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Boron +, Iodine +, Nickel +, Nitrogen +, Carbon +, Hydrogen +, Xenon +, Chlorine +, Molybdenum +, Zirconium +, Lead +, Helium +, Manganese +  and Rhodium +

10 CFR 50.73 +, 10 CFR 50 Appendix A +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50 Appendix I +, 10 CFR 72.210, General License Issued +, 10 CFR 50.48#c +  and 10 CFR 50.71#e +

Initiating Events +  and Emergency Preparedness +

L-81-107, Provides Info Re Results of 800826-30 Test Conducted to Demonstrate Reactor Coolant Pump Seal Design Adequacy During Postulated Station Blackout Conditions.Major Seal Failure Abnormal Leakage Did Not Occur +, L-92-28 +, L-83-573 +, L-84-49 +, L-83-238, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capabilities.Status & Implementation Schedule & List & Description of Reg Guide 1.97,Type a Variables Encl +, L-1110 +, L-1103 +, L-1116 +, L-2227 +, L-2226 +, L-2206 +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +  and L-92-194, Informs That Util Currently Does Not Plan to Replace or Downgrade Qualification of Safety Injection Tank Level & Pressure Instruments,In Response to NRC Re Reg Guide 1.97 +

05000389  +, 00335  +  and 00389  +

ML16063A121 +  and ML13066A546 +

SE-02-2 +, SE-02-1 +, SE-03-2B +, SE-02-4 +, SE-09-3 +, SE-05-1C +, Drawing 1.7-1 +, SE-02-3 +, SE-09-5 +, SE-03-1A +, SE-03-1D +, SE-09-2 +, SE-03-1C +, SE-05-1B +, SE-05-1D +, SE-09-4 +, SE-03-2A +, SE-05-1A +, SE-59-1A1 +, SE-59-1A2 +, SE-59-1B1 +, SE-59-1B2 +, SE-03-1B +, SE-05-1E +, SE-07-5A +  and SE-07-5E +

EC-291 +, EC-283094 +, EC-295 +, EC-284401 +, EC-291393 +, EC-295353 +, EC-293500 +  and EC-296160 +

Reactor Trip +  and Turbine Trip +

GDC 57 +, GDC 55 +, GDC 56 +, GDC 19, Control room +  and GDC 3, Fire protection +

NRC Generic Letter 82-16, NUREG-0737 Technical Specifications +  and NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +

L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +  and L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +

L-81-107, Provides Info Re Results of 800826-30 Test Conducted to Demonstrate Reactor Coolant Pump Seal Design Adequacy During Postulated Station Blackout Conditions.Major Seal Failure Abnormal Leakage Did Not Occur +, L-92-28 +, L-83-573 +, L-84-49 +, L-83-238, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capabilities.Status & Implementation Schedule & List & Description of Reg Guide 1.97,Type a Variables Encl +, L-1110 +, L-1103 +, L-1116 +, L-2227 +, L-2226 +, L-2206 +, L-2022-018, Amendment 27 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant +  and L-92-194, Informs That Util Currently Does Not Plan to Replace or Downgrade Qualification of Safety Injection Tank Level & Pressure Instruments,In Response to NRC Re Reg Guide 1.97 +

Chicago Bridge & Iron +  and Westinghouse +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0660, Safety Evaluation Re Procedures Generation Package for Plant.Nrc Found Program Incomplete in Content.Listed Items Must Be Satisfactorily Addressed Before Program Acceptable +  and NUREG-0843, Ack Receipt of Util Re Periodic Update of Population Data,Noting Inconsistencies Between Fsar,Sser 1 (NUREG-0843) & Tech Specs.Nrc Agrees W/Intent to Conform to Tech Specs +

4.16kV +  and 4.16KV +

ST +, CH +, SP +, CP +, Emergency Operating Procedure +, CH-L-1110 +, CH-001A +, CH-001C +, CH-003A/004A +  and CH-003D/004D +

CAC:MF5495 +  and TAC:64333 +

Regulatory Guide 1.83 +, Regulatory Guide 1.93 +  and Regulatory Guide 1.97 +

8B-1 +, 1A-2A +, 2HVE-8A +, 2HVS-5A +, 2A-5 +, 2HVE-41A +, 2HVS-2A +, 2HVS-2B +, 2HVE-3A +, 2HVE-3B +, 2HVE-9B +, 2HVE-9A +, 2HVS-4A +, 2HVS-4B +, 2L-7A +, 2HVE-6A +, 2HVE-13A +, 2HVE-13B +, 8B-2 +, 2HVE-6B +, 2HVE-21A +, 07-83-10b +, 2B2-TYP +, 07-1B-TYP +, 07-2B-TYP +, 13B-TYP +, 9B-TYP +, 4B-TYP +, 2AB-TYP +, 2B3-TYP +...

Maryland +, Florida +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Shield Building +, Circulating Water System +, Remote shutdown +, Spray Pond +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Anticipated operational occurrence +, Tornado Missile +, Hydrostatic +, Coatings +, Nondestructive Examination +, Incorporated by reference +, Feedwater Heater +, Shift Technical Advisor +, Earthquake +, Pressure Boundary Leakage +, Offsite Circuit +, Backfit +, Power change +, Power Uprate +, Measurement Uncertainty Recapture +, Manual Operator Action +  and Control Room Habitability +