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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

Iodine +, Nitrogen +, Carbon +, Sodium +  and Hydrogen +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.55A#G +, 10 CFR 50.49#i +, 10 CFR 50.54#f +, 10 CFR 55.45#b +, 10 CFR 55.45#b2iii +, 10 CFR 55.45#B +  and 10 CFR 50.55a#g +

05000296  +  and 00259  +

Tennessee Valley Authority +  and Machon R +

NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, 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 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, 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 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, 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 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +, NRC Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs +, NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54 +, NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, 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 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +, ML18038B556 +  and ML18038B556 +

NRC Bulletin 88-04 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 93-03 +, NRC Bulletin 84-02 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 95-02 +, NRC Bulletin 90-01 +, NRC Bulletin 88-03 +, NRC Bulletin 79-12 +, NRC Bulletin 83-08 +, NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +, NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

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-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 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.99 +

NEDC-30844 +, NEDC-30851P +, NEDC-30844A +  and NEDC-30851Pg +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection 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 +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +  and Control Rod +

Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Fire Barrier +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, Notice of Violation +, Flow Accelerated Corrosion +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Commercial Grade +, Control of Heavy Loads +, Hardened vent +, Fire Watch +  and Control Room Habitability +