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 Issue dateTitleTopic
ML09314026531 October 2009Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis ReportShutdown Margin
Anticipated operational occurrence
Abnormal operational transient
MELLLA
ML09314026631 August 2009Attachment 15, Browns Ferry Unit 1 - Technical Specification Change 467, EMF-2950(NP), Revision 0, Extended Power Uptate, LOCA Break Spectrum Analysis Report
ML09320026931 October 2009CDI Report No. 09-13NP, Rev. 1, Stress Assessment of Browns Ferry Nuclear Unit 2 Steam Dryer with Steam Dam, Outer Hood and Tie-Bar Reinforcements, Cover Page - Page 62Finite Element Analysis
Liquid penetrant
ML09320027031 October 2009CDI Report No. 09-13NP, Rev. 1, Stress Assessment of Browns Ferry Nuclear Unit 2 Steam Dryer with Steam Dam, Outer Hood and Tie-Bar Reinforcements, Page 62 Through 119
ML09335065330 November 2009ANP-2863(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp.Shutdown Margin
Abnormal operational transient
Feedwater Controller Failure
MELLLA
ML09335065730 November 2009ANP-2877NP, Rev. 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFE1-9 ATRIUM-10 Fuel Assemblies (105% Oltp).Anticipated operational occurrence
Power change
ML09335065830 June 2009ANP-2821(NP), Rev. 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp).Anticipated operational occurrence
ML09335065930 September 2009ANP-2859(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp).Shutdown Margin
ML10048018531 December 2009BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report
ML10116015230 September 2009ANP-2859(NP), Revision 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp).Shutdown Margin
ML10116015430 June 2009ANP-2821(NP), Revision 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp).Anticipated operational occurrence
ML10116015531 March 2010ANP-2863(NP), Revision 1, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp.Safe Shutdown
Shutdown Margin
Anticipated operational occurrence
Abnormal operational transient
Minimum Critical Power Ratio
Feedwater Controller Failure
MELLLA
ML10116016430 November 2009ANP-2877NP, Revision 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFR1-9 ATRIUM-10 Fuel Assemblies (105% Oltp).Anticipated operational occurrence
Power change
ML10116018131 January 2010Gnf 0000-0111-8036-R0-NP, GE14 Fuel Thermal-Mechanical Information.
ML10116018331 March 2010ANP-2908(NP), Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis.Stroke time
MELLLA
Fuel cladding
ML10116018431 January 2010NEDO-32484, Revision 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
ML10116018530 April 2010NEDO-32484, Supplement 1, Revision 0, Browns Ferry Nuclear Plant Unit 1 Supplementary Report Regarding ECCS-LOCA Additional Single Failure Evaluation at Current Licensed Thermal Power.MELLLA
ML10116021131 March 2010ANP-2637, Revision 3, Boiling Water Reactor Licensing Methodology CompendiumShutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
FLEX
Feedwater Controller Failure
Earthquake
Fuel cladding
Power change
Flow Induced Vibration
ML10116051531 October 2009ANP-2638NP, Revision 2, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions.Shutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
ML10195057610 January 2008NRC Talking Points for Browns Ferry CSTHigh Radiation Area
ML11059005528 February 2011ANP-2988NP, Revision 0, Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition Input to TVA for Rais, Enclosure 3Shutdown Margin
Anticipated operational occurrence
Power change
ML11083104131 May 2009Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, Wenck File 2283-01, Enclosure 2Hydrostatic
ML11083104230 April 2005Texas Transportation Institute, DOS K12 Crash Test and Evaluation of the Hesco C-3315 Flood Barrier, April 2005, Enclosure 3
ML11171A03831 December 2010NEDO-33632, Rev. 0, Browns Ferry (Units 1-3), Core Plate Bolt Analysis Stress Analysis Report.Safe Shutdown Earthquake
Operating Basis Earthquake
Finite Element Analysis
ML11286A10830 September 2011ANP-3035(NP), Revision 0, Areva Responses to August 2011 RAIs for Browns Ferry, Unit 1 Fuel Transition - LOCA, Enclosure 3
ML11286A10930 September 2011ANP-3015(NP), Revision 0, Browns Ferry, Units 1, 2 & 3, LOCA Break Spectrum Analysis, Enclosure 6Stroke time
MELLLA
Fuel cladding
ML11307A42030 April 2005Enclosure 2 - Wenck Associates, Inc., Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, May 2009Hydrostatic
ML12180A06230 July 2012Final Browns Ferry Nuclear Plant Units 1, 2, and 3 Accident Sequence Precursor (ASP) AnalysisSafe Shutdown
Mission time
ML12215A00630 September 2011ANP-3015(NP), Revision 0, Browns Ferry Units 1, 2, and 3, LOCA Break Spectrum Analysis.Stroke time
MELLLA
Fuel cladding
ML13002A48626 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report.Safe Shutdown
Unanalyzed Condition
Fire Barrier
Probabilistic Risk Assessment
Operating Basis Earthquake
Arc flash
Design basis earthquake
Large early release frequency
Earthquake
Scaffolding
Power change
ML13002A48826 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report.Safe Shutdown
Unanalyzed Condition
Fire Barrier
Probabilistic Risk Assessment
Operating Basis Earthquake
Design basis earthquake
Large early release frequency
Earthquake
Scaffolding
Downpower
ML13003007416 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report.Safe Shutdown
Unanalyzed Condition
Fire Barrier
Probabilistic Risk Assessment
Operating Basis Earthquake
Squib
Design basis earthquake
Large early release frequency
Earthquake
Scaffolding
Downpower
ML13070A31131 October 2012ANP-3150(NP), Revision 0, Mechanical Design Report for Browns Ferry Atrium 10XM Fuel AssembliesAnticipated operational occurrence
Finite Element Analysis
ML13070A31231 August 2012ANP-3082(NP), Revision 1, Browns Ferry Thermal-Hydraulic Design Report for Atrium 10XM Fuel AssembliesAnticipated operational occurrence
Minimum Critical Power Ratio
ML13070A31331 August 2012ANP-3145(NP), Revision 0, Browns Ferry Unit 2 Cycle 19 LAR Fuel Cycle DesignShutdown Margin
ML13070A31430 November 2012ANP-3167(NP), Revision 0, Browns Ferry Unit 2 Cycle 19 Reload AnalysisSafe Shutdown
Shutdown Margin
Anticipated operational occurrence
Abnormal operational transient
Minimum Critical Power Ratio
Feedwater Controller Failure
MELLLA
ML13070A31531 October 2012ANP-3152(NP), Revision 0, Browns Ferry Unit 1, 2 and 3 LOCA Break Spectrum Analysis for Atrium 10XM FuelStroke time
MELLLA
Fuel cladding
ML13070A31630 November 2012ANP-2637, Revision 4, Boiling Water Reactor Licensing Methodology CompendiumShutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
FLEX
Feedwater Controller Failure
Earthquake
Fuel cladding
Power change
Flow Induced Vibration
ML13070A31730 November 2012ANP-2860NP, Revision 2, Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, Supplement 1NP, Revision 0, Extension for Atrium 10XMShutdown Margin
Fuel cladding
ML13070A31830 November 2012ANP-3170NP, Revision 0, Evaluation of Fuel Conductivity Degradation for Atrium 10XM Fuel for Brown Ferry Units 1, 2 and 3Anticipated operational occurrence
ML13070A31931 October 2012ANP-3159NP, Revision 0, Atrium 10XM Fuel Rod Thermal-Mechanical Evaluation for Browns Ferry Unit 2 Cycle 19 Reload BFE2-19Anticipated operational occurrence
ML13070A32031 August 2012ANP-3148(NP), Revision 0, Browns Ferry Atrium Tm 10XM Equilibrium Cycle Design SummaryShutdown Margin
ML13070A32330 October 201251-9191259-001, Brown Ferry Units Cycle 19 MCPR Safety Limit Analysis with SAFLIM3D MethodologyAnticipated operational occurrence
Minimum Critical Power Ratio
MELLLA
ML13070A32431 August 2012ANP-3140(NP), Revision 0, Brown Ferry Units 1, 2, and 3 Improved K-factor Model for Ace/Atrium 10XM Critical Power CorrelationAnticipated operational occurrence
ML13183A05828 June 2013Tennessee Valley Authority - Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Browns Ferry Nuclear Plant, Unit 2 Seismic WalkdownSafe Shutdown
Unanalyzed Condition
Operating Basis Earthquake
Fukushima Dai-Ichi
Design basis earthquake
Large early release frequency
Earthquake
Scaffolding
ML13225A54119 December 2013Interim 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
Frazil ice
Battery sizing
Earthquake
Hardened vent
ML13227A35317 April 2013Transmittal of Technical Report 3002000078, BWRVIP-271NP: BWR Vessel & Internals Project Testing and Evaluation of the Browns Ferry Unit 2 120 Degrees Capsule
ML13276A06430 September 2013ANP-3248NP, Revision 1, Areva RAI Responses for Browns Ferry Atrium 10XM Fuel Transition, Enclosure 3Shutdown Margin
Anticipated operational occurrence
Finite Element Analysis
Minimum Critical Power Ratio
Feedwater Controller Failure
Earthquake
ML13276A06531 August 2012ANP-3144(NP), Revision 0, Nuclear Fuel Design Report BFE2-19 LAR Atrium 10XM, Enclosure 6Shutdown Margin
ML13276A06631 August 2013ANP-3153(NP), Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for Atrium Tm 1OXM Fuel, Enclosure 8Stroke time
MELLLA
Fuel cladding