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CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/2131 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 Acc31 March 2014Tennessee 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 AccidSafe 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 Plant28 August 2014Third 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 PlantSpent 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 Pl17 December 2014Response 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 PlanHot 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 2014Expedited 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 2015Application 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 Technical3 June 2015Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify TechnicalStroke time
Fuel cladding
CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information8 July 20153, 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 Report31 July 2015the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure ReportCommercial 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 Revision28 October 2016Proposed 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 Conditions31 May 2018Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionsFLEX
Hardened vent
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report13 September 2018Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report29 November 2018Extended 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 Conditions7 June 2019Tennessee 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 ConditionsFLEX
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 Information13 March 2019Proposed 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 Report16 April 2019Extended Power Uprate - Unit 1 Flow Induced Vibration Summary ReportFlow Induced Vibration
Power Uprate
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report4 September 2019Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User16 December 202010 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 Use27 May 2022to 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 Information18 July 2022Request 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 InformationStroke 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 Interval12 December 2022Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing IntervalSafe 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 2022to 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 05000219/201320131 January 2013Exelon 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 05000237/201320231 January 2013Exelon 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 05000254/201320131 January 2013Exelon 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 05000272/201320131 January 2013Exelon 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 05000277/201320131 January 2013Exelon 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 05000289/201320131 January 2013Exelon 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 05000352/201320131 January 2013Exelon 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 05000373/201320131 January 2013Exelon 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 05000454/201320231 January 2013Exelon 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 05000456/201320231 January 2013Exelon 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 05000461/201320131 January 2013Exelon 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 Estimates15 September 2011Site-Specific Cost EstimatesFuel cladding
Fire Watch
Scaffolding
ML02071070427 February 2002Fitness-for-Duty Program Performance Data for the Period - July 2001 Through December 2001Fitness for Duty
ML0223404417 August 2002Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 1 Restart
ML02248029428 August 2002Fitness-for-Duty Program Performance Data (FFD) for the Period - January 2002 Through June 2002Fitness for Duty
ML0225408874 September 2002Additional Information in Response to Preliminary White Findings Identified in NRC IR 05000277-02-007, 05000278-02-007 Concerning Emergency PreparednessSafe Shutdown
Significance Determination Process
Fuel cladding
Preliminary White Finding
ML02303030115 October 2002TVA Nuclear Strategic Performance Improvement InitiativesPower change
ML02304033819 September 2002Part 2 of 4 - Course Outline for R-304-B and BWR Systems Lesson PlansReactor Vessel Water Level
Loop seal
Hydrostatic
Earthquake
Fuel cladding
Power change
Coast down
ML02304036119 September 2002Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans
ML0235203289 December 2002Response to Request for Additional Information Relating to TS Change No TS-405 - Alternative Source TermPost Accident Monitoring
Seismically rugged
Design basis earthquake
Severe Accident Management Guideline
Earthquake
Maintenance Rule Program
ML03090066619 March 2003Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC
ML03149041422 May 2003Radiation Dose Assessment Report No. 18Offsite Dose Calculation Manual
ML03177034617 June 2003Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC
ML03189047410 July 2003Relaxation 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, SEnforcement Discretion
ML03254037231 May 2003Pressure-Temperature Curves for TVA Browns Ferry Units 2 and 3Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Finite Element Analysis
ML04062044926 February 2004Fitness-for-Duty (FFD) Program Performance Data for July - December 2003Fitness for Duty
ML04121026131 January 2003Tennessee Valley Authority Systems and Analysis Browns Ferry Nuclear Plant Probabilistic Safety Assessment Unit 2 Summary, Revision 1Internal Flooding
Probabilistic Risk Assessment
Large early release frequency