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ASME Section XI +, ASME Section III +  and ASME Section VI +

Boron +, Uranium +, Nitrogen +, Oxygen +, Sodium +, Xenon +, Zirconium +, Lead +  and Samarium +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 50.62 +, 10 CFR 100.11 +  and 10 CFR 50.65#a4 +

05000277  +  and 05000278  +

Turbine Trip +  and Reactor Trip +

Exelon +  and Gallagher M +

ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +, ML031250309 +  and ML031250309 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-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)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

NUREG-0562, Advises That NUREG-0562 Fuel Failure Criteria Not Approved as Basis for Licensing.Use of Criteria Should Be Discontinued to Eliminate Licensing Delays.List of Plants Applying Criteria Requested +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

NEDO-21778 +, NEDC-32410P +, NEDO-21231 +, NEDC-32183P +, NEDC-32162P +, NEDC-32163P +, NEDO-24154 +, NEDO-30130 +, NEDC-32428P +, NEDO-24229 +, NEDO-32368 +  and NEDC-32162 +

SR-3.3.1.1.2 +, SR-3.0.3 +, SR-3.0.1 +, SR-3.2.3.1 +, SR-3.0.4 +, SR-3.2.2.1 +, SR-3.3.1.1 +, SR-3.0.2 +, SR-3.3.2.1.2 +, SR-3.3.2.1.1 +, SR-3.1.7.4 +, SR-3.1.8.1 +, SR-3.1.4.2 +, SR-3.1.3.4 +, SR-3.3.1.1.1 +, SR-3.1.7.5 +, SR-3.1.5.1 +, SR-3.1.2.1 +, SR-3.1.7.2 +, SR-3.3.1.2.2 +, SR-3.1.4.4 +, SR-3.1.4.1 +, SR-3.3.1.1.3 +, SR-3.1.7.3 +, SR-3.3.1.1.9 +, SR-3.1.3.2 +, SR-3.3.1.1.8 +, SR-3.3.1.1.7 +, SR-3.1.7.7 +, SR-3.1.1.1 +...

Manual Scram +  and Automatic Scram +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Control Room Emergency Ventilation +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Main Condenser +, Control Rod +, Main Steam +  and Main Turbine Bypass System +

TS-3.0.3 +, TS-3.3.1.1 +, TS-3.0.1 +, TS-3.9.2 +, TS-3.3.2.1 +, TS-3.7.7 +, TS-3.0.4 +, TS-3.4.9 +, TS-3.2.3 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.1.3 +, TS-3.1.5 +, TS-3.1.1 +, TS-3.1.4 +, TS-3.2.2 +, TS-3.9.5 +, TS-3.0.2 +, TS-3.0.5 +, TS-3.0.6 +, TS-3.9.1 +, TS-3.2.1 +, TS-3.1.8 +, TS-3.10.1 +, TS-5.5.10.d +, TS-3.0.7 +, TS-3.10.7 +  and TS-3.10.6 +

Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Post Accident Monitoring +, Hydrostatic +, Squib +, Missed surveillance +, Abnormal operational transient +, Scram Discharge Volume +, Feedwater Controller Failure +, Overtravel +, Power Operated Valves +, Fuel cladding +, Power change +, Coast down +, Operational leakage +  and Operational convenience +