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Boron +, Iodine +, Nitrogen +, Carbon +, Hydrogen +, Lead +  and Mercury +

10 CFR 2.390 +, 10 CFR 51.30#d +, 10 CFR 52.47#b2 +  and 10 CFR 51.55#a +

Initiating Events +  and Mitigating Systems +

RS-14-134, Revised Schedule for Submitting Facility Security Clearance Renewal +  and RS-14-071, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term +

ML14092A414 +, ML15097A117 +, ML15097A114 +, ML15097A078 +, ML15097A076 +, ML083030246 +, ML082341039 +, BVY 06-009, Applicants Environmental Report Operating License Renewal Stage, Appendix E +, ML16284A016 +  and RS-14-071, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term +

Turbine Trip +  and Reactor Trip +

Bergman T +  and NuScale +

ML20197A417 +, ML20197A417 +, ML20197A417 +, ML20197A417 +, ML20197A417 +, ML20197A417 +, ML20197A417 +, ML20197A417 +  and ML20197A417 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-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 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, Kr-85 +, I-131 +, Nitrogen-16 +, C-14 +  and Mo-99 +

NUREG/BR-0184 +, NUREG/CR-4551 +, NUREG/CR-7009 +, NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station +, NUREG/CR-7161 +, NUREG-7110 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1530, SECY-23-0020: Enclosure 2 - Regulatory Analysis +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, NUREG-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +, NUREG/CR-6613, Exhibit K - NUREG/CR-6613, Vol. 1, SAND97-0594 - Code Manual for MACCS2 - Users Guide +  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 +  and 4.16kV +

RS-14-134, Revised Schedule for Submitting Facility Security Clearance Renewal +  and RS-14-071, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term +

Pennsylvania +, Washington +, Virginia +, Nebraska +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Gas Treatment System +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

Hot Short +, Safe Shutdown +, High winds +, Ultimate heat sink +, Post Accident Monitoring +, Internal Flooding +, Probabilistic Risk Assessment +, B.5.b +, License Renewal +, Hardened vent +, Chernobyl +  and Leak Before Break +