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

ANSI N18.1-1971 +, ANSI N45.2 +, ANSI N45.2-1971 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

Boron +, Iodine +, Uranium +, Krypton +, Carbon +, Sodium +, Hydrogen +, Xenon +, Lead +  and Tin +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 1 +, 10 CFR 73 +, 10 CFR 50.47 +, 10 CFR 50.71 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 51.21 +, 10 CFR 50.54 +, 10 CFR 50.36a +, 10 CFR 50.36a#a2 +, 10 CFR 3 +, 10 CFR 550.4 +, 10 CFR 50.55a +, 10 CFR 50.73#a2 +, 10 CFR 50.73#a +, 10 CFR 50.54#q +, 10 CFR 50.54#p +, 10 CFR 50.54#t +, 10 CFR 50.54#m2iv +...

58 FR 39132 +, 52 FR 3288 +, 59 FR 48180 +, 60 FR 8739 +, 59 FR 17404 +  and 59 FR 19031 +

Zircaloy +  and ZIRLO +

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

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +, NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle +, NRC Generic Letter 93-07, Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans +  and NRC Generic Letter 94-01, Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators +

ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +, ML20080K967 +  and ML20080K967 +

1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

I-131 +  and Iodine-131 +

NUREG-1434 +, NUREG/CR-3539 +, NUREG-1273 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-1366, Amends 170 & 152 to Licenses NPF-9 & NPF-17,respectively, Incorporating Guidance & Recommendations for Diesel Generators Contained in NUREG-1366,GL 93-05,Gl 94-01 & NUREG-1431 +

Regulatory Guide 1.33 +, Regulatory Guide 4.15 +  and Regulatory Guide 1.8 +

NEDO-31400A +  and NEDC-308512 +

SR-3.8.1.3 +, SR-4.1.3.1.2 +, SR-3.8.1 +, SR-3.3.1.1.2 +, SR-3.0.3 +, SR-4.8.1.1.2 +, SR-3.7.5.1 +, SR-3.0.1 +, SR-3.3.8.2.2 +, SR-4.7.1.1 +, SR-3.7.2.2 +, SR-3.0.4 +, SR-3.5.1.2 +, SR-3.8.1.9 +, SR-3.0.2 +, SR-3.4.6.1 +, SR-3.1.3.4 +, SR-3.7.3.3 +, SR-3.6.1.1.1 +, SR-3.5.1.3 +, SR-3.8.4.5 +, SR-3.8.4.4 +, SR-3.6.1.3.3 +, SR-3.8.6.2 +, SR-3.1.5.1 +, SR-3.1.2.1 +, SR-3.1.7.2 +, SR-3.6.1.6.1 +, SR-3.6.1.6.2 +, SR-3.3.1.1.3 +...

Washington +  and Mississippi +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Filtration System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +...

TS-3.6.4.1 +, TS-3.0.3 +, TS-3.7.2 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.7.4 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.7.3 +, TS-3.6.1.1 +, TS-3.10.5 +, TS-3.0.1 +, TS-3.5.2 +, TS-3.8.7 +, TS-3.8.3.1 +, TS-3.9.2 +, TS-3.6 +, TS-3.5.3 +, TS-3.3.6.1 +, TS-5.5.9 +, TS-3.3.1.2 +, TS-3.7.1 +, TS-3.3.2.1 +, TS-3.3.3 +, TS-3.7.7 +, TS-3.8.3 +, TS-3.8.5 +, TS-3.6.1.6 +, TS-3.8.4 +, TS-3.3.7.5 +...

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Stroke time +, Post Accident Monitoring +, Hydrostatic +, Incorporated by reference +, Scram Discharge Volume +, Shift Technical Advisor +, Process Control Program +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Operability Determination +, Spiral reload +, Earthquake +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Offsite Circuit +, Fire Protection Program +, Power change +, Unidentified leakage +, Overspeed +, Operational leakage +, Loss of condenser vacuum +  and Pressure Temperature Limits Report +