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Nitrogen +, Chloride +, Lead +  and Aluminum +

10 CFR 20 +, 10 CFR 100 +  and 10 CFR 50.73#a2iB +

Barrier Integrity +, Initiating Events +  and Mitigating Systems +

05000293  +  and 00293  +

IR 05000387/2010004 +, ML15147A412 +, ML18158A130 +  and ML18157A040 +

Turbine Trip +  and Reactor Trip +

NRC Region 1 +  and Frank Arner +

ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +, ML18158A130 +  and ML18158A130 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.0223 d (0.536 hours, 0.00319 weeks, 7.34365e-4 months)  +, 0.0185 d (0.444 hours, 0.00265 weeks, 6.088e-4 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 0.0257 d (0.618 hours, 0.00368 weeks, 8.46232e-4 months)  +, 0.0225 d (0.54 hours, 0.00321 weeks, 7.39692e-4 months)  +, 0.00468 d (0.112 hours, 6.679894e-4 weeks, 1.53722e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.0192 d (0.46 hours, 0.00274 weeks, 6.304885e-4 months)  +, 0.0212 d (0.509 hours, 0.00303 weeks, 6.966955e-4 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 0.0175 d (0.421 hours, 0.0025 weeks, 5.764575e-4 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 0.0145 d (0.347 hours, 0.00207 weeks, 4.75625e-4 months)  +, 0.0139 d (0.333 hours, 0.00198 weeks, 4.566e-4 months)  +, 0.0167 d (0.4 hours, 0.00238 weeks, 5.483005e-4 months)  +, 0.0178 d (0.426 hours, 0.00254 weeks, 5.83687e-4 months)  +, 0.0237 d (0.569 hours, 0.00339 weeks, 7.80025e-4 months)  +, 0.015 d (0.361 hours, 0.00215 weeks, 4.9465e-4 months)  +, 0.00926 d (0.222 hours, 0.00132 weeks, 3.044e-4 months)  +, 0.0118 d (0.284 hours, 0.00169 weeks, 3.884905e-4 months)  +, 0.0271 d (0.649 hours, 0.00387 weeks, 8.89609e-4 months)  +, 0.0234 d (0.561 hours, 0.00334 weeks, 7.67849e-4 months)  +, 0.0243 d (0.584 hours, 0.00348 weeks, 7.99811e-4 months)  +, 0.0245 d (0.588 hours, 0.0035 weeks, 8.055185e-4 months)  +, 0.0255 d (0.611 hours, 0.00364 weeks, 8.371e-4 months)  +...

NRC Inspection Manual 0609 +, IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609 Appendix H +, NRC Inspection Manual 0609, Appendix K +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609 Appendix G +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0609/Appendix M, Significance Determination Process Using Qualitative Criteria +

IR 05000219/2016004 +  and IR 05000387/2010004 +

NUREG-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +  and NUREG/CR-7110, Official Exhibit - ENT000457-00-BD01 - NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) +

4kV +, 4.16kV +  and 345kV +

1E-6 +, 1E-7 +, 2E-7 +, 7E-8 +, 5E-9 +, 3E-8 +, 5E-4 +, 5E-2 +  and 7E-2 +

Manual Scram +  and Automatic Scram +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Intermediate Range Monitor +, Steam Jet Air Ejector +, Mechanical Pressure Regulator +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.5.C +, TS-3.7.A +, TS-3.6.D +, TS-4.7.A +, TS-3.5.B +  and TS-3.7.B +

Jimi Yerokun +  and Division of Reactor Safety I +

Safe Shutdown +, Reactor Vessel Water Level +, Loop seal +, High Radiation Area +, Ultimate heat sink +, Mission time +, Weld Overlay +, Water level shrink +, FLEX +, Corrosion bonding +, Significance Determination Process +, Large early release frequency +, Loss of Offsite Power +, Severe Accident Management Guideline +, Preliminary White Finding +, Unidentified leakage +, Unidentified leak +  and Reactive Inspection +