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 Issue dateTitleTopic
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 .
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-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
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
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
ML17024A03631 December 2016Operating Data Report for 2016Temporary Modification
Biofouling
Power change
Coast down
ML16146A01825 May 2016Special Report 296/2016-001 for Inoperable Post Accident Monitoring (PAM) InstrumentationPost Accident Monitoring
ML16028A29529 January 201610 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration
ML15356A65422 December 2015Submittal of 10 CFR 50.46 30-Day Report
ML15254A54311 September 2015Submittal of 10 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage InstallationFuel 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
ML14356A36211 February 2015Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents)Mission time
Tornado Missile
FLEX
Fukushima Dai-Ichi
Design basis earthquake
Earthquake
Hardened vent
Scaffolding
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-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
ML13177A35216 July 2013Review of Commitment Submittal for License Renewal Regarding the One-Time Inspection Procedure (TAC ME7797, ME7798, and ME7799)Aging Management
ML13144A57622 May 2013Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1)
ML13115A95516 May 2013Final ASP Analysis-Browns Ferry Nuclear Plant, Unit 3, Reactor Trip and Subsequent Loss of Offsite Power Due Failure of Unit Station System Transformer Differential Relay (LER 296/12-004)Fitness for Duty
Mission time
Enforcement Discretion
Significance Determination Process
Offsite Circuit
ML13092A39227 March 2013Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition - Transition Report
ML12356A17630 November 2012Kld TR-505, Rev. 1, Development of Evacuation Time Estimates, Part 6 of 8
ML12335A34027 November 2012Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review ofSafe Shutdown
Unanalyzed Condition
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Operating Basis Earthquake
Fukushima Dai-Ichi
Design basis earthquake
Earthquake
Scaffolding
ML11270006926 September 2011Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 PlantsShutdown Margin
Anticipated operational occurrence
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Channel-control blade interference
Scram Discharge Volume
Earthquake
ML11087125024 March 2011BWR Vessel and Internals Inspection Summaries for Spring 2010 OutagesWeld Overlay
VT-2
License Renewal
Earthquake
EVT-1
Dissimilar Metal Weld
DM weld
Power Uprate
Thermal fatigue
ML11005028722 June 2010Investigation of Tritium Releases to GroundwaterGrab sample
Hydrostatic
ML1019304176 May 2010Tritium Database ReportOffsite Dose Calculation Manual
Hydrostatic
ML12171A18931 March 2010Integrated Resource Plan, Tva'S Environmental & Energy FutureOpen House
ML10088002824 March 2010Day Report of Emergency Core Cooling System Evaluation Model Changes
ML10020101415 January 2010Attachment 2, Browns Ferry, Unit 1 Response to NRC Request for Supplemental Information Regarding Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis MethodologiesShutdown Margin
Reactor Vessel Water Level
Abnormal operational transient
MELLLA
ML10020101615 January 2010Gnf 0000-0111-8036-R0-NP, GE14 Fuel Thermal-Mechanical Information
ML10020101515 January 2010NEDO-32484, Rev. 7, Browns Ferry Nuclear Plant Units 1, 2, and 3 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis.Stroke time
Anticipated operational occurrence
MELLLA
Power change
ML1011602106 October 200951-9121503-002, Engineering Information Record, Responses to NRC Comments Regarding Browns Ferry Unit 1 Proposed Fuel Transition AmendmentMELLLA
ML09246050031 August 2009CDI Report No. 09-25NP, Rev. 0, Stress Assessment of Browns Ferry Nuclear, Unit 1 Steam Dryer to 120% OLTP Power Level, Enclosure 5Finite Element Analysis
Liquid penetrant
ML08346002230 November 2008Enclosure 2 - Browns Ferry, Units 1, 2, & 3 - Technical Specifications Changes TS-418 and TS-431 - Extended Power Uprate - CDI Report 07-11NP, Revision 1, Dynamics of BWR Steam Dryer Components, Non-Proprietary VersionFinite Element Analysis
ML07115036923 April 2007Units 1, 2, & 3 - Submittal of Unit 1 Periodic Inspection Program for License Renewal Procedure in Fulfillment of License Renewal Commitment
ML07103039713 April 2007Status of Unit 1 Restart Issues, Revision 12Safe Shutdown
High winds
Reactor Vessel Water Level
Probabilistic Risk Assessment
Coatings
Operator Manual Action
Emergency Lighting
License Renewal
Hardened vent
Fire Protection Program
Power Uprate
ML06353003714 December 2006Core Operating Limits Report for Cycle 7 OperationShutdown Margin
ML0631004421 November 2006Supplemental Information - Changes to Instrumentation Surveillance Test Intervals and Allowed Out-of-Service TimesReactor Vessel Water Level
Half scram
Stroke time
Scram Discharge Volume
ML06220027726 July 2006Technical Specifications (TS) Changes TS-431 & TS-418 - Extended Power Uprate (EPU) - Response to Round 7 Requests for Additional InformationVT-2
Finite Element Analysis
Flow Induced Vibration
ML06167015112 June 2006Extended Power Uprate (EPU) - Reload Analysis ReportShutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
Feedwater Controller Failure
MELLLA
Fuel cladding
ML06251038531 May 2006Enclosure 3, Browns Ferry, Units 1, 2 & 3 - CDI Report No. 05-28P, Rev 1, Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements.
ML06145039715 May 20060043-8325-SRLR, Revision 1, Supplemental Reload Licensing Report for Brown Ferry 1, Reload 6 Cycle 7, Pages 123 Through EndSafety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Feedwater Controller Failure
MELLLA
ML06145039515 May 20060043-8325-SRLR, Revision 1, Supplemental Reload Licensing Report for Brown Ferry 1, Reload 6 Cycle 7, Cover Through Page 122Shutdown Margin
Anticipated operational occurrence
MELLLA
ML06088041321 March 2006EPU Containment Overpressure Credit Risk Assessment, Rev. 1High winds
Mission time
Internal Flooding
Probabilistic Risk Assessment
Coatings
Large early release frequency
ML0607204301 March 2006March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations.Hot Short
Safe Shutdown
Significance Determination Process
Thermoset
Exemption Request
Fire Protection Program
Backfit
ML05130046227 April 2005Technical Specifications Change 438- Response to Request for Additional Information Regarding Excess Flow Check Valve Surveillance Test FrequencyHydrostatic
ML05117024225 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 OperationShutdown Margin
Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Flow Induced Vibration
Coast down
ML05117024425 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 OperationSafe Shutdown
Shutdown Margin
Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Feedwater Controller Failure
Earthquake
Flow Induced Vibration
Coast down
ML06068059628 February 2005Hydrothermal Modeling of Browns Ferry with Units 1, 2, and 3 at Extended Power UprateUltimate heat sink
ML06038067426 March 2004Seismic - Induced Ii/I Spray Evaluations at Browns Ferry Nuclear Plant Unit 1Safe Shutdown
Seismically rugged
Design basis earthquake
Earthquake
ML04233056318 March 2004TVA Systems and Analysis Browns Ferry Nuclear Plant, Probabilistic Safety Assessment Unit 3.Summary Report Rev. 1, January 2003Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
ML04062044926 February 2004Fitness-for-Duty (FFD) Program Performance Data for July - December 2003Fitness for Duty