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ML16021A423 +, ML14148A126 +, ML031400376 +, ML16179A124 +, ML093380283 +, ML20300A225 +, ML20267A146 +, ML20345A318 +, ML21032A119 +, ML22300A117 +  and ML103230151 +

Reactor Trip +  and Turbine Trip +

James Chang +, Coyne K +, NRC/RES/DRA +, Christopher Hunter +, Michelle Kichline +, Enos-Sylla L +  and Pan Q +

ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +, ML24352A019 +  and ML24352A019 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 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)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +

General Electric +  and Westinghouse +

NUREG-2187 +, NUREG/CR-7177 +, NUREG-2156 +, NUREG/IA-0216 +, NUREG-2236 +, NUREG-2256, Notice of Partially Closed Meeting Between the Electric Power Research Institute (EPRI) and the U.S. Nuclear Regulatory Commission (NRC) on NUREG-2256, Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA) +  and NUREG-1953, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom +

AOP +, ES-0.1 +, EOP-3 +, ES-1.3 +, PSP +  and Emergency Operating Procedure +

RIL 2024-17, Research Information Letter (Ril) 2024-17, Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA) Evaluations of Standardized Plant Analysis Risk (SPAR) Model Human Failure Events +  and RIL 2022-13 +

1x10-4 +, 2x10-3 +, 1x10-2 +, 5x10-4 +, 5x10-3 +, 4x10-3 +, 9x10-3 +, 3x10-3 +, 1x10-3 +, 2x10-2 +, 3x10-2 +  and 9x10-2 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Containment Spray +

Mission time +, Probabilistic Risk Assessment +, FLEX +, Significance Determination Process +, Design basis earthquake +, Loss of Offsite Power +  and Hardened vent +