Browse wiki

SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

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

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.120 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 55.59 +, 10 CFR 51.21#51 +, 10 CFR 50.91#a +, 10 CFR 50.91#a6 +  and 10 CFR 50.71#e +

SECY-97 042 +  and SECY-97-042 +

05000321  +, 05000366  +, 00321  +  and 00366  +

Turbine Trip +  and Reactor Trip +

SIL 377 +  and SIL 480 +

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

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 +

ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +, ML20155C660 +  and ML20155C660 +

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)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 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)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

10 CFR 2 +, NEDC-32749P +, HL-5679, Submits Response to RAI Re Extended Power Uprate LAR +, 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-5689, Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients +, 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 +

ML20155C660 +, ML20155C660 +  and ML20155C660 +

TAC:M95087 +, TAC:M87850 +, TAC:M91077 +  and TAC:M95148 +

Regulatory Guide 1.52 +, Regulatory Guide 1.49 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.139 +

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

SECY-97 042 +  and SECY-97-042 +

SR-3.3.4.1.2 +  and SR-3.3.1.1 +

Georgia +, Washington +, Florida +  and Maine +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Shutdown Cooling +, Reactor Recirculation Pump +, 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-3.3.1.1 +, TS-3.4.9 +, TS-5.5.12 +  and TS-3.3.4.1 +

Safe Shutdown +, Shutdown Margin +, Half scram +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, High Energy Line Break +, Feedwater Heater +, Feedwater Controller Failure +, Large early release frequency +, MELLLA +, Loss of Offsite Power +, Earthquake +, Maintenance Rule Program +, Power-Operated Valves +, Fuel cladding +, Power change +, Flow Induced Vibration +, Power Uprate +, Overspeed trip +, Overspeed +, Simmer margin +, Subsequent actuation +, Loss of condenser vacuum +  and Control Room Habitability +