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 Issue dateTitleTopic
ML23346A23917 January 2024Seismic Hazard Report by the Office of Nuclear Reactor Regulation
ML23334A25030 November 2023Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23192A44731 July 2023Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards InformationProbabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
ML23025A07525 January 2023American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle .
ML22363A39228 December 2022Cycle 14 Mellla+ Eigenvalue Tracking Data
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
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
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits30 June 2022Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air SuitsMururoa
ML22154A4043 June 2022Unit 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 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
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
ML21277A1234 October 2021Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw EvaluationFinite Element Analysis
ML21246A29529 September 2021Memo to FileDecommissioning Funding Plan
ML21246A29429 September 2021Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIsDecommissioning Funding Plan
Authorized possession limits
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping4 January 2021Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel PipingNondestructive Examination
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User16 December 202010 CFR 71.95 Report for 3-60B Casks User
ML20329A34524 November 2020Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of AnalysesHydrostatic
EVT-1
Dissimilar Metal Weld
ML20314A0286 November 2020Verbal Relief for Penetration NozzleNondestructive Examination
ML20303A17523 October 2020Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML20255A00024 September 2020Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: SeismicInternal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Large early release frequency
Earthquake
Backfit
ML20112F4856 May 2020Staff Assessment of Flooding Focused EvaluationSafe Shutdown
Internal Flooding
Hydrostatic
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report4 September 2019Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
ML19053A46910 June 2019Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: SeismicSafe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Large early release frequency
License Renewal
Earthquake
Backfit
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-19-041, 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-19-032, 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
ML19007A3307 January 2019Final Report PBAPS Thermal Study
ML18354B06620 December 2018Summary of Monitoring Well Installation DetailsGrab sample
Offsite Dose Calculation Manual
Zebra Mussel
FLEX
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Biofouling
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
ML18283B54710 October 2018Responding 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
RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...28 September 2018Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...High winds
Stroke time
FLEX
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
TORMIS
Battery sizing
Hardened vent
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report13 September 2018Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
RS-18-098, Seismic Probabilistic Risk Assessment Report, 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 ...28 August 2018Seismic Probabilistic Risk Assessment Report, 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 ...Safe Shutdown
Ultimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
Finite Element Analysis
FLEX
Fukushima Dai-Ichi
Large early release frequency
Earthquake
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
ML18093A38230 March 2018Decommissioning Status Report - 2017
ML18079B14023 February 2018Browns 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
RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)5 January 2018Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML17222A3285 September 2017Flood Hazard Mitigation Strategies AssessmentFLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Flood Hazard Mitigation Strategies Assessment
ML17170A07315 June 2017Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233Weak link
ML17114A37120 April 2017Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule
ML17093A69730 March 2017Decommissioning Status Report - 2016
ML19064B22324 February 2017Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station
ML17033B1642 February 2017American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs
ML17027A01527 January 2017ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Aging Management
License Renewal
Coast down
Power Uprate
Overspeed trip
ML17024A03631 December 2016Operating Data Report for 2016Temporary Modification
Biofouling
Power change
Coast down
ML16342B6217 December 2016Results of Visual Inspections of Replacement Steam Dryer
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
ML16196A0885 August 2016Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism ReevaluationUltimate heat sink
FLEX
Fukushima Dai-Ichi
Earthquake
RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal30 June 2016Mitigating Strategies Flood Hazard Assessment (Msfha) SubmittalUltimate heat sink
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation