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	Issue date	Title	Topic
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
ML022340441	7 August 2002	Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 1 Restart
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
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
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 Earthquake Flow Induced Vibration
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 Significance Determination Process Feedwater Controller Failure Large early release frequency MELLLA Turbine Missile Fuel cladding Fire Protection Program Flow Induced Vibration GOTHIC Power Uprate Failure to Scram
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 Earthquake Flow Induced Vibration
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
ML042330563	18 March 2004	TVA Systems and Analysis Browns Ferry Nuclear Plant, Probabilistic Safety Assessment Unit 3.Summary Report Rev. 1, January 2003	Internal Flooding Probabilistic Risk Assessment Large early release frequency
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
ML042800052	27 May 2004	Zebra Mussels: Biology, Impacts, and Control, Chapter 13	Zebra Mussel
ML042800065	31 July 2003	Regional Electricity Supply & Demand Projections (Energy Information Agency (EIA)-411). Annual 617 Report of EIA-411 Submittals (Eventually Provided to the U.S. Department of Energy), July 31, 2003
ML043380321	15 November 2004	American Society of Mechanical Engineers Section XI, in Service Inspection Program	Probabilistic Risk Assessment Finite Element Analysis Aging Management EVT-1
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
ML051170242	25 April 2005	(BFN) - Units 2, and 3 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-418 - Request for Extended Power Uprate Operation	Shutdown Margin Reactor Vessel Water Level Stroke time Anticipated operational occurrence Flow Induced Vibration Coast down
ML051170244	25 April 2005	(BFN) - Unit 1 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-431 - Request for Extended Power Uprate Operation	Safe Shutdown Shutdown Margin Reactor Vessel Water Level Stroke time Anticipated operational occurrence Feedwater Controller Failure Earthquake Flow Induced Vibration Coast down
ML051300462	27 April 2005	Technical Specifications Change 438- Response to Request for Additional Information Regarding Excess Flow Check Valve Surveillance Test Frequency	Hydrostatic
ML051360155	12 August 1994	IPE-PRA Revision 1, Unit 2.
ML051360162	13 April 1995	IPE-PRA Revision 1A, Unit 2.
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
ML060380674	26 March 2004	Seismic - Induced Ii/I Spray Evaluations at Browns Ferry Nuclear Plant Unit 1	Safe Shutdown Seismically rugged Design basis earthquake Earthquake
ML060620548	27 February 2006	Brown Ferry Nuclear EPU Containment Overpressure (COP) Credit Risk Assessment.
ML060680593	30 November 1992	Copies of Material Provided to Us Fish and Wildlife Service

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