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Issue date | Title | Topic | |
---|---|---|---|
ML093140265 | 31 October 2009 | Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis Report | Shutdown Margin Anticipated operational occurrence Abnormal operational transient MELLLA |
ML093140266 | 31 August 2009 | Attachment 15, Browns Ferry Unit 1 - Technical Specification Change 467, EMF-2950(NP), Revision 0, Extended Power Uptate, LOCA Break Spectrum Analysis Report | |
ML093200269 | 31 October 2009 | CDI 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 62 | Finite Element Analysis Liquid penetrant |
ML093200270 | 31 October 2009 | CDI 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 | |
ML093350653 | 30 November 2009 | ANP-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 |
ML093350657 | 30 November 2009 | ANP-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 |
ML093350658 | 30 June 2009 | ANP-2821(NP), Rev. 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp). | Anticipated operational occurrence |
ML093350659 | 30 September 2009 | ANP-2859(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp). | Shutdown Margin |
ML100480185 | 31 December 2009 | BWRVIP-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 | |
ML101160152 | 30 September 2009 | ANP-2859(NP), Revision 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp). | Shutdown Margin |
ML101160154 | 30 June 2009 | ANP-2821(NP), Revision 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp). | Anticipated operational occurrence |
ML101160155 | 31 March 2010 | ANP-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 |
ML101160164 | 30 November 2009 | ANP-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 |
ML101160181 | 31 January 2010 | Gnf 0000-0111-8036-R0-NP, GE14 Fuel Thermal-Mechanical Information. | |
ML101160183 | 31 March 2010 | ANP-2908(NP), Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis. | Stroke time MELLLA Fuel cladding |
ML101160184 | 31 January 2010 | NEDO-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 |
ML101160185 | 30 April 2010 | NEDO-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 |
ML101160211 | 31 March 2010 | ANP-2637, Revision 3, Boiling Water Reactor Licensing Methodology Compendium | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence FLEX Feedwater Controller Failure Earthquake Fuel cladding Power change Flow Induced Vibration |
ML101160515 | 31 October 2009 | ANP-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 |
ML101950576 | 10 January 2008 | NRC Talking Points for Browns Ferry CST | High Radiation Area |
ML110590055 | 28 February 2011 | ANP-2988NP, Revision 0, Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition Input to TVA for Rais, Enclosure 3 | Shutdown Margin Anticipated operational occurrence Power change |
ML110831041 | 31 May 2009 | Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, Wenck File 2283-01, Enclosure 2 | Hydrostatic |
ML110831042 | 30 April 2005 | Texas Transportation Institute, DOS K12 Crash Test and Evaluation of the Hesco C-3315 Flood Barrier, April 2005, Enclosure 3 | |
ML11171A038 | 31 December 2010 | NEDO-33632, Rev. 0, Browns Ferry (Units 1-3), Core Plate Bolt Analysis Stress Analysis Report. | Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis |
ML11286A108 | 30 September 2011 | ANP-3035(NP), Revision 0, Areva Responses to August 2011 RAIs for Browns Ferry, Unit 1 Fuel Transition - LOCA, Enclosure 3 | |
ML11286A109 | 30 September 2011 | ANP-3015(NP), Revision 0, Browns Ferry, Units 1, 2 & 3, LOCA Break Spectrum Analysis, Enclosure 6 | Stroke time MELLLA Fuel cladding |
ML11307A420 | 30 April 2005 | Enclosure 2 - Wenck Associates, Inc., Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, May 2009 | Hydrostatic |
ML12180A062 | 30 July 2012 | Final Browns Ferry Nuclear Plant Units 1, 2, and 3 Accident Sequence Precursor (ASP) Analysis | Safe Shutdown Mission time |
ML12215A006 | 30 September 2011 | ANP-3015(NP), Revision 0, Browns Ferry Units 1, 2, and 3, LOCA Break Spectrum Analysis. | Stroke time MELLLA Fuel cladding |
ML13002A486 | 26 November 2012 | Fukushima 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 |
ML13002A488 | 26 November 2012 | Fukushima 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 |
ML130030074 | 16 November 2012 | Fukushima 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 |
ML13070A311 | 31 October 2012 | ANP-3150(NP), Revision 0, Mechanical Design Report for Browns Ferry Atrium 10XM Fuel Assemblies | Anticipated operational occurrence Finite Element Analysis |
ML13070A312 | 31 August 2012 | ANP-3082(NP), Revision 1, Browns Ferry Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies | Anticipated operational occurrence Minimum Critical Power Ratio |
ML13070A313 | 31 August 2012 | ANP-3145(NP), Revision 0, Browns Ferry Unit 2 Cycle 19 LAR Fuel Cycle Design | Shutdown Margin |
ML13070A314 | 30 November 2012 | ANP-3167(NP), Revision 0, Browns Ferry Unit 2 Cycle 19 Reload Analysis | Safe Shutdown Shutdown Margin Anticipated operational occurrence Abnormal operational transient Minimum Critical Power Ratio Feedwater Controller Failure MELLLA |
ML13070A315 | 31 October 2012 | ANP-3152(NP), Revision 0, Browns Ferry Unit 1, 2 and 3 LOCA Break Spectrum Analysis for Atrium 10XM Fuel | Stroke time MELLLA Fuel cladding |
ML13070A316 | 30 November 2012 | ANP-2637, Revision 4, Boiling Water Reactor Licensing Methodology Compendium | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence FLEX Feedwater Controller Failure Earthquake Fuel cladding Power change Flow Induced Vibration |
ML13070A317 | 30 November 2012 | ANP-2860NP, Revision 2, Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, Supplement 1NP, Revision 0, Extension for Atrium 10XM | Shutdown Margin Fuel cladding |
ML13070A318 | 30 November 2012 | ANP-3170NP, Revision 0, Evaluation of Fuel Conductivity Degradation for Atrium 10XM Fuel for Brown Ferry Units 1, 2 and 3 | Anticipated operational occurrence |
ML13070A319 | 31 October 2012 | ANP-3159NP, Revision 0, Atrium 10XM Fuel Rod Thermal-Mechanical Evaluation for Browns Ferry Unit 2 Cycle 19 Reload BFE2-19 | Anticipated operational occurrence |
ML13070A320 | 31 August 2012 | ANP-3148(NP), Revision 0, Browns Ferry Atrium Tm 10XM Equilibrium Cycle Design Summary | Shutdown Margin |
ML13070A323 | 30 October 2012 | 51-9191259-001, Brown Ferry Units Cycle 19 MCPR Safety Limit Analysis with SAFLIM3D Methodology | Anticipated operational occurrence Minimum Critical Power Ratio MELLLA |
ML13070A324 | 31 August 2012 | ANP-3140(NP), Revision 0, Brown Ferry Units 1, 2, and 3 Improved K-factor Model for Ace/Atrium 10XM Critical Power Correlation | Anticipated operational occurrence |
ML13183A058 | 28 June 2013 | Tennessee 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 Walkdown | Safe Shutdown Unanalyzed Condition Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Large early release frequency Earthquake Scaffolding |
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 Frazil ice Battery sizing Earthquake Hardened vent |
ML13227A353 | 17 April 2013 | Transmittal of Technical Report 3002000078, BWRVIP-271NP: BWR Vessel & Internals Project Testing and Evaluation of the Browns Ferry Unit 2 120 Degrees Capsule | |
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 |
ML13276A065 | 31 August 2012 | ANP-3144(NP), Revision 0, Nuclear Fuel Design Report BFE2-19 LAR Atrium 10XM, Enclosure 6 | Shutdown Margin |
ML13276A066 | 31 August 2013 | ANP-3153(NP), Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for Atrium Tm 1OXM Fuel, Enclosure 8 | Stroke time MELLLA Fuel cladding |