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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:News Article
MONTHYEARML18283A5031976-06-21021 June 1976 Forwarding Letter from Mr. Anthony Divito Offering Comments Re Browns Ferry Fire ML18283B8681976-04-0808 April 1976 Forwarding Letter from Constituent Along with Copy of Reader'S Digest Article Entitled, the Burning Question of Browns Ferry, Letter Urging Give Constituent'S View Most Thorough Consideration ML18283B8671976-04-0606 April 1976 Letter Furnishing Re Shocking Experience with Congressman Jones Vicious & Unwarranted Attack on ASLB, NRC Judicial Process 1976-06-21
[Table view] Category:Report
MONTHYEARML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, 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)2022-12-0909 December 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-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data 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 ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation ML21246A2942021-09-29029 September 2021 Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs ML21246A2952021-09-29029 September 2021 Memo to File CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information 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 ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions 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 ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17170A0732017-06-15015 June 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233 ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule ML17033B1642017-02-0202 February 2017 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 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 ML16196A0882016-08-0505 August 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML16146A0182016-05-25025 May 2016 Special Report 296/2016-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration ML16027A0592016-01-27027 January 2016 Snubbers Added to Lnservice Testing Program ML15356A6542015-12-22022 December 2015 Submittal of 10 CFR 50.46 30-Day Report 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) NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 72015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program ML15282A2402015-09-21021 September 2015 Startup Test Plan NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program2015-09-21021 September 2015 Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan ML15254A5432015-09-11011 September 2015 Submittal of 10 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). ML15282A2362015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1822015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.2015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1842015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). ML15282A1852015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 92015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 2023-07-31
[Table view] Category:Technical
MONTHYEARML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-100, 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)2022-12-0909 December 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-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data 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 ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information 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 ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report 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 ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule 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 ML16196A0882016-08-0505 August 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML16027A0592016-01-27027 January 2016 Snubbers Added to Lnservice Testing Program 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) ML15282A2402015-09-21021 September 2015 Startup Test Plan ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 72015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program2015-09-21021 September 2015 Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program ML15282A1822015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 92015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 ML15282A2362015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1842015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). ML15282A1852015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.2015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical2015-06-0303 June 2015 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl2014-12-17017 December 2014 Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plan CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)2014-12-11011 December 2014 (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2014-03-31031 March 2014 Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML14077A0952014-01-30030 January 2014 BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8 ML14077A0902013-12-31031 December 2013 BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11 ML13225A5412013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6342013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3, TAC Nos.: MF0902, MF0903, and MF0904 ML13276A0642013-09-30030 September 2013 ANP-3248NP, Revision 1, Areva RAI Responses for Browns Ferry Atrium 10XM Fuel Transition, Enclosure 3 ML13276A0662013-08-31031 August 2013 ANP-3153(NP), Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for Atrium Tm 1OXM Fuel, Enclosure 8 2023-07-31
[Table view] |
Text
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FROM: ACTION CONTROL ES CONTROL NO.
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FINAL REPI Y ehsterm ~e FILE LOCATION Q CHAIRMAN Q EXECUTIVE DIRECTOR DESCRIPTION g3 LETTER Q MEMO Q REPORT Q OTHER SPECIAL INSTRUCTIONS OR REMARKS re it@ lu Ray 4ene@ eeacereir:g eel'L ei Eha iKcRic SB~ QL8 Xkcc495hg. Xc~ Xcc geMfe hee8m~e ce Gceem Fex~
CLASSIFIED DATA DOCUMENT(COPY NO. C LASS IF I CATION NUMBER OF PAGES CATEGORY POSTAL REGISTRY NO. Q NSI QRD Q FRD ASSIGNED TO DATE INFORMATION ROUTING LEGAL REVIEW Q FINAL Q COPY ASSIGNED TO: DATE NO LEGAL OBJECTIONS NOTIFY:
Q EDO ADMIN8< CORRES BR EXT.
COMMENTS, NOTIFY:
EXT, JCAE NOTIF ICATION RECOMMENDED! QYES Q NO NRC FORM 232 EXECUTIVE DIRECTOR FOR OPERATIONS (11-75) OO NOT REJIIOVE THIS COPY PRINCIPAL CORRESPONDENCE CONTROL
April 6, 1976 lIr. billiam A. Anders, Chairman U. S. Nuclear Regulato~ Commssion
':fashington, D. C. 20555
Dear "hairman Anders:
Re: In the thtter of Tennessee Valley Authority (Browns Ferry Nuclear Plant, Units 1 and 2)
Docket Nos. 50-259 and 50-260 I have and thank you for a copy of a letter from Robert, E, Jones to you and a copy of a letter from Robert E. Jones to Hr. James R. Yore, both dated March 25, 1976. I feel sure that. Hr. Jones vicious and unwarranted at. tack on the Atomic Safety and Licensing Board>> composed of Administrative Judge Reilly>>
Dr. Paxton and Qr. Cowan>> and me was as shocking to you as it, was to me.
This, of course, is not the first time that Hr. Jones has without warrant viciously attacked the judicial process. Enclosed. will be found a copy of an article from The >Jashington Post. of Friday,. ffarch 17, 1972, I will be happy to furnish you with a copy of the transcript of the session referred to in the artie if you need the same.
As you may know, Hr. Jones is known as '9h.. T.V.A." Apparently, he deems any disagreement, with the TVA as an attack .on him.
I do not feel vindictive toward iver. Jones. But>> we must remember that in being merciful, we must think in terms of tempering justice and not. in terms of negating it. Consequently, because of the high position that he occupies, Nr.
Jones attack cannot be ignored. I assume that you will take some positive steps in response to Nr. Jones'ttack on the Board. Conseouently, I will appreciate your keeping me informed of all of your actions in this connection.
Route 4>> Box 354.
Scottsboro, Alabama 35768 (205: 574-5770)
CC:
Certificate of Service List, Browns Ferry LQtter Honorable John 0. Pastore Chairman, Joint Committ,ee on Atomic Energy
~!~ t<s ., ~
<~ Jack Anderson fi 4i Seel'et GrDIIlp Session Hei+
v"f WASHNGTON A few dis- "These judges relish the op- Dams and buifdings had been runtled congressmen, guardi- portunity," he groused, to stop "brought to a screeching halt,"
ns of the prized pork barrel, construction of pork-barrel pro]- he said, while the federal gov-
> geld a secret grump session the ects. Injunctions "are being ernment weighed the effects on 3 other day. malicfously used to halt the pro- the env}ronment.
ects that Congress has worked Attending vere congressmen for years and years and years to "That is just n monstrous
~
~whofn public, pay lip service to accomplish." thing,"he buffed, He was will-
. the .environmental movement. ing to sec people protected by gut in secret, they complained Ho added sourly that "you the laws, he said, hut "the hell bitterly about its impact on their have a bunch of ignoramusses with the fish."
. pet public works projects. who are judges who are not re- He proclaimed that he wanted specting what has been done "to find something that wiff They werc particularly'n- here."
censed over lawsuits that are shortstop all of these )}tttfe pes-
~ .
Boldfng up construction. At one Agreeing, Rep. Bill Harsha, tiferous suits that aro ham-"
- point, Rep. Bob Jones, B-Afa., R-Ohio, also lamb sted "Nr. stringing .the programs,"
~
denounced federal judges as a Nader and his group hat has us As one member after anofher
.'!bunch of i ramusses." tied up in court." He eferred to stood up for pollution, Rep, Jim
- p. im re,
>"Qg no doubt his secret views sex., 'nk- the delay of pet projects while the federaL governmeht makes Kee, Q-W.Ua., tried to under-stand what the discussion was
~en co 'ts, gould nevyr et out to hfs fish-hell Ivi the fhhl" blurted.'X'he sure they won't harm the envi-ronment ail about. "Under wh6 t auth~orf-ty. or pecking order," ha asM, Rep. Pat Caffery, D-La., a the Ervironrnental Pro'- 'does
$ 'Nothing ls dew<<r to the hearts. 'plained spokesman for Big Oil,-com- Agency (EPA) have the "'ection of congressmen than 'federal that the federal environ- to,... hold>up actions'e 'ight projects, hnown in political par- mental protection laws had held aro the'ones who give blected by lance as "pork." lTost of the up plans to lease oil and gas the people."
pork fs dhhed out by the House lands off the Louisiana coast. Cofttee staff members ex-
- Public V/orks Committee, whose "All of.'a sudden at the 11th plained to Kee that public nroj-membe'rs are upset over the en. ects were held up under jaws hour," ho. said, "the court vironmental,restraints u p o n grants their projects. .; . an injunction...
blocking these lease sales." He.
'already on the hoof+. But Com mittee Counsel Richard Su)lfvan JUDGES didn't mention that the court urged that the laws should be acted to prevent a disastrous oil revised to circumvent the tough They gathered .behind closed spill such as the one that fouled environmental'mpact state-
~
. ~gpss to ldiscuss their griev<< tho California coast. ments how required fmforo a s "5hWs project can be started>
". i."We have n64 bbtafned a 56- chimed Rep. Roger Zion, R-Ind The committee immediately pago transcript ~ the secret proceedings. lhp yctfng. chair- and silly."
in to call the present conservation laws "ridiculous hammered oN a hill that wouM permit ER'A to gfve some o! its man, Jones compafrled about powers tahe states which are "these insipid and multitudinous Then Jim Wright began,to as- more'vulnerable to t ne pressure suits filed in these courts.... sault the environmental'cts.. of the big pof Idlers,
ROBERT E,JONES OOM'M ITTZEE B Bill B IT Cf,h
- PUDL1 C WORKS ROIIr ADVRSES~
DCOTFSDORO, ALADhMA
~
Cangn~l Of
~ OOVKRIIIAKIIT O7KRPaT(OILS ttje%311ife0 SIBLE Qou8e ot Q.eyre5cvfatibcd c.t e r.~
~a~bingforr, Rl.E. 20545 March 25, lg76 Mr. Mlliam A. Anders, Chairman Nuclear Regulatory Commission Iiashington, D. C. 20555
Dear Mr. Anders:
I was inost distressed to leaxn of the action of-the Atomic Safety and Licensing Board in calling public hearings regarding Browns Perry Nuclear Plant, Units 1 and 2.
A copy of my letter to Hr. James R. Yore, Acting Chairman of the Atomic Safety and Licensing, Board is enclosed. fox your information. B The expense of public hearings and the exorbitant cost to electxic power consumers in the Tennessee Valley Authority area caused by the delay for the hearings is uncalled fox.
Xt would seem any responsible public agency'hould be
'equired to examine the background of petitionexs who seel". to intervene and thus deIay and impede projects to the total cost of the public.
30 - Logged EX PARTE 1'DQ E B SUSPENSE:
0'ignature.
April 13. Cy of incoming to OGC, OCA,
~
SECY, AS5LB. OCA to ah1."no@ledge.
76-1517 6 E Robert H. Jones J: cvh Enclosures
+~ lN ROBERT Eo JONES COMMITTCCa ITN DIST@4.T, AlJLSAMA tVBLlCWORKS AND-TRANS HORTATION, BOMC AOOSSSSt
, CHAlRMAN SCOTTSBORO, AlJLQAMA Kottgrsdd of tfjo E'ttitob State~<
Joule Of X~eyt:e~~OOtatiba5 Kasfjingtotr, Q.C~. 20515 Harch 25, 1976 Hr. James R. Yore Acting Chairman Atomic Safety and. Licensing Board Nuclear Regulatory Commission Washington, D. C. 20555
Dear Hr. Yore:
I have been told that the Atomic Safety and Licensing, Board has ordered public hearings regarding whether Browns Ferry Nuclear Plant Units'1 an'd 2 should be permitted to go back into operation.
Coming as it does after. full and complete review by the Advisory Committee on Reactor Safeguards of the Nuclear Regulatory. Commission, such a hearing is a flagrant abuse of regulatory process and a complete waste of time and government funds. In addition, delay in operation of the units is costing Tennessee Valley Authority consumers approximately
$ 10 million a month for increased fuel costs.
I want to strongly protest this delay and point out that the Atomic Safety and Licensing Board has an obligation to the public to look into the background and qualifications of petitioners to intervene as well as into the substance of any claims.
Before ordering a hearing, it would certainly seem appropriate to determine whether or not the allegations are some fiction of the petitioner.
If the foolishness of unexamined petitions continue, there will be no fact finding of any finality nor an administrative decision worthy of its salt.
Such travesties of justice are all the more absurd when the hearings are based on the charges of some prejudiced person with a notorious reputation for being discredited time and time again. When the petitioner is an attorney, representing himself and other similar landowners, and
Mr. James R. 'Yore March 25, 1976 Page 2 has chronically sought to delay and impede development of numerous nuclear generating facilities, it would seem his motives and background should be carefully examined before the public is put to the expense of a hearing and the extra cost resulting from delays in operation of a power plant.
If the people in the administrative side of government are going to examine the facts alleging injury, they owe the responsibility to all the people to see who is making the allegations.
An agency which is to be only a citadel to receive the complaints of chronic gripers ought to get out of the business. There will be nothing but constant agitation without substance. If those kind of people are going'o be allowed to constantly visit this kind of injury on the public, there should be some remedial legislative effort made to dampen your reception to delay. These preliminary sparring exhibitions should be ended.
It seems to me that you have over extended your authority in your miscalculation of and callousness for the energy problem of this country.
My'hope is that more substantial thoughts will be given to this whole problem rather than acquiescence to the gadflies that seek interventi.on.
For your information, I am. enclosing an outline of the extensive review and testing procedures which have been accomplished already at Browns Ferry.
Robert E. Jones J:cvh Enclosures cc: Honorable John 0. Pastore Chai.rman, Joint Committee on Atomic Energy Mr. William A. Anders, Chairman Nuclear Regulatory Commission Washington, D. C. 20555
MAJOR REVIEW OF BROQlNS FERRY. FOLLOW',I ~ THE I~3 RCH 22 ~ 1975 g FIRE I. TVA review Immediately following the Inarch 22, 1975, fire, TVA initiated a fact-finding investigation into events lead-ing up to, during, and after the incident until plant conditions were stabilized; The review was conducted by a special committee composed of TVA management from various professional disciplines. Other committees were subsequently formed to study closely many specific aspects of the overall situation and to recommend TVA
'actions with regard to these items. In addition, a comprehensive report, "Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2 as a Result.
of the lIarch 22,. 1975, Fire," has been prepared that fully discusses all aspects of the fire, its effi cts, and plans for restoration activities. This four-volume report was initially submitted to the Nuclear Regulatory Commis-sion on April 13, l975, and has been supplemented and modified as more detailed information became available. The report is very comprehensive and involved hundreds of TVA engineers, scientists, management employees, and out-side consultants. It has been reviewed in detai'1 by several segments of the Nuclear Regulatory Commission and the Advisory Committee on Reactor Safeguards and has been available to the public through the Public Document Room.
II. Inspection Upon and E rcement Review notification that the fire was t
in progress the Nuclear Regulatory Commission's Office of Inspection 'and Enforcement (IGF) dispatched investigators to the site. They performed a detailed on-site investigation into the events surrounding the fire. The IGE investigation was very detailed and took about two and one-half months. A total of 17 investigators took part in the investigation which culminated in issuance of a voluminous report on July 28, 1975.
III.NRC staff review The NRC staff reviewed in detail all aspects of the TVA plans for restoration of the Browns Ferry plant. The NRC review included detailed evaluation of fire damage, fire protection,systa, administrative controls, design modifications, fire stop designs, fire detection systems, and the retesting program. Results of the NRC staff investigations are summarized in their "Safety Evaluation by the Division of Operating Reactors Supporting the Operation After the Restoration and Hodification of the Browns Ferry Nuclear Plant, Units 1 and 2, Following the Harch 22, 1975 Pire," issued February 23, 1976.
The NRC review was performed over a many-month period. The staff concluded that pending resolution of some items "the health and safety of the public will not be endangered by operation of the facility as restored and modified." (Quote fxom p. 10-1 of the NRC staff Safety Evaluation, February 23, 1976)
'XV ACRS Review.
The Advisory Committee on Reactor Safeguards performed an independent review of the fire and restoration activities.
On February 27, 1976, TVA and the NRC staff met with the Browns Ferry ACRS subcommittee charged with conducting a detailed review of the repairs and modifications that are to be made before restart of the fire-affected units.
This was a full day meeting, open to the public, during which TVA and the NRC made detailed .presentations covering all aspects of the evaluation of fire damage, plant cleanup, repair and design modifications that will be implemented and answered questions from the ACRS subcommittee which had arisen as a result of their review. Then on I'.arch 4, 1976, TVA and the NRC staff met with the full ACRS to further review the fire and restoration activities. Tnis meeting was also open to the public. ACRS review resulted in an affirmative recommendation regarding restart of the Bxowns Ferry units and summarized their findings in their Narch ll, 1976, letter from Dade ~~. j'Toellar to William A; Anders.
V. Special NRC Review Group A special review group was appointed by the Nuclear Regulatory Commission to, study the circumstances and implications of the Hrowns Ferry fire. The purpose of this review group was to 'identify the broad lessons to be learned
from the fire and to make recommendations for the future based .on those lessons.. The review group report concludes
".....that the probability of disruptive fires of the magnitude of the Hrowns Ferry event is small and there is .
no need to restrict operation of nuclear E
power plants for public safety." (Quote from p. 3, Report of Special Review Group, Pebruary 28, 1976.)
VX. Joint Committee on Atomic Energy The JCAE investigated the Browns Perry fire and held public hearings on the fire in September 1975. The hearing transcripts are available to the public and are part of the congressional record. (Hearings before the Joint Committee on'tomic Energy, Congress of the United States, Ninety-Fourth Congress, First Session, September 16, 1975.) t
CIIROI'lOLOGX 'F Kl'Y RESTORATXON ACTXVXTXES A 22, 1975, CABLE FIRE EVENTS'XNCE i'2.RCH March 22 Cable, fire at Browns Ferry
/
Began identifying condition of the units, establishing minimum requirements for safe shutdown cooling, and installing temporary cables.
March 23 Established ad hoc committee to conduct official TVA investigation of March 22 fire.
March 26 Began cleanup of plant'ouipment and systems.
I'Iarch 28 Established preliminary plans including six major categories of outage work: (1) cable repair, (2) cleanup, (3) drywell evaluation, (4) retests, (5) modifications, and (6) main-tenance.
Established division of responsibilities for repair and retests among DPP, DED, and DEC.
Appointed DPP Outage Director.
Established a "cleanup group" to prepare pro-cedures and provide technical guidance for plant cleanup and, evaluation of-effects of fire ress. due II Established a Drywell Evaluation Team to deter-mine condition of drywell.
March 31 Established daily telephone conferences between DPP~ DEC~ ahd DED to assist in planning and scheduling of restoration efforts.,
April 3 Designated a DPP Overall Restoration Coordinator and principal coordinators for DPP, DED, and DEC.
Prepared and distributed w-'thin TVA the outline for the overall "Plan for Evaluation, Repair, and 2."
Return to Service of Browns Ferry Units 1 and Advisory Committee on Reactor Safeguards (ACRS) meets on the subject of BFNP fire.
April 7 Courier mail service established between Knoxville, Chattanooga, Browns Ferry, and Muscle Shoals.
. ~
April 12 Heeting held in Chattanooga for final aareement on detailed plan for restoration of units 1 and
- 2. Attendees included the '?anager of Power, Assistant ?!anager of Power, Director of Power Production,and other TVA managerent.
April 13 Detailed restoration plan hand carried to NRC in &washington.
April l5 & 16 First formal meetina with DEC in Bethesda. NRC asked fo additional information before commence-ment of cable rer,oval.
April 17 HRC issued reauixements for removal and restora-tion of fire-affected features and for operation of BFNP units 1 and 2.
April 18 DED issued plan for identification and evalua-tion of affected structures and mechanical equipment.
April 23 & 24 Second meeting with NRC at Browns Ferry (to xeview TVA's safety analysis for the plant configuration for cable removal) .
Hay 2 NRC issues letter orderinq all activities halted.
?hay 2-5 TVA met with NRC to develop restoration technical specifications.
.Nay 3 'VA submits to NRC the safety evaluation for plant configuration for cable removal with fuel remaining in the reactor pressure vessels.
TVA makes decision to remove fuel from units 1 and 2 vessels to speed up cable removal, cable termination, and other work in the reactor vessel which could more easily be done with the fuel out of the reactor vessels.
TVA publishes first schedule for return to service of units 1 and 2--unit 1, December 1, 1975, and unit 2, September 14, 1975. Hain plant activities during month of Pay were' cleanup of fire residue and installation of tenporary cables for safe shutdown'cooling.
Nay 7 Ad hoc committee releases final report of its official investigation.
NRC issues letter permitting resumption of activities.
, ~
Hay 9 NRC issues Safety Evaluation. Report supporting license amendment to chanae technical speci-fications to take into account existing conditions at plant.
?.Tay 29 TVA establishes t'op-level Browns Ferry t!anage-ment Review Committee including the 0lanager of Power, the "Tanager of Engineering Design and Construction, and other affected division directors and principal staff.
Submittal of revised safety analysis report to NRC for cable removal (revision was made to allow removal of fuel from both units 1 and 2).
June 2 NRC issues letter with instructions for converting and retainina damaged cables and cable trays.
June 13 TVA met. with NRC in Bethesda and presented proposed design changes resultina from evaluation of the l'Tarch 22 fire.
NRC issues Safety Evaluation Report supporting license amendment to change technical'peci-fications to permi't defueling units 1 and 2.
Letter also approved plans for removal"of fire-affected features.
June 16 Commencement of removal of units 1 and 2 drywell leads.
Additional engineering manpower for DEC Modifications Group started reporting at site.
June 22 Units. 1 and 2 reactor pressure vessel head removal began in preparation for fuel removal.
NRC X&E issued inspection report with no items of noncompliance.
June 25 Installation of temporary cable's complete for I&E and plant configuration (configuration allowing cable removal).
July 1 TVA met with NRC in Bethesda to describe-design changes and cable splicinq for plant restoration.
Fuel removal began on unit 2 (fuel removal was delayed from NRC approval date of June 13 until July 1 because of final work in getting in the physical plant configuration reauired by the safety analysis report and removal of the ~,
I'
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drywell heads and reactor pressure vessel heads).
July 3 Fuel removal began on unit l.
First penetration fire test conducted at Watts Bar .",uclear Plant tost facilitv.
July 11 TVA r.et ~ith klRC in Pethesda to discuss TVA's administrative controls for fire protection.
July 13 Reactor building cleanup in final stages.
July 17 Fuel removal completed on unit 2.
July 18 Fuel removal completed on unit 1.
July 28 NRC Office of Inspection and Enforcement.
issues its report on the fire (about two inches in thickness).
July '31 Joint Committee on Atomic Energy announces that hearings would be, held on the DFNP fire.
August, 1 First cutting of fire-damaged cables began.
TVA agrees with NRC to repu3ldivisional cables.
August 13 NRC requested additional informational necessary to complete review to permit commencement of restoration work.
August 18 Fire-damaged cable cutting and removal of cable trays and conduit essentially complete.
August 19 and 20 TVA met with ?lRC to discuss restoration plan, especially in the areas of fire protection water systems, fire barriers, and use of polyurethane in penetration seals.
August 28 TVA met with NRC in Bethesda regarding additional NRC design requirements.
NRC issues letter accepting TVA criteria for determining what structural and mechanical components must be replaced- and authorized proceeding with this work. Letter withheld approval of restoration of electrical com-ponents and wiring and approval of installation of fire protection system modifications.
NRC forwards to TVA report, dated July 30, of NRC consultant's analysis of TVA's plans for upgrading plant fire protection.
September 2 TVA answers NRC l6E report and alleged violations.
NRC approves remaining restoration work and the design changes proposed in TVA's recovery plan (through 20th revision).
NRC issues Safety Evaluation Report of restoration activities and fire protection system design chanaes as described in TVA's "Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2" and revisions thereto up to and including revision
- 20. Letter authorized proceeding with restoration.
September 14 Removal of damaged concrete and steel from fire area complete.
September 16 TVA meets with JCAE in ~washington.
September 28 Cleanup of building and mechanical components from fire residue complete.
,October 1 TVA met with NPC in Bethesda to discuss TVA's plans for removal of existing penetration sealant material and.to discuss the new design for penetrations. NRC gave oral approval to begin removal of existing sealant materials.
October 3 All DED drawings for construction of fire protection systems complete and issued.
October 6 Commenced installation of cable tray hangers and cable trays.
Completed liquid-penetrant examination of piping and components which were exposed to fire residue (no stress corrosion problems apparent) .
October 7 Completed installation of cable trays.
October 8 Established weekly DPP', DED, and DEC management meetings at Browns Ferry to plan, organize, and implement all work associated with restoration of units 1 and 2.
October 22
~...
TVA 'met
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with NPC in Ynoxville to discuss (1) zones of influence between electical divisions, (2) extension of the auto water fire extinguishing system, (3) application of fire barriers to protect conduit, (4) desian of the high-pressure water fire protection system, and (5) further tests on electrical sleeve penetrations.
November 3 Commenced splicing of fire-damaged cables and installation of new cables where reauired.
Also began installation of conduit.
TVA submits SAR C and,revised technical speci-fications.
November 9 Commenced installation of fire protection electrical eouipment and piping.
November 12 and 13 TEA met with NRC at Browns Ferry to discuss (1) the fire protection commitments still out-standing with NRC, (2) the problem of physical separation of electrical divisions, and (3) outstanding items reauired by NRC before NRC could prepare a safety evaluation report for.
return to operation of units 1 and 2.
November 26 Final Brooms Ferry penetration test at the !'?atts Bar Nuclear Plant test facility. This was the tenth in a series of tests.
November 30 Commenced termination of cables.
December 18 NRC notifies TVA that they are delayinq review of fire hazards analysis and'ire protection analyses pending review by TVA's fire protection consultant.
NRC approves electrical design changes described in TVA's recovery plan.
December 19 NRC approves revised technical specifications and SAR C.
December 21 Commencement of preoperational retests of unit 2.
December 31 NRC approval to install electrical penetrations according to DED design.
January 9 DED restoration work essentially complete.
January ll Splicing of fire-damaged cables essentially complete.
.January 21 TVA submits to NRC responses to comments from TVA's
fire consultant and other items NRC has required.
January 22 TVA met with ."1RC to discuss TVA's responses to comments from TVA ' fire consultant and other cleanup items TVA had been asked to submit 'inal in preparation for 11PC preparing their safety evaluation for return to operation.
February 23 NRC issues Safety Evaluation Report supporting return to full power operation of BFNP units l and 2.
February 27 ACRS Browns Ferry subcommittee meets with HPC and TVA for detailed discussion of repairs and modifications at BFNP.
February 28 NRC Special Review, Group issues their study of the BFHP fire.
Harch 4 ACRS meets with NRC and TVA to review repairs and modifications at BFNP.
March ll ACRS issues affirmative recommendation regarding restart of BFNP units l and 2.