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MONTHYEARML0511501912005-04-19019 April 2005 Enclosure 3, Ltr, Licensing Action Status and Interdependencies Project stage: Other ML0514300362005-05-20020 May 2005 Response to Nrc'S Letter on Licensing Action Status and Interdependencies, Project stage: Other ML0622104582006-09-27027 September 2006 License Amendment 261 Limits on Main Steam Isolation Valve Leakage Project stage: Approval ML0627100142006-09-27027 September 2006 Tech Spec Pages for Amendment 261 Limits on Main Steam Isolation Valve Leakage Project stage: Other 2005-05-20
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application 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 ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation 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 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills 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 ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-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 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-04-28028 April 2022 Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-009, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-03-31031 March 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CNL-21-002, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.2021-12-0303 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance. CNL-21-090, Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539)2021-11-19019 November 2021 Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539) CNL-21-020, Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2021-11-0505 November 2021 Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) CNL-21-050, License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2021-05-29029 May 2021 License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)2021-03-0505 March 2021 Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)2020-07-17017 July 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) CNL-20-044, License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis2020-05-0606 May 2020 License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition CNL-19-009, License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515)2019-09-18018 September 2019 License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515) CNL-19-070, TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor2019-07-0303 July 2019 TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor CNL-19-034, to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3..2019-03-0808 March 2019 to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3.. CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-099, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results2018-07-23023 July 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme2018-06-15015 June 2018 License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-056, Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2017-08-15015 August 2017 Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-014, Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Pro2017-04-0505 April 2017 Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Proce CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To..2017-01-17017 January 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To.. CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-010, Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508)2016-08-12012 August 2016 Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508) CNL-16-016, License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82016-07-14014 July 2016 License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 CNL-16-068, Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2016-03-28028 March 2016 Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. CNL-15-074, Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants2015-06-19019 June 2015 Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) 2023-03-30
[Table view] Category:Safety Evaluation
MONTHYEARML23319A1992024-01-0303 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 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 ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program 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 ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) 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 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 ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes 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 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants 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 ML20253A1812020-09-23023 September 2020 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Code ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times ML19329E3192020-01-0202 January 2020 SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044) 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 ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML19016A2152019-02-28028 February 2019 Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-46 ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds 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) ML18236A3312018-09-24024 September 2018 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 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) ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds 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 ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) 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 ... 2024-01-03
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September 27, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING LIMITS ON MAIN STEAM ISOLATION VALVE LEAKAGE (TAC NO. MC3813)
Dear Mr. Singer:
The Commission has issued the enclosed Amendment No. 261 to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant (BFN), Unit 1. This amendment is in response to your application dated July 9, 2004 (letter TVA-BFN-TS-436).
The amendment revises BFN Unit 1 Technical Specifications Surveillance Requirement 3.6.1.3.10 to increase the allowed main steam isolation valve (MSIV) leak rate limit from 11.5 standard cubic feet per hour (scfh) per valve, to 100 scfh for each individual MSIV with a combined leak rate of 150 scfh for all four main steam lines.
A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosures:
- 1. Amendment No. 261 to DPR-33
- 2. Safety Evaluation cc w/enclosures: See next page
September 27, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING LIMITS ON MAIN STEAM ISOLATION VALVE LEAKAGE (TAC NO. MC3813)
Dear Mr. Singer:
The Commission has issued the enclosed Amendment No. 261 to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant (BFN), Unit 1. This amendment is in response to your application dated July 9, 2004 (letter TVA-BFN-TS-436).
The amendment revises BFN Unit 1 Technical Specifications Surveillance Requirement 3.6.1.3.10 to increase the allowed main steam isolation valve (MSIV) leak rate limit from 11.5 standard cubic feet per hour (scfh) per valve, to 100 scfh for each individual MSIV with a combined leak rate of 150 scfh for all four main steam lines.
A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosures:
- 1. Amendment No. 261 to DPR-33
- 2. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION:
PUBLIC GHill, OIS (2 hard copies) JMa LPL2-2 R/F RidsRgn2MailCenter (MWidmann, LMellen) RGoel RidsNrrLACGoldstein RidsOgcRP RidsAcrsAcnwMailCenter RidsNrrDeEgcb RidsNrrDorlLpl2-2 (LRaghavan) RidsNrrDssScvb DDuvigneaud RidsNrrDorlDpr RidsNrrPMMChernoff RidsNrrDirsItsb RidsNrrPMEBrown RidsNrrLABClayton (Hard Copy)
RidsNrrPMFLyon RidsNrrDssSbpb Package: ML062210461 Tech Spec: ML062710014 ADAMS Accession No.: ML062210458 **Memo dated 5/11/05 NRR-058 OFFICE LPL2-2/PE LPL2-2/PM LPL2-2/LA SCVB/BC EGCB/BC ITSB/BC SBPB/BC OGC LPL2-2/BC NAME FLyon for BClayton for DDuvigneaud MChernoff CGoldstein RDenning** RKaras TKobetz JSegala DRoth LRaghavan DATE 8/23/06 8/23/06 8/23/06 5/11/05 8/30/06 9/1/06 8/31/06 9/22/06 9/26/06 Official Record Copy
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 261 Renewed License No. DPR-33
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated July 9, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 261, are hereby incorporated in the 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 from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 27, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Replace Page 3 of Renewed Operating License DPR-33 with the attached Page 3.
Revise the Appendix A Technical Specifications by removing the page identified below and inserting the attached page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 3.6-16 3.6-16
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259
1.0 INTRODUCTION
By letter dated July 9, 2004 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML041980222), the Tennessee Valley Authority (TVA, the licensee) submitted to the Nuclear Regulatory Commission (NRC) a request for changes to the Browns Ferry Nuclear Plant (BFN), Unit 1, Technical Specifications (TSs). The proposed changes increase the allowable leakage limit for any one of the four main steam line (MSL) penetrations from 11.5 standard cubic feet per hour (scfh) to 100 scfh, and establish a 150-scfh limit on the maximum allowable combined leakage of all four MSL penetrations.
Specifically, TS Surveillance Requirement (SR) 3.6.1.3.10 currently states:
Verify leakage rate through each MSIV is # 11.5 scfh when tested at $ 25 psig.
The licensee proposes to revise TS SR 3.6.1.3.10 to state:
Verify leakage rate through each MSIV is # 100 scfh and that the combined leakage rate for all four main steam lines is # 150 scfh when tested at $ 25 psig.
The licensee's application also included a request for exemption from Title 10, Code of Federal Regulations (10 CFR), Part 50, Appendix J. The proposed exemption would allow the licensee to exclude leakage from MSL penetrations from consideration in meeting the requirement that the total leakage of Type B and Type C containment penetrations shall not exceed 60 percent of the maximum allowable containment leakage (i.e., 0.6 La). MSL penetrations are Type C containment penetrations. The request for exemption is being reviewed by the NRC staff concurrently as a separate licensing action.
The NRC staff previously approved similar changes to the MSIV leakage rate limits for BFN Units 2 and 3 by Amendment Nos. 263 and 223, respectively, dated March 14, 2000 (ADAMS Accession No. ML003693000). The radiological consequences of the increased MSIV leakage rate limits and the acceptability of the alternate leakage treatment (ALT) system for BFN Unit 1 were previously reviewed and approved by the NRC staff, as documented in the safety
evaluation for BFN Unit 1 Amendment No. 251 (Full-Scope Implementation of Alternative Source Term), dated September 27, 2004 (ADAMS Accession No. ML042730028).
2.0 EVALUATION
2.1 Background
The main steam system transports steam from the reactor vessel to the main turbines and other steam driven auxiliary equipment. Each of the four MSLs contains two quick closing main steam isolation valves (MSIVs) located in the containment penetration piping. One MSIV in each line is located inside the containment, and the other is located outside. These valves serve to rapidly isolate the primary containment MSL penetrations in the event of an MSL break accident or loss-of-coolant accident. At some boiling-water reactor (BWR) facilities, the MSLs are provided with a leakage control system (LCS) to collect and process MSIV leakage; however, BFN-1 does not have an MSIV LCS.
MSIVs, due to their size and service conditions, have a history of leakage in excess of their design criteria. On July 16, 1982, the NRC staff issued NRC Information Notice 82-23, "Main Steam Isolation Valve Leakage," which discussed the high frequency at which MSIVs were failing to meet TS leak test criteria. Because of these recurring problems with excessive leakage of MSIVs, the NRC established Generic Issue C-8, "Main Steam Line Valve Leakage Control Systems." The same year, the BWR Owners' Group (BWROG) formed an MSIV Leakage Committee to address the MSIV leakage issue. In 1986, Generic Letter 86-17, "Technical Findings Related to Generic Issue C-8; Boiling Water Reactor Main Steam Isolation Valve Leakage and Leakage Treatment Methods," was issued, and a follow-on MSIV Leakage Closure Committee was formed to further the effort. Based on the committee<s work, the BWROG developed an approach for resolution of Generic Issue C-8 that proposed to remove the safety related leakage control systems on those facilities having them, and increase MSIV allowable leakage limits. The BWROG described the proposal in "BWROG Report for Increasing MSIV Leakage Rate Limits and Elimination of Leakage Control Systems,"
NEDC-31858P, Revision 1, dated October 1991.
The purpose of NEDC-31858P was to define a means by which BWR licensees could demonstrate to regulators that alternate leakage treatment (ALT) leakage pathways using main steam system piping and the main condenser are capable of performing a post-accident dose mitigation function for MSIV leakage, under safe-shutdown earthquake conditions. This would provide a basis to (1) eliminate MSIV Leakage Control Systems at those facilities having them and (2) increase allowable MSIV leakage rates. The NRC staff reviewed NEDC-31858P, Revision 2, and issued its safety evaluation on March 3, 1999 (ADAMS Accession No. ML010640286), approving the report for reference in future individual plant applications.
The safety evaluation concluded that licensees demonstrating certain plant-specific attributes are eligible for amendments increasing the allowable MSIV leakage rate up to 200 scfh.
Licensees would have to demonstrate that the main steam piping from the outermost isolation valve up to the turbine stop valve, the bypass/drain piping to the main condenser, and the main condenser, will retain structural integrity during and following a safe-shutdown earthquake (SSE). NEDC-31858P was reissued by the BWROG as NEDC-31858P-A (ADAMS Accession No. ML993440254), dated November 22, 1999.
2.2 Technical Evaluation 2.2.1 Review of the ALT Pathway The NRC staff previously reviewed (1) the functional design of the ALT path and capability to establish the ALT path under post-accident conditions, and (2) structural/seismic issues related to integrity of the ALT path. Details of the NRC staff's review are documented in the safety evaluation for BFN Unit 1 Amendment No. 251, dated September 27, 2004 (ADAMS Accession No. ML042730028). The NRC staff's conclusion was that there is reasonable assurance that the BFN Unit 1 MSIV ALT system is seismically adequate for the intended purpose. The NRC staffs conclusion was based on the fact that (1) the ALT pathway has been walked-down in accordance with the procedures in NEDC-31858P-A, which was approved by the NRC staff, (2) all the outliers have been either analytically resolved or physically modified, (3) the condenser was seismically analyzed subject to a design-basis earthquake (DBE) for its adequacy and its anchorages were evaluated to be adequate in accordance with information contained in NEDC-31858P-A, and (4) the turbine building is deemed, through the use of approximate calculations to be followed by performance of dynamic seismic analysis prior to the plant restart, to remain intact following a DBE. In approving Amendment No. 251, the NRC staff added license condition 2.C(15):
The licensee is required to confirm that the conclusions made in TVA's letter dated September 17, 2004 [ADAMS Accession No. ML042730342], for the turbine building remain acceptable using seismic demand accelerations based on dynamic seismic analysis prior to the restart of Unit 1.
In approving this amendment, the NRC staff notes that the licensee must satisfy license condition 2.C(15). The basis used by the NRC staff in approving Amendment No. 251 has not changed; therefore, the staff concludes that the ALT system continues to be adequate to perform its safety function.
2.2.2 Radiological Consequences The NRC staff previously reviewed the radiological consequences for increased MSIV leakage via the ALT path. Details of the staff's review were documented in the safety evaluation for BFN Unit 1 Amendment No. 251. The NRC staff's radiological review encompassed (1) the release pathways, (2) meteorology, and (3) control room habitability, and focused on the changes from previous NRC-accepted analyses. The NRC staff reviewed the technical analyses related to the radiological consequences of DBAs that were performed by TVA in support of Amendment No. 251, which was based on the increased MSIV leakage limits. With regard to BFN, Unit 1, the inputs used in the main steam line break accident, fuel handling accident, and control rod drop accident were bounding for Units 1, 2, and 3. The inputs used in the loss-of-coolant accident were different for Unit 1 and Units 2 and 3; a separate analysis was performed and the bounding results for Units 1, 2, and 3 were provided. Based on its review of information provided by the licensee, the NRC staff concluded that the offsite dose consequences of DBAs are within the acceptance criteria of 10 CFR Part 100, and the control room dose consequences are within the acceptance criteria of 10 CFR Part 50, Appendix A, General Design Criterion 19. The basis used by the NRC staff in approving Amendment No. 251 has not changed; therefore, the staff concludes that the offsite dose consequences of DBAs continue to be within the acceptance criteria of 10 CFR Part 100, and the control room
dose consequences are within the acceptance criteria of 10 CFR Part 50, Appendix A, General Design Criterion 19.
2.2.3 TS Bases Changes The licensee proposed associated changes to the TS Bases. Since the proposed change summarized a required action from the TSs, the NRC staff recommended that the licensee consider revising the proposed change to the TS Bases to more closely conform to NUREG-1433, "Standard TSs, General Electric, BWR/4," Volume 2, "Bases." The issue was discussed in a telephone call on August 21, 2006, between F. Lyon (NRC) and J. McCarthy (TVA). The licensee will consider the issue when the change is processed under its TS Bases Control Program.
2.2.4 Conclusion Based on the information provided by TVA related to increasing the allowable MSIV leakage rate at BFN Unit 1 to 100 scfh per valve, provided the combined leakage from all four MSLs is not greater than 150 scfh, the NRC staff finds reasonable assurance that the ALT will perform its safety function and that radiological consequences of DBAs at BFN, Unit 1 will be within the dose guidelines of 10 CFR Part 100 and the criteria of 10 CFR Part 50, Appendix A, General Design Criterion 19. Therefore, the proposed changes to the MSIV leakage limits are acceptable.
2.3 Summary of Commitments In its July 9, 2004, application, the licensee made the following commitments:
- 1. Prior to Unit 1 restart, plant operating procedures will be revised to provide procedural requirements for the establishment of the ALT path to the condenser.
- 2. The Unit 1 outliers [e.g., conditions that did not conform with the seismic walkdown screening guidelines or were judged by the licensee to require further review] will be resolved prior to Unit 1 restart. This includes qualification of 1-PCV-1-147 and the addition of in-line check valves (1-CKV-1-742 and 1-CKV-1-744) for the offgas preheaters.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff attempted to contact the Alabama State official concerning the proposed issuance of the amendment. There was no official response.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a surveillance requirement. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration,
and there has been no public comment on such finding (71 FR 29680). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is operation in the proposed manner, (2) such activities will be conducted in compliance with the reasonable assurance that the health and safety of the public will not be endangered by Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: J. Ma R. Goel Date: September 27, 2006
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Mr. Glenn W. Morris, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Robert J. Beecken, Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, Manager 10833 Shaw Road Nuclear Assurance and Licensing Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609