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Boron +, Iodine +, Gadolinium +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chlorine +, Chloride +, Lead +, Silicon +, Silver +  and Samarium +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.49 +  and 10 CFR 50.62 +

05000289  +  and 00650  +

Reactor Trip +  and Turbine Trip +

NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +  and NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +

ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +, ML18117A397 +  and ML18117A397 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 279 +  and IEEE 279-1971 +

NUREG-1430 +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

ES +, SP +, RT +, CH-1 +, CH-2 +  and ES-022T +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.197 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.95 +

1S-02 +, 1T-02 +, 1D-621 +, 1SA-E2 +, 1SB-E2 +, 1D-621-41-100 +  and 1C-1D-1E +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Turbine +, Safety Parameter Display System +, HVAC +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Control Rod +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

TS-3.15.1 +, TS-4.1.4 +  and TS-6.20.c +

Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Grab sample +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Shift Technical Advisor +, Loss of Offsite Power +, Earthquake +, Commercial Grade +, Fire Protection Program +, Power change +, Core Exit Thermocouple +, Control Room Habitability +  and Basic Component +