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Issue date | Title | Topic | |
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CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 | 31 January 2022 | (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 | |
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 Acc | 31 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 | Safe Shutdown Boric Acid Mission time Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Design basis earthquake Earthquake Seismic Walkdown Report |
CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | 11 December 2014 | (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | Reactor Vessel Water Level Stroke time Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding Power change |
CNL-14-129, Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Browns Ferry Nuclear Plant | 28 August 2014 | Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Browns Ferry Nuclear Plant | Spent Fuel Pool Instrumentation |
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 Pl | 17 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 | Hot Short Safe Shutdown High Radiation Area Mission time Fire Barrier Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Multiple Spurious Operation Incorporated by reference FLEX Thermoset Large early release frequency Severe Accident Management Guideline Fire Protection Program Fire Watch Very Early Warning Fire Detection |
CNL-14-210, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. | 22 December 2014 | Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. | Ultimate heat sink Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Seismically rugged Design basis earthquake Containment Hardened Vent Earthquake Power Operated Valves |
CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | 25 September 2015 | Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA |
CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | 3 June 2015 | Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | Stroke time Fuel cladding |
CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information | 8 July 2015 | 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information | |
CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | 31 July 2015 | the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | Commercial Grade Dedication |
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 Revision | 28 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-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 31 May 2018 | Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | FLEX Hardened vent |
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report | 13 September 2018 | Extended Power Uprate - Flow Induced Vibration Summary Report | Flow Induced Vibration |
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report | 29 November 2018 | Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves 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 Conditions | 7 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 | FLEX Design basis earthquake Spent Fuel Pool Instrumentation Severe Accident Management Guideline Hardened vent |
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 Information | 13 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-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | 16 April 2019 | Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | Flow Induced Vibration Power Uprate |
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report | 4 September 2019 | Extended Power Uprate - Flow Induced Vibration Summary Report | Flow Induced Vibration |
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User | 16 December 2020 | 10 CFR 71.95 Report for 3-60B Casks User | |
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 Use | 27 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-22-066, 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 Information | 18 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 | Stroke time Anticipated operational occurrence Abnormal operational transient |
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 Interval | 12 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 | Safe Shutdown Stroke time Incorporated by reference Scram Discharge Volume Weak link |
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) | 9 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) | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Abnormal operational transient Feedwater Controller Failure MELLLA |
IR 05000219/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000237/2013202 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000254/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000272/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000277/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000289/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000352/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000373/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000454/2013202 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000456/2013202 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
IR 05000461/2013201 | 31 January 2013 | Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee | |
LR-N11-0289, Site-Specific Cost Estimates | 15 September 2011 | Site-Specific Cost Estimates | Fuel cladding Fire Watch Scaffolding |
ML020710704 | 27 February 2002 | Fitness-for-Duty Program Performance Data for the Period - July 2001 Through December 2001 | Fitness for Duty |
ML022340441 | 7 August 2002 | Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 1 Restart | |
ML022480294 | 28 August 2002 | Fitness-for-Duty Program Performance Data (FFD) for the Period - January 2002 Through June 2002 | Fitness for Duty |
ML022540887 | 4 September 2002 | Additional Information in Response to Preliminary White Findings Identified in NRC IR 05000277-02-007, 05000278-02-007 Concerning Emergency Preparedness | Safe Shutdown Significance Determination Process Fuel cladding Preliminary White Finding |
ML023030301 | 15 October 2002 | TVA Nuclear Strategic Performance Improvement Initiatives | Power change |
ML023040338 | 19 September 2002 | Part 2 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans | Reactor Vessel Water Level Loop seal Hydrostatic Earthquake Fuel cladding Power change Coast down |
ML023040361 | 19 September 2002 | Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans | |
ML023520328 | 9 December 2002 | Response to Request for Additional Information Relating to TS Change No TS-405 - Alternative Source Term | Post Accident Monitoring Seismically rugged Design basis earthquake Severe Accident Management Guideline Earthquake Maintenance Rule Program |
ML030900666 | 19 March 2003 | Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC | |
ML031490414 | 22 May 2003 | Radiation Dose Assessment Report No. 18 | Offsite Dose Calculation Manual |
ML031770346 | 17 June 2003 | Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC | |
ML031890474 | 10 July 2003 | Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Browns Ferry, S | Enforcement Discretion |
ML032540372 | 31 May 2003 | Pressure-Temperature Curves for TVA Browns Ferry Units 2 and 3 | Shutdown Margin Anticipated operational occurrence Hydrostatic Finite Element Analysis |
ML040620449 | 26 February 2004 | Fitness-for-Duty (FFD) Program Performance Data for July - December 2003 | Fitness for Duty |
ML041210261 | 31 January 2003 | Tennessee Valley Authority Systems and Analysis Browns Ferry Nuclear Plant Probabilistic Safety Assessment Unit 2 Summary, Revision 1 | Internal Flooding Probabilistic Risk Assessment Large early release frequency |