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	Issue date	Title	Topic
ML24179A028	26 June 2024	Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a)	Past operability Finite Element Analysis Subsequent License Renewal
ML23192A447	31 July 2023	Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information	Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake
ML22363A392	28 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)	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
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
ML22154A404	3 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 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
ML21277A123	4 October 2021	Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation	Finite Element Analysis License Renewal Power Uprate
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
ML20255A000	24 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	Internal Flooding Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Large early release frequency Earthquake Backfit
ML20112F485	6 May 2020	Staff Assessment of Flooding Focused Evaluation	Safe Shutdown Internal Flooding Hydrostatic FLEX Fukushima Dai-Ichi Flooding Focused Evaluation
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-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-19-041, 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-19-032, 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-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
ML18283B547	10 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 Report	13 September 2018	Extended Power Uprate - Flow Induced Vibration Summary Report	Flow Induced Vibration
ML18079B140	23 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
ML17222A328	5 September 2017	Flood Hazard Mitigation Strategies Assessment	FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment
ML17114A371	20 April 2017	Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule	Power Uprate
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
ML16196A088	5 August 2016	Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation	Ultimate heat sink FLEX Fukushima Dai-Ichi Earthquake
ML16027A059	27 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)	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
NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program	21 September 2015	Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program	Flow Induced Vibration
ML15282A181	21 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 Plan	21 September 2015	Browns Ferry, Units 1, 2, and 3, Startup Test Plan	Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level High Radiation Area Anticipated operational occurrence Probabilistic Risk Assessment Water level shrink Feedwater Heater MELLLA Flow Induced Vibration Power Uprate
ML15282A240	21 September 2015	Startup Test Plan	Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level High Radiation Area Anticipated operational occurrence Probabilistic Risk Assessment Water level shrink Feedwater Heater MELLLA Flow Induced Vibration Power Uprate
NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7	21 September 2015	Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7
ML15282A239	21 September 2015	Flow Induced Vibration Analysis and Monitoring Program	Flow Induced Vibration
NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).	31 August 2015	ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis 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).	31 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 9	31 August 2015	ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9
ML15282A182	31 August 2015	ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9
ML15282A236	31 August 2015	NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.	Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration Power Uprate
ML15282A184	31 August 2015	ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).
ML15282A185	31 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.	31 August 2015	NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.	Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration Power Uprate
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-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-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-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
ML14176A961	24 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	Fire Barrier Coatings Foreign Material Exclusion
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
ML14077A095	30 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	Mission time
ML14077A090	31 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	Mission time
ML13225A541	19 December 2013	Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)	Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Integrated leak rate test Frazil ice Battery sizing Earthquake Hardened vent Power Uprate Manual Operator Action
ML13338A634	18 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	Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Design basis earthquake Integrated leak rate test Frazil ice Battery sizing Earthquake Hardened vent Power Uprate Manual Operator Action
ML13276A064	30 September 2013	ANP-3248NP, Revision 1, Areva RAI Responses for Browns Ferry Atrium 10XM Fuel Transition, Enclosure 3	Shutdown Margin Anticipated operational occurrence Finite Element Analysis Minimum Critical Power Ratio Feedwater Controller Failure Earthquake

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