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Letter  and Graphics incl Charts and Tables

ASME Section XI +, ASME Section III +, ASME Section IV +  and ASME Section II +

ARP-LA-71-29 +  and ARP-1-XA-78-51 +

Boron +, Iodine +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +  and Zinc +

10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.49 Appendix R +  and 10 CFR 50 Appendix J#i +

9-8 +, 9-9 +, 25-95 +, 9-29 +  and 9-97 +

05000259  +  and 00259  +

Tennessee Valley Authority +  and Crouch W +

SIL 427 +, SIL 257 +, SIL 382 +, SIL 129 +, SIL 136 +  and SIL 272 +

NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +, ML052280327 +...

ML18036B358 +, ML18032A432 +, ML023600026 +, ML032190680 +, ML051150476 +, L-79-012, Regulatory Framework for Restart +, ML20079D964 +, ML20092J308 +, IR 05000259/1988031 +, 05000296/LER-1986-009-03, :on 860908,Loop I of RHR Sys Declared Inoperable After Damaged Hanger Discovered.Caused by High Vibration in Shutdown Cooling Mode.Hanger Repaired & Design Mod Will Be Performed +, IR 05000259/1993039 +, ML18033A319 +, ML18031B230 +  and 05000260/LER-2005-004, Regarding Primary to Secondary Leakage in Residual Heat Removal Heat Exchanger in Excess of Analyzed Limits +

Foxboro +, General Electric +  and Westronics +

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 +  and 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 +

Nozzle:N2A +, Nozzle:N1A +, Nozzle:N8A +  and Nozzle:N6A +

4kV +  and 24V +

TAC:MC3743 +, TAC:MB7679 +, TAC:MC7208 +, TAC:62264 +  and TAC:62253 +

SR-3.3.1.1 +, SR-3.3.1.1.9 +, SR-3.3.1.1.8 +, SR-3.3.1.1.7 +  and SR-3.1.1.1 +

1A-BFN +, 2C-BFN +, 64D-01 +, 64D-02 +, 64D-03 +, 64D-04 +, 64D-05 +, 64A-06 +, 64A-08 +, 64A-09 +, 64A-10 +, 64A-11 +, 64A-12 +, 64A-13 +, 64A-14 +, 64A-15 +, 64A-16 +, 64A-17 +, 64A-18 +, 64A-25 +, 64B-27 +, 64B-23 +, 64B-28 +, 14A-K11A +, 1C-BFN +, 6A-C +, 5M-C +, 11A-K +, 4X-C +, 1E-BFN +...

Tennessee +, Georgia +, Maryland +, Washington +  and Alabama +

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 +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Stator Cooling Water +, Emergency Equipment Cooling Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Reactor Vessel Water Level +, Fire Barrier +, Tornado Generated Missile +, Seismically rugged +, Local Leak Rate Testing +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Loss of Offsite Power +, Excess Flow Check Valve +, Main Steam Line Radiation Monitor +, Containment high range radiation monitor +, Earthquake +, Power Uprate +, Overspeed trip +  and Loss of condenser vacuum +