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COMMISSION PAPER  and TEXT-SAFETY REPORT

ANSI N45.4-1972 +, ANSI 45.4-1972 +  and ANSI 45.4 1972 +

Boron +, Iodine +, Oxygen +, Sodium +, Hydrogen +, Zirconium +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 52 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.54#o +, 10 CFR 50.34#f +  and 10 CFR 50.34#g +

SECY 86-76 +, SECY 89-12 +  and SECY-89-228 +

Reactor Trip +  and Turbine Trip +

Taylor J +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +

GDC 38 +, GDC 16 +, GDC 55 +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +

ML20011C620 +, ML20011C620 +, ML20011C620 +, ML20011C620 +, ML20011C620 +, ML20011C620 +  and ML20011C620 +

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)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

Westinghouse +  and General Electric +

NUREG/CR-4551 +, NUREG/CR-3539 +, NUREG-1273 +, NUREG-1197 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

TOP-LEVEL +  and TOP +

Regulatory Guide 1.4 +, Regulatory Guide 1.155 +, Regulatory Guide 1.3 +, Regulatory Guide 1.7 +, Regulatory Guide 1.106 +  and Regulatory Guide 1.141 +

SECY 86-76 +, SECY 89-12 +  and SECY-89-228 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

Safe Shutdown +, Fire Barrier +, Probabilistic Risk Assessment +, Squib +, Integrated leak rate test +, Earthquake +, Power-Operated Valves +, Fuel cladding +, Backfit +, Fatality +, Unidentified leakage +, Overspeed trip +, Overspeed +, Control Room Habitability +  and Leak-Before-Break +