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| =Text= | | =Text= |
| {{#Wiki_filter:September 22, 2023 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801 | | {{#Wiki_filter:September 22, 2023 |
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| | Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==Dear Mr. Barstow:== | | ==Dear Mr. Barstow:== |
| | The purpose of this letter is to make administrative changes to the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68. |
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| The purpose of this letter is to make administrative changes to the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68.
| | After the U.S. Nuclear Regulatory Commiss ion (NRC) issued the subject amendments (Agencywide Documents and Management System (ADAMS) Accession No. ML23205A213) on September 8, 2023, Tennessee Valley Authority (TVA) informed the NRC project manager that certain technical specification (TS) pages were issued with spacing that differed from guidance in Technical Specification Task Force (TSTF) Traveler TSTF-GG-05-01, Writers Guide for Plant-Specific Improved Technical Specificat ions (ML060720511). Specifically, the spacing of the entries in the Completion Time column for TS 3.4.7 Required Actions A.1 and D.1 (Unit 1), |
| After the U.S. Nuclear Regulatory Commission (NRC) issued the subject amendments (Agencywide Documents and Management System (ADAMS) Accession No. ML23205A213) on September 8, 2023, Tennessee Valley Authority (TVA) informed the NRC project manager that certain technical specification (TS) pages were issued with spacing that differed from guidance in Technical Specification Task Force (TSTF) Traveler TSTF-GG-05-01, Writers Guide for Plant-Specific Improved Technical Specifications (ML060720511). Specifically, the spacing of the entries in the Completion Time column for TS 3.4.7 Required Actions A.1 and D.1 (Unit 1), | |
| C.1 and D.1 (Unit 2), and D.1 and E.2 (Unit 3) was inconsistent with the guidance. At the TVAs request, the NRC is reissuing the affected TS pages to adjust the spacing so that it is consistent with the guidance in TSTF-GG-05-01 and with the other Completion Time entries in the Browns Ferry TSs. | | C.1 and D.1 (Unit 2), and D.1 and E.2 (Unit 3) was inconsistent with the guidance. At the TVAs request, the NRC is reissuing the affected TS pages to adjust the spacing so that it is consistent with the guidance in TSTF-GG-05-01 and with the other Completion Time entries in the Browns Ferry TSs. |
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| The NRC concludes that these changes are entirely administrative in nature and do not change the staffs previous conclusion in the safety evaluation for issuance of Amendment Nos. 332, 355, and 315, nor do they affect the no significant hazards considerations, as published in the Federal Register on May 16, 2023 (88 FR 31285). | | The NRC concludes that these changes are entirely administrative in nature and do not change the staffs previous conclusion in the safety evaluation for issuance of Amendment Nos. 332, 355, and 315, nor do they affect the no significant hazards considerations, as published in the Federal Register on May 16, 2023 (88 FR 31285). |
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| Enclosed, please find reissued TS pages 3.4-18 and 3.4-19 (Unit 1), TS page 3.4-19 (Unit 2), | | Enclosed, please find reissued TS pages 3.4-18 and 3.4-19 (Unit 1), TS page 3.4-19 (Unit 2), |
| and TS pages 3.4-19 and 3.4-19a (Unit 3). | | and TS pages 3.4-19 and 3.4-19a (Unit 3). |
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| J. Barstow If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov. | | J. Barstow |
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| | If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov. |
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| Sincerely, | | Sincerely, |
| /RA/
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| Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, 50-296 | | /RA/ |
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| | Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| | Docket Nos. 50-259, 50-260, 50-296 |
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| ==Enclosure:== | | ==Enclosure:== |
| | Reissued Pages for Amendment No. 332 Reissued Pages for Amendment No. 355 Reissued Pages for Amendment No. 315 |
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| | cc: Listserv |
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| | ENCLOSURE |
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| | BROWNS FERRY NUCLEAR PLANT, UNIT NOS. 2 AND 3 |
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| | DOCKET NOS. 50-259,50-260, AND 50-296 |
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| | REISSUED TECHNICAL SPECIFICATION PAGES FOR LICENSE AMENDMENT NOS. 332, 355, AND 315 |
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| | UNIT 1 TECHNICAL SPECIFICATION PAGES 3.4-18 AND 3.4-19 UNIT 2 TECHNICAL SPECIFICATION PAGE 3.4-19 UNIT 3 TECHNICAL SPECIFICATION PAGES 3.4-19 AND 3.4-19a |
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| Reissued Pages for Amendment No. 332 Reissued Pages for Amendment No. 355 Reissued Pages for Amendment No. 315 cc: Listserv
| | RHR Shutdown Cooling System - Hot Shutdown 3.4.7 |
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| ENCLOSURE BROWNS FERRY NUCLEAR PLANT, UNIT NOS. 2 AND 3 DOCKET NOS. 50-259,50-260, AND 50-296 REISSUED TECHNICAL SPECIFICATION PAGES FOR LICENSE AMENDMENT NOS. 332, 355, AND 315 UNIT 1 TECHNICAL SPECIFICATION PAGES 3.4-18 AND 3.4-19 UNIT 2 TECHNICAL SPECIFICATION PAGE 3.4-19 UNIT 3 TECHNICAL SPECIFICATION PAGES 3.4-19 AND 3.4-19a
| | 3.4 REACTOR COOLANT SYSTEM (RCS) |
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| RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
| | 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown |
| ---------------------------------------NOTES---------------------------------------
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| | LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation. |
| | |
| | ---------------------------------------NOTES--------------------------------------- |
| : 1. Both required RHR shutdown cooling subsystems and recirculation pumps may not be in operation for up to 2 hours per 8 hour period. | | : 1. Both required RHR shutdown cooling subsystems and recirculation pumps may not be in operation for up to 2 hours per 8 hour period. |
| : 2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours for performance of Surveillances. | | : 2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours for performance of Surveillances. |
| APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR low pressure permissive pressure. | | |
| | APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR low pressure permissive pressure. |
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| ACTIONS | | ACTIONS |
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| ------------------------------------------------------NOTE--------------------------------------------------- | | ------------------------------------------------------NOTE--------------------------------------------------- |
| Separate Condition entry is allowed for each RHR shutdown cooling subsystem. | | Separate Condition entry is allowed for each RHR shutdown cooling subsystem. |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHR A.1 Verify an alternate 1 hour shutdown cooling method of decay heat subsystem inoperable. removal is available. AND Once per 24 hours thereafter (continued)
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| BFN-UNIT 1 3.4-18 Amendment No. 234, 249, 332
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| RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued) | | CONDITION REQUIRED ACTION COMPLETION TIME |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated RHR shutdown cooling Completion Time of subsystem to OPERABLE Condition A not met. status. | | |
| C. Two required RHR C.1 Verify an alternate 1 hour shutdown cooling method of decay heat subsystems removal is available for AND inoperable. each inoperable RHR shutdown cooling Once per 24 subsystem hours thereafter D. Required Action and -------------------NOTE----------------- | | A. One required RHR A.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystem inoperable. removal is available. AND |
| associated LCO 3.0.3 and all other LCO Completion Time of Required Actions requiring a Condition C not met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. | | |
| D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status. | | Once per 24 hours thereafter |
| | |
| | (continued) |
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| | BFN-UNIT 1 3.4-18 Amendment No. 234, 249, 332 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 |
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| | ACTIONS (continued) |
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| | CONDITION REQUIRED ACTION COMPLETION TIME |
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| | B. Required Action andB.1 Initiate action to restoreImmediately associated RHR shutdown cooling Completion Time of subsystem to OPERABLE Condition A not met. status. |
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| | C. Two required RHRC.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems removal is available for AND inoperable. each inoperable RHR shutdown cooling Once per 24 subsystem hours thereafter |
| | |
| | D. Required Action and-------------------NOTE----------------- |
| | associated LCO 3.0.3 and all other LCO Completion Time of Required Actions requiring a Condition C not met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. |
| | |
| | D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status. |
| | |
| (continued) | | (continued) |
| BFN-UNIT 1 3.4-19 Amendment No. 234, 332
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| RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued) | | BFN-UNIT 1 3.4-19 Amendment No. 234, 332 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status. | | |
| C. Two required RHR C.1 Verify an alternate 1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter D. Required Action and ------------------NOTE------------------ | | ACTIONS (continued) |
| associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. | | CONDITION REQUIRED ACTION COMPLETION TIME |
| D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status. | | |
| | B. Required Action and B.1 Initiate action to restoreImmediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status. |
| | |
| | C. Two required RHR C.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter |
| | |
| | D. Required Action and ------------------NOTE------------------ |
| | associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. |
| | |
| | D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status. |
| | |
| (continued) | | (continued) |
| BFN-UNIT 2 3.4-19 Amendment No. 253, 355
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| RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued) | | BFN-UNIT 2 3.4-19 Amendment No. 253, 355 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status. | | |
| C. Two required RHR C.1 Verify an alternate 1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter D. Required Action and ------------------NOTE------------------ | | ACTIONS (continued) |
| | CONDITION REQUIRED ACTION COMPLETION TIME |
| | |
| | B. Required Action and B.1 Initiate action to restoreImmediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status. |
| | |
| | C. Two required RHR C.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter |
| | |
| | D. Required Action and ------------------NOTE------------------ |
| associated Completion | | associated Completion |
| Time of Condition C not LCO 3.0.3 and all other LCO meW. Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. | | Time of Condition C not LCO 3.0.3 and all other LCO meW. Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. |
| D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status. | | |
| | D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status. |
| | |
| (continued) | | (continued) |
| BFN-UNIT 3 3.4-19 Amendment No. 212, 315
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| RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued) | | BFN-UNIT 3 3.4-19 Amendment No. 212, 315 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 |
| CONDITION REQUIRED ACTION COMPLETION TIME E. No RHR shutdown E.1 Initiate action to restore Immediately cooling subsystem in one RHR shutdown operation. cooling subsystem or one recirculation pump to AND operation. | | |
| | ACTIONS (continued) |
| | CONDITION REQUIRED ACTION COMPLETION TIME |
| | |
| | E. No RHR shutdown E.1 Initiate action to restoreImmediately cooling subsystem in one RHR shutdown operation. cooling subsystem or one recirculation pump to AND operation. |
| | |
| No recirculation pump in AND operation. | | No recirculation pump in AND operation. |
| E.2 Verify reactor coolant 1 hour from circulation by an alternate discovery of no method. reactor coolant circulation AND Once per 12 hours thereafter AND E.3 Monitor reactor coolant Once per hour temperature and pressure. | | E.2 Verify reactor coolant1 hour from circulation by an alternate discovery of no method. reactor coolant circulation |
| BFN-UNIT 3 3.4-19a Amendment No. 212, 315 | | |
| | AND |
| | |
| | Once per 12 hours thereafter AND |
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| | E.3 Monitor reactor coolantOnce per hour temperature and pressure. |
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| | BFN-UNIT 3 3.4-19a Amendment No. 212, 315 |
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| ML23257A123 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME KGreen RButler DWrona KGreen DATE 09/14/23 09/15/23 09/21/23 09/22/23}} | | ML23257A123 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME KGreen RButler DWrona KGreen DATE 09/14/23 09/15/23 09/21/23 09/22/23}} |
Letter Sequence Other |
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MONTHYEARCNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023
Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4
Project stage: Request
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
Project stage: Approval
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
Project stage: Other
2023-09-22
[Table View] |
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Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024
Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003
CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024
Application for Subsequent Renewed Operating Licenses, Second Safety Supplement
ML24305A1692024-10-31031 October 2024
Site Emergency Plan Implementing Procedure Revision
05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024
Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators
05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024
Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure
ML24299A2632024-10-25025 October 2024
Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075
ML24289A1232024-10-24024 October 2024
Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24308A0042024-10-16016 October 2024
Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County
CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024
Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1
ML24270A2162024-09-27027 September 2024
Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24263A2952024-09-19019 September 2024
Site Emergency Plan Implementing Procedure Revision
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000260/20240902024-09-17017 September 2024
NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1
CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024
Cycle 16 Reload Analysis Report
ML24255A8862024-09-10010 September 2024
Core Operating Limits Report for Cycle 16 Operation, Revision 0
ML24239A3332024-09-0303 September 2024
Full Audit Plan
IR 05000259/20244042024-09-0303 September 2024
Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter
IR 05000259/20240052024-08-26026 August 2024
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005
ML24225A1682024-08-16016 August 2024
– Notification of Inspection and Request
IR 05000259/20244022024-08-0606 August 2024
Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402
ML24219A0272024-08-0606 August 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000259/20240022024-08-0202 August 2024
Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
ML24183A4142024-07-10010 July 2024
– License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296)
05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024
Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024
Inoperability of Unit 3 Diesel Generator Due to Relay Failure
ML24184A1142024-07-0202 July 2024
Site Emergency Plan Implementing Procedure Revision
ML24183A3842024-07-0101 July 2024
Registration of Use of Cask to Store Spent Fuel (MPC-364, -365)
ML24179A0282024-06-26026 June 2024
Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a)
05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024
Reactor Scram Due to Generator Step-Up Transformer Failure
ML24175A0042024-06-23023 June 2024
Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System
ML24176A1132024-06-23023 June 2024
American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24155A0042024-06-18018 June 2024
Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47)
ML24158A5312024-06-0606 June 2024
Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363)
ML24071A0292024-06-0505 June 2024
Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter
ML24068A2612024-06-0505 June 2024
SLRA Fluence Methodology Report - Proprietary Determination Letter
IR 05000259/20244032024-05-22022 May 2024
– Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403
05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024
High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24136A0702024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
IR 05000259/20240012024-05-14014 May 2024
Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24123A2012024-05-0202 May 2024
NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information
ML24122A6852024-05-0101 May 2024
2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual
2024-09-03
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24043A0462024-02-16016 February 2024
Summary of Meeting with TVA to Discuss Use of Risk-Informed Process Evaluation (RIPE) for a Proposed LAR Regarding Elimination of Limiting Condition for Operation Actions for Rod Worth Minimizers
ML23319A1992024-01-0303 January 2024
Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23116A2472023-05-23023 May 2023
Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control
ML23101A1102023-05-16016 May 2023
Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications
ML23073A2902023-05-0202 May 2023
Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22348A0662023-01-13013 January 2023
Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22327A0182022-12-0101 December 2022
Correction of Error Incurred During Issuance of License Amendment No. 322
ML22273A1032022-11-22022 November 2022
Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification
ML22220A2602022-11-21021 November 2022
Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A
ML22138A3252022-06-24024 June 2022
Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis
ML22161A9292022-06-10010 June 2022
Bf 2022-301 Exam Report Items, SRO Written Exam
ML22020A2282022-03-16016 March 2022
Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2
ML21285A0682021-10-28028 October 2021
Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2
ML21214A1392021-08-30030 August 2021
Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters
ML21173A1772021-07-27027 July 2021
Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components
ML21075A0762021-04-30030 April 2021
Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis
ML21041A4892021-04-0808 April 2021
Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3
ML20268A0822021-01-12012 January 2021
Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20190A1052020-08-11011 August 2020
Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation
ML20085G8962020-06-26026 June 2020
Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times
ML19294A0112019-12-26026 December 2019
Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2
ML18277A1102019-08-27027 August 2019
Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection
ML19198A0012019-08-13013 August 2019
Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140)
ML19037A1372019-04-0202 April 2019
Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants
ML18241A3192018-10-0909 October 2018
Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision
ML18251A0032018-09-27027 September 2018
Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292)
ML18138A4522018-05-29029 May 2018
Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20
ML17289A0322017-12-22022 December 2017
Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160)
ML17215A2432017-10-0202 October 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566)
ML17032A1202017-08-14014 August 2017
Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate
ML17034A3602017-03-27027 March 2017
Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ...
ML17052A1362017-03-16016 March 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos. 297, 321, and 281 to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 (CAC Nos. MF8125, MF8126, and MF8127)
ML16330A1582017-01-17017 January 2017
Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality
ML16028A4142016-04-26026 April 2016
Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio
ML15317A4782016-02-0909 February 2016
Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio
ML15344A3212016-01-0707 January 2016
Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits
ML15321A4722015-12-23023 December 2015
Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation
ML15287A2132015-12-16016 December 2015
Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits
ML15324A2472015-12-14014 December 2015
Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control
ML15287A3712015-12-0404 December 2015
Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029)
ML15212A7962015-10-28028 October 2015
Issuance of Amendments to Transition to Fire Protection Program NFPA-805
ML15251A5402015-09-29029 September 2015
Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0
ML15065A0492015-06-0202 June 2015
Issuance of Amendment Revising Pressure and Temperature Limit Curves
2024-02-16
[Table view] |
Text
September 22, 2023
Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - ADMINISTRATIVE CHANGES TO TECHNICAL SPECIFICATION PAGES ISSUED FOR LICENSE AMENDMENT NOS. 332, 355, AND 315 (EPID L-2023-LLA-0035)
Dear Mr. Barstow:
The purpose of this letter is to make administrative changes to the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68.
After the U.S. Nuclear Regulatory Commiss ion (NRC) issued the subject amendments (Agencywide Documents and Management System (ADAMS) Accession No. ML23205A213) on September 8, 2023, Tennessee Valley Authority (TVA) informed the NRC project manager that certain technical specification (TS) pages were issued with spacing that differed from guidance in Technical Specification Task Force (TSTF) Traveler TSTF-GG-05-01, Writers Guide for Plant-Specific Improved Technical Specificat ions (ML060720511). Specifically, the spacing of the entries in the Completion Time column for TS 3.4.7 Required Actions A.1 and D.1 (Unit 1),
C.1 and D.1 (Unit 2), and D.1 and E.2 (Unit 3) was inconsistent with the guidance. At the TVAs request, the NRC is reissuing the affected TS pages to adjust the spacing so that it is consistent with the guidance in TSTF-GG-05-01 and with the other Completion Time entries in the Browns Ferry TSs.
The NRC concludes that these changes are entirely administrative in nature and do not change the staffs previous conclusion in the safety evaluation for issuance of Amendment Nos. 332, 355, and 315, nor do they affect the no significant hazards considerations, as published in the Federal Register on May 16, 2023 (88 FR 31285).
Enclosed, please find reissued TS pages 3.4-18 and 3.4-19 (Unit 1), TS page 3.4-19 (Unit 2),
and TS pages 3.4-19 and 3.4-19a (Unit 3).
J. Barstow
If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov.
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. 50-259, 50-260, 50-296
Enclosure:
Reissued Pages for Amendment No. 332 Reissued Pages for Amendment No. 355 Reissued Pages for Amendment No. 315
cc: Listserv
ENCLOSURE
BROWNS FERRY NUCLEAR PLANT, UNIT NOS. 2 AND 3
DOCKET NOS. 50-259,50-260, AND 50-296
REISSUED TECHNICAL SPECIFICATION PAGES FOR LICENSE AMENDMENT NOS. 332, 355, AND 315
UNIT 1 TECHNICAL SPECIFICATION PAGES 3.4-18 AND 3.4-19 UNIT 2 TECHNICAL SPECIFICATION PAGE 3.4-19 UNIT 3 TECHNICAL SPECIFICATION PAGES 3.4-19 AND 3.4-19a
RHR Shutdown Cooling System - Hot Shutdown 3.4.7
3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown
LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES---------------------------------------
- 1. Both required RHR shutdown cooling subsystems and recirculation pumps may not be in operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for performance of Surveillances.
APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR low pressure permissive pressure.
ACTIONS
NOTE---------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One required RHR A.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystem inoperable. removal is available. AND
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter
(continued)
BFN-UNIT 1 3.4-18 Amendment No. 234, 249, 332 RHR Shutdown Cooling System - Hot Shutdown 3.4.7
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. Required Action andB.1 Initiate action to restoreImmediately associated RHR shutdown cooling Completion Time of subsystem to OPERABLE Condition A not met. status.
C. Two required RHRC.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems removal is available for AND inoperable. each inoperable RHR shutdown cooling Once per 24 subsystem hours thereafter
D. Required Action and-------------------NOTE-----------------
associated LCO 3.0.3 and all other LCO Completion Time of Required Actions requiring a Condition C not met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status.
(continued)
BFN-UNIT 1 3.4-19 Amendment No. 234, 332 RHR Shutdown Cooling System - Hot Shutdown 3.4.7
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. Required Action and B.1 Initiate action to restoreImmediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status.
C. Two required RHR C.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter
D. Required Action and ------------------NOTE------------------
associated Completion LCO 3.0.3 and all other LCO Time of Condition C not Required Actions requiring a met. MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status.
(continued)
BFN-UNIT 2 3.4-19 Amendment No. 253, 355 RHR Shutdown Cooling System - Hot Shutdown 3.4.7
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. Required Action and B.1 Initiate action to restoreImmediately associated Completion RHR shutdown cooling Time of Condition A not subsystem to OPERABLE met. status.
C. Two required RHR C.1 Verify an alternate1 hour shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 subsystem. hours thereafter
D. Required Action and ------------------NOTE------------------
associated Completion
Time of Condition C not LCO 3.0.3 and all other LCO meW. Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restoreImmediately one RHR shutdown cooling subsystem to OPERABLE status.
(continued)
BFN-UNIT 3 3.4-19 Amendment No. 212, 315 RHR Shutdown Cooling System - Hot Shutdown 3.4.7
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
E. No RHR shutdown E.1 Initiate action to restoreImmediately cooling subsystem in one RHR shutdown operation. cooling subsystem or one recirculation pump to AND operation.
No recirculation pump in AND operation.
E.2 Verify reactor coolant1 hour from circulation by an alternate discovery of no method. reactor coolant circulation
AND
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND
E.3 Monitor reactor coolantOnce per hour temperature and pressure.
BFN-UNIT 3 3.4-19a Amendment No. 212, 315
ML23257A123 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME KGreen RButler DWrona KGreen DATE 09/14/23 09/15/23 09/21/23 09/22/23
