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Copper +, Nitrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50 +  and 10 CFR 50.63 +

NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal +, NRC-92-0068, Confirms Util Commitment on Procedure to Ensure That Each Containment Isolation Valve Will Be in Appropriate Position During SBO Event & Provides Schedule for Final Implementation of Procedure +, NRC-92-0017, Confirms That Util Commitments on Station Blackout Rule Implemented.Timed Walkdown (Simulation) of Control Switch Manipulations Required to Energize Safe Shutdown Loads Performed +, NRC-89-0061, Forwards Response to 10CFR50.63 Re Facility Actions in Event of Station Blackout.Response Modeled After NUMARC Generated Generic Response to Station Blackout Rule for Plants Using AC Power +, NRC-21-0002, 3 to Updated Final Safety Analysis Report, Drawing 6M721-2847, System Diagram Control Center Air Conditioning Air Side Reactor Building +  and NRC-91-0086, Provides Response to Recommendations Contained within NRC Station Blackout Safety Evaluation Requested in . Activities Determined Necessary to Meet Station Blackout Rule Completed +

05000341  +, 07200071  +  and 00324  +

GDC 17, Electric power systems +  and GDC 18 +

ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +, ML21055A062 +  and ML21055A062 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +

IEEE 323-1974 +, IEEE 279 +, IEEE 279-1971 +, IEEE 308-1971 +, IEEE 308 +, IEEE-450 +  and IEEE 336-1971 +

NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal +, NRC-92-0068, Confirms Util Commitment on Procedure to Ensure That Each Containment Isolation Valve Will Be in Appropriate Position During SBO Event & Provides Schedule for Final Implementation of Procedure +, NRC-92-0017, Confirms That Util Commitments on Station Blackout Rule Implemented.Timed Walkdown (Simulation) of Control Switch Manipulations Required to Energize Safe Shutdown Loads Performed +, NRC-89-0061, Forwards Response to 10CFR50.63 Re Facility Actions in Event of Station Blackout.Response Modeled After NUMARC Generated Generic Response to Station Blackout Rule for Plants Using AC Power +, NRC-21-0002, 3 to Updated Final Safety Analysis Report, Drawing 6M721-2847, System Diagram Control Center Air Conditioning Air Side Reactor Building +  and NRC-91-0086, Provides Response to Recommendations Contained within NRC Station Blackout Safety Evaluation Requested in . Activities Determined Necessary to Meet Station Blackout Rule Completed +

24V +, 4.16kV +  and 345kV +

ST +  and CP +

TAC:M81254 +, TAC:68545 +  and TAC:81254 +

Regulatory Guide 1.9 +, Regulatory Guide 1.155 +, Regulatory Guide 1.76 +, Regulatory Guide 1.6 +, Regulatory Guide 1.32 +, Regulatory Guide 1.41 +  and Regulatory Guide 1.30 +

2C-1 +, 2A-1 +, 2A-2 +, 38TD8-1 +, 2B-1 +, 2C-2 +, 2B-2 +, 2PA-1 +, 2PB-1 +, 72C-3C +, 72F-5C +, 72C-2D +, 72E-5B +, 1C-R +, 72F-4B +, 72B-2A +, 72C-3A +, 72F-2A +, 72E-5A +, 2IA-1 +, 2IA-2 +, 2IB-1 +, 2IB-2 +  and 64B-C +

Fermi +  and 07200071 +

Georgia +, Virginia +, New York +, Kentucky +, Michigan +, Florida +, Vermont +  and Iowa +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Intermediate Range Monitor +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Ultimate heat sink +, Fire Barrier +, Stroke time +, Tornado Missile +, Temporary Modification +, Emergency Lighting +, Open Phase Condition +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Overspeed trip +, Overspeed +  and GNF3 +