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Boron +, Iodine +, Nitrogen +, Sodium +, Hydrogen +, Xenon +, Zirconium +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50.54#f +  and 10 CFR 50.62#c1 +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 12 +, GDC 24 +, GDC 13 +, GDC 22 +, GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +  and NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +

ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +, ML16180A160 +  and ML16180A160 +

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 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

IEEE 344 +, IEEE 323 +, IEEE 279 +  and IEEE 279-1971 +

Westinghouse +  and Foxboro +

NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG/CR-1821, Forwards List of Open Issues from Draft NUREG/CR-1821, Seismic Review of Robert E. Ginna Power Plant as Part of Sep. Addl Info Re Seismic Design Consideration & Component Integrity Should Be Submitted within 30 Days +

TAC:MC4195 +, TAC:M88305 +, TAC:M86848 +  and TAC:M74945 +

Regulatory Guide 1.97 +  and Regulatory Guide 1.32 +

1E-6 +, 1E-11 +, 1E-3 +, 1E-2 +, 1E-1 +, 409A-1 +, 409B-1 +, 410A-1 +, 410B-1 +, 1A-inverte +, 1B-480-V +, 1C-inverte +, 1D-480-V +, 1E-6-100 +, 50F-750F +, 1E-1-1E4 +, 1E-6-1E5 +, 1E3-1E2 +, 1E-5-10 +, 5E-5-50 +, 1E-9-1E-3 +, 1E-12-1E-3 +, 1E-3-1E4 +, 1E-6-1E3 +, 1E-3-1E3 +, 1E-8-10 +  and 1E-6-1 +

Manual Scram +  and Automatic Scram +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Safety Parameter Display System +, HVAC +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Decay Heat Removal +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Post Accident Monitoring +, Met Tower +, Emergency Lighting +, High Energy Line Break +, Loss of Offsite Power +, Earthquake +, Power change +, Core Exit Thermocouple +, Manual Operator Action +, Water hammer +, Control Room Habitability +  and Pressure Temperature Limits Report +

WCAP-7306 +  and WCAP-13864 +

WCAP-7306 +  and WCAP-13864 +