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-14-208, 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 Water hammer |
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-15-143, 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 Commercial Grade |
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-18-112, 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 Integrated leak rate test Operability Determination Spent Fuel Pool Instrumentation Severe Accident Management Guideline Hardened vent Power Uprate |
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-22-100, 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 Heater Feedwater Controller Failure MELLLA Power Uprate Exclusive Use Affidavit Overspeed trip |
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 Feedwater Heater Stress corrosion cracking Earthquake Fuel cladding Power change Coast down Overspeed trip |
ML023040361 | 19 September 2002 | Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans | |
ML023470308 | 5 December 2002 | Steam Generator Inservice Inspection, Steam Generator Tube Plugging & Repair 30-Day Report | Eddy Current Testing |
ML030650716 | 25 February 2003 | Special Report Per Technical Specification 5.6.6., Problem Investigation Process No.: 0-03-0154, 0-03-0415 | Post Accident Monitoring |
ML032540372 | 31 May 2003 | Pressure-Temperature Curves for TVA Browns Ferry Units 2 and 3 | Shutdown Margin Anticipated operational occurrence Hydrostatic Finite Element Analysis Feedwater Heater License Renewal Power Uprate |
ML032731557 | 29 September 2003 | Technical Letter Report on the Third 10-Year Interval Inservice Inspection Request for Relief Nos. 02-004 and 02-005 for Oconee Nuclear Station, Unit 1 | Hydrostatic VT-2 Incorporated by reference Dissimilar Metal Weld |
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 |
ML041550786 | 29 February 2004 | FRA-ANP Document No. 77-5038568-00, LBB Evaluation of the Core Flood and Low Pressure Injection/Decay Heat Removal Piping Systems for Oconee Unit 3. | Safe Shutdown Earthquake Finite Element Analysis High Energy Line Break Intergranular Stress Corrosion Cracking Stress corrosion cracking License Renewal Pressure Boundary Leakage Pressure boundary leak Unidentified leakage Water hammer |
ML041840114 | 30 April 2004 | Engineering Report GE-NE-0000-0023-1250-1, Rev 0, Browns Ferry, Units 1, 2 and 3, Steam Dryer Analysis for Extended Power Uprate Conditions. | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Intergranular Stress Corrosion Cracking Earthquake Flow Induced Vibration Power Uprate |
ML041840116 | 30 June 2004 | Proposed Technical Specifications Change TS-431, Extended Power Uprate UFSAR Review Matrix, Enclosure 6 | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Ultimate heat sink Non-Destructive Examination Stroke time Anticipated operational occurrence Time to boil Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Nondestructive Examination Temporary Modification Finite Element Analysis High Energy Line Break Significance Determination Process Flow Accelerated Corrosion Feedwater Heater Intergranular Stress Corrosion Cracking Feedwater Controller Failure Large early release frequency MELLLA Stress corrosion cracking Eddy Current Testing Turbine Missile Fuel cladding Fire Protection Program Flow Induced Vibration GOTHIC Power Uprate Failure to Scram Overspeed trip Simmer margin Subsequent actuation Water hammer |
ML041840413 | 30 April 2004 | Engineering Report, Steam Dryer Analysis for Extended Power Uprate Conditions | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Intergranular Stress Corrosion Cracking Earthquake Flow Induced Vibration Power Uprate |
ML042080336 | 2 July 2004 | Response to Request for Additional Information Related to Technical Specifications Change No. TS-405 Alternative Source Term | Safe Shutdown Ultimate heat sink Grab sample Design basis earthquake Earthquake Power Uprate |
ML042380243 | 31 August 2003 | Tennessee Valley Authority System and Analysis Browns Ferry Nuclear Plant, Probabilistic Safety Assessment, Certification and Per Resolution | Safe Shutdown Mission time Finite Element Analysis Large early release frequency Hardened vent Power Uprate Failure to Scram Loss of condenser vacuum |
ML042800052 | 27 May 2004 | Zebra Mussels: Biology, Impacts, and Control, Chapter 13 | Zebra Mussel |
ML042960391 | 15 October 2004 | ORNL/NRC/LTR-04/18, Electronic Archival of the Results of Pressurized Thermal Shock Analyses for Beaver Valley, Oconee, and Palisades Reactor Pressure Vessels Generated with the 04.1 Version of Favor. | License Renewal |
ML043380321 | 15 November 2004 | American Society of Mechanical Engineers Section XI, in Service Inspection Program | Probabilistic Risk Assessment Finite Element Analysis Aging Management Stress corrosion cracking EVT-1 |
ML043550271 | 31 March 2004 | CTRS-Report, Thermal - Hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment. | Loop seal Probabilistic Risk Assessment Earthquake |
ML050560037 | 8 February 2005 | 12-5023272-01, Risk Assessment for Alternate STS End States. | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Mission time Time to boil Probabilistic Risk Assessment Offsite Circuit Manual Operator Action |
ML050770370 | 11 March 2005 | Technical Specifications (TS) Change TS-447, Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision | Safe Shutdown Earthquake High Energy Line Break |
ML051360155 | 12 August 1994 | IPE-PRA Revision 1, Unit 2. | |
ML051360162 | 13 April 1995 | IPE-PRA Revision 1A, Unit 2. | |
ML051640307 | 22 July 2005 | Third 10-Year Interval Inservice Inspection Program Plan Requests for Relief 04-ON-002 and 04-ON-003 | Incorporated by reference Liquid penetrant Dissimilar Metal Weld Scaffolding |
ML060380671 | 2 February 2006 | Response to NRC Request for Additional Information Regarding Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - Submittal of Browns Ferry Unit 1 Seismic and Internal Fires IPEEE Reports | Hot Short Safe Shutdown High winds Ultimate heat sink Probabilistic Risk Assessment Aging Management Significance Determination Process Design basis earthquake License Renewal Earthquake Loss of condenser vacuum |
ML060620548 | 27 February 2006 | Brown Ferry Nuclear EPU Containment Overpressure (COP) Credit Risk Assessment. | |
ML060720273 | 30 November 1992 | a Guide for Environmental and Best Management Practices for Tennessee Valley Authority Transmission Construction and Maintenance Activities | |
ML060720293 | 28 February 2005 | Hydrothermal Modeling of Browns Ferry Nuclear Plant with Units 1, 2, and 3 at Extended Power Uprate | Ultimate heat sink |
ML060720354 | 31 March 2006 | GE-NE-0000-0049-6652-01NP, Rev 0, General Electric Boiling Water Reactor Steam Dryer Scale Model Test Based Fluctuating Load Definition Methodology, March 2006 Benchmark Report | Finite Element Analysis Flow Induced Vibration |
ML060880464 | 21 March 2006 | BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 1 | High winds Mission time Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency Integrated leak rate test Power Uprate Loss of condenser vacuum |
ML061070632 | 30 April 2006 | Units 1, 2, & 3 - GENE-0000-0052-3661-01-NP, Test Report #1, Browns Ferry Nuclear Plant; Unit 1, Scale Model Test. | |
ML061300441 | 31 May 2006 | C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz. | |
ML061300443 | 31 May 2006 | GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions. | Finite Element Analysis Intergranular Stress Corrosion Cracking Earthquake Flow Induced Vibration Power Uprate |
ML062090482 | 10 July 2006 | BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 2 | High winds Mission time Internal Flooding Probabilistic Risk Assessment Large early release frequency Integrated leak rate test Power Uprate Loss of condenser vacuum |
ML062130343 | 31 July 2006 | C.D.I. Report No. 06-11, Revision 2, Hydrodynamic Loads on Browns Ferry Nuclear Unit 1 Steam Dryer to 200 Hz. | |