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Letter, Inspection Report  and Inspection Report Correspondence

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.62 +, 10 CFR 50 Appendix B Criterion V +  and 10 CFR 50 Appendix B Criterion XVI +

J. McCarthy +, J. Lewis +, W. Crouch +, J. Valente +, M. Bajestani +, R. Baron +, D. Burrell +, P. Byron +, J. Corey +, R. Cutsinger +, B. Hargrove +, K. Hess +, G. Little +, R. Moll +, J. Schlessel +, J. Symonds +, D. Kehoe +, E. Hollins +, S. Kane +, J. Ownby +, Mary Bennett +, Rolonda Jackson +  and Rosalyn Jones +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Physical Protection +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

WO 02-009379 +  and WO 03-008315 +

05000259  +, 00259  +, 00728  +  and 00758  +

Widmann M +  and Reactor Projects Region 2 Branch 6 +

GDC 44 +  and GDC 10 +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, 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 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs +

IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +, IR 05000259/2006007 +...

TI 2515/95 +, TI 2500/20 +  and TI 2515/099 +

IP 71111.17 +, IP 71111.08 +, IP 71111.23 +, IP 37550 +, IP 37551 +, IP 51053 +, IP 50090 +, IP 92701 +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Bulletin 79-14 +, NRC Bulletin 79-12 +, NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NuReg-0661 +, Nureg-1232 +, NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

SR-3.1.6.1 +  and SR-3.3.2.1.2 +

14C-2 +, 47W465-4 +, 5A-F21A +, 5A-F22A +, 5A-F21B +, 5A-F22B +, 1RP203-IIIA +, 1RP206-IIIA +, U1C6R-026 +, U1C6R-028 +  and U1C6R-031 +

Tennessee +  and Washington +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Remote shutdown +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Reactor Water Recirculation +, Control Rod +  and Main Steam +

Tennessee Valley Authority +  and Singer K +

Safe Shutdown +, Grab sample +, Fire Barrier +, Hydrostatic +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Emergency Lighting +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Liquid penetrant +, Power Uprate +, Eddy-Current Testing +  and Seal weld +

WO 02-009379 +  and WO 03-008315 +