Browse wiki

Letter, Technical Specification  and Bases Change

Boron +, Iodine +, Nitrogen +, Carbon +, Oxygen +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50 Appendix J +  and 10 CFR 50 Appendix G +

05000336  +  and 00336  +

Dominion Nuclear Connecticut +  and Grecheck E +

GDC 57 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 1, Quality standards and records +

ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +, ML051610405 +  and ML051610405 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 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)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

AOP +  and Emergency Operating Procedure +

SR-4.8.1.1.2 +, SR-4.7.1.5 +, SR-4.6.5.1.b +, SR-4.6.2.1.1 +, SR-4.5.3.1 +, SR-4.6.1.1.a +, SR-4.6.3.1.a +, SR-4.6.3.1.b +  and SR-4.7.6.1.c +

Manual Scram +  and Automatic Scram +

Connecticut +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Control Room Emergency Ventilation +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Auxiliary Feed Water +  and Containment Spray +

TS-3.0.3 +, TS-3.8.1 +, TS-3.3.1.1 +, TS-3.5.2 +, TS-3.5.3 +, TS-3.0.4 +, TS-3.4.6.2 +, TS-3.8.1.1 +, TS-3.7.1.2 +, TS-3.4.6.1 +, TS-3.0.2 +, TS-4.0.3 +, TS-4.0.4 +, TS-3.4.9.3 +, TS-3.1.3.6 +, TS-3.4.1.3 +, TS-4.0.2 +, TS-2.1 +, TS-3.4.1.6 +  and TS-6.23.d +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Stroke time +, Reserve Station Service Transformer +, Missed surveillance +, Stress corrosion cracking +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Offsite Circuit +, Unidentified leakage +  and Operational convenience +