Browse wiki

Accident Sequence Precursor (ASP) Analysis  and Final

05000373  +  and 05000374  +

IR 05000373/2013009 +, ML051160213 +, ML051950061 +, ML112060305 +, ML13172AA402 +, ML13109A518 +, 05000373/LER-2013-002-01, Regarding Unusual Event Declared Due to Loss of Offsite Power and Dual Unit Reactor Scram +, 05000373/LER-2013-005, Regarding Technical Specification Required Shutdown Due to Pressure Boundary Leakage +, 05000373/LER-2013-003, Regarding Low Pressure Core Spray System Declared Inoperable Due to Faulty Control Switch +, 05000374/LER-2013-001, Regarding Pin Hole Leaks Identified in High Pressure Core Spray Piping +  and 05000374/LER-2013-002, Regarding Manual Reactor Scram Following Trip of Circulating Water Pumps +

NRC/RES/DRA +  and Correia C +

ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +, ML15071A343 +  and ML15071A343 +

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 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)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 0.00837 d (0.201 hours, 0.0012 weeks, 2.751015e-4 months)  +, 0.0208 d (0.5 hours, 0.00298 weeks, 6.849e-4 months)  +  and 0.0246 d (0.59 hours, 0.00351 weeks, 8.08182e-4 months)  +

NUREG/CR-6883 +, NUREG-1792 +  and NUREG/CR-6538 +

David Aird +, Keith Tetter +, Song-Hua Shen +  and Dale Yeilding +

1E51-F076 +, 1E21-F005 +, 1E-6 +, 1E-5 +, 1E-3 +, 2E-5 +, 5E-6 +, 7E-6 +, 1E-2 +, 5E-1 +, 1x10-5 +, 3E-3 +, 7E-3 +, 1E-1-4220 +, 4E-3 +, 2x10-5 +, 4E-1 +  and 1E-1-400S +

Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Fitness for Duty +, Mission time +, Anticipated operational occurrence +, Significance Determination Process +, Loss of Offsite Power +, Pressure Boundary Leakage +  and Through-Wall Leak +