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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

Iron +, Carbon +, Oxygen +, Hydrogen +, Chloride +  and Lead +

BWRVIP-79 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-94 +, BWRVIP-116 +, BWRVIP-86 +, BWRVIP-25 +  and BWRVIP-86-A +

10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.21 +, 10 CFR 54.37 +, 10 CFR 54.4#a2 +, 10 CFR 50.49#f +, 10 CFR 54.37#b +, 10 CFR 54.21#d +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 50.71#e +  and 10 CFR 50.71#e4 +

V. Schiavone +, D. Green +, S. Austin +, W. Rice +, K. Brune +, M. Floyd +, K.J. Polson +  and A. Rogers +

PM 46244 +, PM-46244 +  and PM 36979 +

00259  +, 05000259  +, 05000260  +, 05000296  +, 00260  +  and 00296  +

NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, ML061030027 +, ML11171A037 +, ML071150369 +, ML12083A020 +, ML012123A707 +, ML12090A474 +, ML042520374 +  and IR 05000260/2013008 +

FP-BFN-401 +, FP-BFN-402 +  and SK-B1001 +

NRC/RGN-II/DRS/EB3 +  and Vias S J +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +, IR 05000259/2013009 +...

IR 05000259/2013009 +  and IR 05000260/2013008 +

NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NRC Bulletin 80-11 +  and NRC Bulletin 82-02 +

Information Notice 87-67 +, Information Notice 2013-06, Issues with Air and Water Interaction in Fire Protection Sprinkler Systems +, Information Notice 2012-19, License Renewal Post-Approval Site Inspection Issues +  and Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues +

NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, NUREG-1475 +, NUREG-1813 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

PM 46244 +, PM-46244 +  and PM 36979 +

TAC:MA6787 +  and TAC:MC5373 +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.142 +

RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components +  and RIS 2011-14, Metal Fatigue Analysis Performed by Computer Software +

Tennessee +  and Georgia +

Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Main Transformer +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Control Rod +  and Main Steam +

Tennessee Valley Authority +  and Shea J W +

Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Coatings +, Incorporated by reference +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, Subsequent License Renewal +, Earthquake +, Maintenance Rule Program +, Control of Heavy Loads +, Biofouling +, Fire Protection Program +, Eddy Current Test +, Thermography +  and Owner Activity Report +

WO 112999039 +, WO 112999023 +, WO 111004285 +, WO 112999027 +, WO 112075004 +, WO 112686682 +, WO 113111168 +, WO 113111190 +, WO 113597903 +, WO 113746453 +, WO 10675535 +, WO 111717976 +, WO 112565627 +, WO 112687107 +, WO 113404811 +, WO 111229336 +, WO 111739158 +, WO 114307070 +, WO 114366025 +, WO 114366051 +, WO 114943201 +, WO 114943205 +, WO 112115949 +, WO 112868995 +, WO 114159151 +, WO 10518803 +, WO 10518809 +, WO 10518971 +, WO 110692654 +, WO 112285776 +...