Browse wiki

Letter  and Status Report

Nitrogen +  and Hydrogen +

10 CFR 50 Appendix R +, 10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.49#i +  and 10 CFR 50.54#f +

05000259  +  and 00259  +

Tennessee Valley Authority +  and Abney T +

NRC Generic Letter 98-01 +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, 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 83-08, Modification of Vacuum Breakers on Mark I Containments +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, 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 89-16, Installation of a Hardened Wetwell Vent +, 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 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +, ML051390375 +  and ML051390375 +

IR 05000259/2004009 +, IR 05000259/2005006 +  and IR 05000259/2004011 +

ML18037A912 +  and ML20011E780 +

General Electric +  and Westinghouse +

NRC Bulletin 88-04 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 93-03 +, NRC Bulletin 84-02 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 95-02 +, NRC Bulletin 88-10 +, NRC Bulletin 90-01 +, NRC Bulletin 88-03 +, 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-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, 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 +  and 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 +

TAC:MB7679 +, TAC:MA1179 +, TAC:MC3125 +, TAC:MC3186 +, TAC:MA1810 +, TAC:MB7747 +, TAC:56104 +, TAC:00459 +, TAC:62260 +, TAC:M96135 +, TAC:M85254 +, TAC:M82687 +, TAC:M97020 +, TAC:62259 +, TAC:M86882 +, TAC:M93876 +, TAC:M69430 +, TAC:M75635 +, TAC:M94650 +, TAC:73852 +, TAC:60627 +  and TAC:73970 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.99 +

NEDC-30844 +, NEDO-32205 +  and NEDC-30851P +

1A-BFN +, 2C-BFN +, 80K6-825419 +, 1C-BFN +, 6A-C +, 5M-C +, 11A-K +, 4T-C +  and 1E-BFN +

Tennessee +, Georgia +, Maryland +  and Washington +

Reactor Coolant System +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, HVAC +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Coatings +, Emergency Lighting +, Notice of Violation +, Intergranular Stress Corrosion Cracking +, Containment high range radiation monitor +, Hardened vent +, Fire Protection Program +, Power Uprate +  and Water hammer +