 3.3.2 require that the ESFAS instrumentation for each function in Table 3.3.2-1 shall be OPERABLE. Sequoyah and Watts Bar TS Table 3.3.2-1, Function 5, require that the automatic Turbine Trip and Feedwater Isolation function (i.e.,
Function 5.a) and SG Water Level - High High (P-14) function (i.e., Function 5.b) be operable in Modes 1, 2, and 3, except as noted by note (i) for Sequoyah, Units 1 and 2, note (f) for Watts Bar, Unit 1, and note (h) for Watts Bar, Unit 2. The turbine trip function requires the four main turbine stop valves to be capable of closing within the time limit prescribed in Sequoyah UFSAR Table 7.3.1-4, Engineered Safety Features Response Times, and the Watts Bar, Units 1 and 2, Technical Requirements Manuals Table 3.3.2-1, Engineered Safety Features Response Times (ML073620391). When one train of the automatic function (i.e., Function 5.a) is inoperable, Condition H is entered, and the Required Actions and Completion Times shall be met. Similarly, if less than three channels of the SG Water Level - High High (P-14) (i.e.,
Function 5.b) are inoperable, then Condition D is entered, and the Required Actions and Completion Times shall be met.
In the LAR, the licensee noted that Sequoyah and Watts Bar TS 3.3.2 do not provide any specific condition/action for the turbine stop valves. Therefore, if one or more turbine stop valves is inoperable, then both trains of the turbine trip function must be declared inoperable. When two trains are inoperable, entry into LCO 3.0.3 is required. LCO 3.0.3 states that, when an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable.
The primary functions of the Turbine Trip and Feedwater Isolation (Table 3.3.2-1, Functions 5.a and 5.b) signals are to prevent damage to the turbine due to water in the steam lines, and to stop the excessive flow of feedwater into the SGs. These functions are necessary to mitigate the effects of a high water level in the SGs which could result in carryover of water into the steam lines and excessive cooldown of the primary system. The SG high water level is due to excessive feedwater flow. The SG Water Level - High High (P-14) function (i.e., Function 5.b) is actuated when the level in any SG exceeds the high high setpoint, and performs the following functions: trips the main turbine, trips the MFW pumps; initiates feedwater isolation; and shuts the MFW regulating valves and the MFRV bypass valves.
The licensee proposed to add a note to each units TS Table 3.3.2-1 that would state, Turbine trip function is not required when all turbine stop valves or all governor valves are closed and are incapable of opening, which would allow the turbine trip function to be considered met when either all turbine stop valves or all governor valves are closed and are incapable of being opened.
The NRC staff reviewed the proposed change and determined that the turbine trip function will be met when all turbine stop valves or all governor valves are closed and are incapable of opening. If any turbine stop valve or any governor valve is not closed, then the required actions for Function 5, in Modes 1, 2, or 3, will be required to be met. The remaining functionstripping the MFW pumps, initiating feedwater isolation, and shutting the MFW regulating valves and the bypass feedwater regulating valveswill still be required to be met. The staff also determined that the appropriate controls will still be provided to maintain the ALLOWABLE VALUE and NOMINAL TRIP SETPOINT for Functions 5.a and 5.b within prescribed operating ranges as the ALLOWABLE VALUE and NOMINAL TRIP SETPOINT were not changed as part of this LAR.
Therefore, the NRC staff finds that the proposed addition of note (j) to Sequoyah TS Table 3.3.2-1, note (i) to Watts Bar, Unit 1, TS Table 3.3.2-1, and note (j) to Watts Bar, Unit 2, TS Table 3.3.2-1 is acceptable.
3.2 Evaluation of Proposed Revision to Notes (f) and (h) for Watts Bar, Units 1 and 2 The licensee proposed a revision to notes (f) and (h) of Watts Bar, Units 1 and 2, TS Table 3.3.2-1, respectively. Initially, the licensee had proposed to change the words associated bypass valves to MFRV bypass valves, and remove the phrase and de-activated. However, upon further review, the licensee decided to retain the words associated bypass valves, and provided a supplement dated February 12, 2025, to revise the LAR accordingly.
In a November 27, 2024, response to a request for additional information regarding the removal of the words, and deactivated, the licensee stated that the intent of TS LCO 3.3.2 for the Feedwater Isolation function is to ensure that the feedwater flow to the SGs is terminated. Once the flow path is isolated, the circuitry is no longer necessary to ensure the assumptions of the safety analysis remain valid. The licensee further stated that with the valves closed, they are performing their intended safety function. Valve indication is readily available to operators in the main control room and is verified post trip with contingency actions in place to mitigate a failure to isolate. If the feedwater isolation circuitry is rendered inoperable, actions required to mitigate a high-energy line break cause operations to isolate the flow path by putting the required valves in their required position (i.e., closed) to perform their design safety function. Once closed, the circuitry is no longer required. Discrete operator action is required to reopen these valves; therefore, deactivation is unnecessary.
The licensee also explained that the main feedwater isolation valves (MFIVs) and bypass valves, and MFRVs and bypass valve control logic is designed so that upon reset of the FWI signal, the valves will remain closed. Following an FWI signal, these valves will be reset by two additional switches in the main control room.
Additionally, the licensee provided information regarding the manual valves that can isolate the 16-inch MFW line and the 6-inch bypass line. The licensee also described the 16-inch MFIVs and MFRVs, and the 6-inch bypass MFIVs and MFRVS, including their controllers and fail positions upon a loss of power or air. The licensee stated that at Watts Bar the manual valve for the 16-inch MFW line has a motor operator; however, it does not have any associated automatic controls, and it is only operated by a local hand-switch or the valves handwheel, which would be used if the motor operator failed. Once the valve is closed by a field operator, the valve stays closed until further operator action is taken to open it.
The NRC staff has evaluated the requested change to Watts Bar, Units 1 and 2, TS Table 3.3.2-1, notes (f) and (h), respectively, the system design information in the UFSAR, and the licensees supplements dated November 27, 2024, and February 12, 2025. Based on its review of this information, the NRC staff determined that because valves will remain closed after the FWI signal is reset, and discrete operator action is needed to reset the valves or reopen them, the condition that the valves be deactivated is unnecessary. Additionally, notes (f) and (h) retain the alternative condition that the main feedwater and bypass lines can be isolated by a closed manual valve. The staff also determined that the appropriate controls will still be provided to maintain the ALLOWABLE VALUE and NOMINAL TRIP SETPOINT for Functions 5.a and 5.b within prescribed operating ranges as the ALLOWABLE VALUE and NOMINAL TRIP SETPOINT were not changed as part of this LAR. Therefore, the NRC staff finds that the proposed change to notes (f) and (h) for the Watts Bar, Units 1 and 2, TS Table 3.3.2-1, respectively, is acceptable.
3.3 Evaluation of Conforming Changes to TS Table 3.3.2-1 The licensee proposed editorial and conforming changes to Sequoyah and Watts Bar TS Table 3.3.2-1. Specifically, for Sequoyah, Units 1 and 2, the licensee proposed to re-letter existing note (j) to note (k) for Functions 6.d.(1) and (2) and from note (k) to note (l) for Function 6.e due to the addition of note (j) for Functions 5.a and 5.b.
For Watts Bar, Unit 1, the licensee proposed the deletion of note (j) which says Deleted and the re-lettering of note (i) for Function 6.e.(1) to note (j) due to the addition of note (i) for Functions 5.a and 5.b.
For Watts Bar, Unit 2, the licensee proposed the deletion of note (k) which says Deleted and the re-lettering of note (j) for Function 6.e.(1) to note (k) due to the addition of note (j) for Functions 5.a and 5.b, and the re-lettering of note (m) to note (l) for Function 6.f due to deletion of note (k).
The NRC staff has evaluated the proposed conforming changes described above and finds them to be acceptable because they are administrative in nature and do not change the technical content of the notes nor do they change any of the ESFAS instrumentation functions or aspects that pertain to the functions.
3.4 Technical Conclusion Based on its evaluation, the NRC staff determined that that the turbine trip function will be met when all turbine stop valves or all governor valves are closed and are incapable of opening. The staff also determined that because the MFIVs, MFRVs, and associated bypass valves will remain closed after the FWI signal is reset, and discrete operator action is needed to reset the valves or reopen them, the condition that the valves be deactivated is unnecessary. Lastly, the staff determined that the conforming changes to the Sequoyah and Watts Bar TS Table 3.3.2-1 notes were administrative in nature and do not change the technical content of the notes.
Therefore, the NRC staff finds that the proposed changes discussed in the sections are acceptable because the Sequoyah and Watts Bar TS Table 3.3.2-1, Function 5, as revised, will continue to meet the requirements of 10 CFR 50.36(c)(2).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendments on January 29, 2025. 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 amendments also change the format of the license or permit or otherwise make editorial, corrective or other minor revisions. The Commission previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on October 1, 2024 (89 FR 79971), 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) and 10 CFR 51.22(c)(10)(v). 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 Contributors: T. Sweat, NRR K. Green, NRR Date: March 31, 2025
ML25051A210 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DSS/SNSB/BC NAME KGreen ABaxter DMurdock DATE 02/20/2025 02/21/2025 02/27/2025 OFFICE NRR/DSS/STSB/BC(A)
NRR/DSS/SCPB/BC NRR/DEX/EICB/BC NAME SMehta MValentin (BLee for)
FSacko DATE 02/25/2025 02/27/2025 03/10/2025 OFFICE OGC - NLO w/edits NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME MFWoods DWrona KGreen DATE 03/31/2025 3/31/2025 3/31/2025