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CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE

Boron +, Iodine +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Aluminum +  and Zinc +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix G +  and 10 CFR 50 Appendix H +

05000321  +, 05000366  +, 00321  +  and 00366  +

Turbine Trip +  and Reactor Trip +

NRC (Affiliation Not Assigned) +  and Olshan L +

GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, 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 +

ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +, ML20237D606 +...

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

10 CFR 2 +, NEDC-32749P +, ML20217F185 +, HL-5660, Forwards Response to Request for Addl Info Re Extended Power Uprate License Amend.Encl 2 Provides Proprietary Page Change to 980706 Submittal for NRC Question 91.Proprietary Encl Withheld,Per 10CFR2.790 +, HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld +, HL-5333, Informs That Second Phase of Power Uprate Addressed to NRC Will Be Made This Summer & Will Request New Licensed Power of 2763 Mwt or 108% of Plant Current Limit of 2558 Mwt. Review of post-LOCA Dose Methodology & Results,Requested +  and HL-5647, Forwards Proprietary & non-proprietary Info in Response to 980327 RAI Re Licensee Extended Power Uprate Amend Request, Submitted on 970808.Calculations SMNH-97-007 & SMNH-97-008, Encl.Proprietary Info Withheld +

General Electric +  and Target Rock +

NRC Bulletin 96-03 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +  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 +

ML20237D606 +, ML20237D606 +  and ML20237D606 +

TAC:M99383 +  and TAC:M99393 +

TAC:M99393 +, TAC:M99383 +, TAC:M87850 +, TAC:M91077 +  and TAC:M95148 +

Regulatory Guide 1.52 +, Regulatory Guide 1.49 +  and Regulatory Guide 1.99 +

NEDC-32749P +, NEDC-32749 +, NEDC-32720P +, NEDC-32424P +, NEDO-32205 +, NEDC-32523P +, NEDO-30832 +, NEDC-32424 +, NEDO-24011P +  and NEDO-22205 +

SR-3.3.4.1.2 +  and SR-3.3.1.1 +

1E-6 +, 1E-7 +  and 1E-S +

Georgia +, Washington +, Alabama +, Florida +  and Maine +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Stator Water Cooling +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Stator Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +...

TS-3.3.4.1 +  and TS-3.3.1.1 +

Southern Nuclear +  and Summer H +

Safe Shutdown +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, Anticipated operational occurrence +, Internal Flooding +, Hydrostatic +, Coatings +, High Energy Line Break +, Feedwater Heater +, Large early release frequency +, MELLLA +, Loss of Offsite Power +, Earthquake +, Maintenance Rule Program +, Power-Operated Valves +, Fuel cladding +, Flow Induced Vibration +, Power Uprate +, Overspeed trip +, Overspeed +, Simmer margin +, Subsequent actuation +  and Loss of condenser vacuum +