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Meeting Briefing Package/Handouts  and Slides and Viewgraphs

Environmental Protection Agency +  and Federal Emergency Management Agency +

Hydrogen +, Zirconium +  and Lead +

10 CFR 50 Appendix R +  and 10 CFR 50.48#c +

Emergency Preparedness +, Initiating Events +  and Mitigating Systems +

SECY-98-144 +, NRC 2005 +  and SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +

Information Notice 2009-06, Construction-Related Experience with Flood Protection Features +, ML11262A151 +, ML060900005 +, ML112411359 +, ML18249A340 +, ML18135A109 +, ML17089A538 +, ML13038A203 +, ML19162A422 +, ML19210D835 +, ML19260E683 +, ML13099A347 +, ML16270A522 +, ML16298A411 +, IR 05000331/2020003 +, ML16245A871 +, ML19323J370 +, ML080320300 +  and ML1018301010 +

NRC/RES/DRA +  and Nathan Siu +

ML21138A805 +, ML21138A805 +, ML21138A805 +, ML21138A805 +, ML21138A805 +, ML21138A805 +  and ML21138A805 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +  and 3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +

Hurricane Andrew +  and Winter Storm +

IR 05000261/2010009 +  and IR 05000331/2020003 +

Information Notice 2006-18, Significant Loss of Safety-related Electrical Power at Forsmark, Unit 1, in Sweden +  and Information Notice 2009-06, Construction-Related Experience with Flood Protection Features +

NUREG/CR-6738 +, NUREG-1792 +, NUREG/CR-2300 +, NUREG-2150 +, NUREG-2122 +, NUREG/CP-0138 +, NUREG-2201 +, NUREG/CR-3192 +, NUREG/IA-0216 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-0980, Informs of Nomination of Ci Grimes & RT Neville for Congressional Award for Exemplary Svc to Public.Nominating Statements for Each Nominee Encl +, NUREG-1474, Forwards Rept of Staff Actions Resulting from Review of Effect of Hurricane Andrew on Plant,For Review +, NUREG/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts +, 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) +, NUREG-1614, DFC, Vol. 8, Strategic Plan: Fiscal Years 2022-2026 +, NUREG/CR-2497, Forwards Draft Abstract of NUREG/CR-2497, Precursors to Potential Severe Core Damage Accidents:1969-79. Comments Requested by 820220 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and DD-87-21, Directors Decision DD-87-21 Denying Addl Relief Requested by Petitioners That Commission Order Immediate Implementation of Relief Noted in 860506 Petition Re Suspension of Further Licensing of Nuclear Plants in Us +

SECY-98-144 +  and SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +

1E-6 +, 1E-5 +, 1E-4 +, 1E-7 +  and 07-11-520 +

Automatic Scram +  and Manual Scram +

Illinois +, Maryland +, Washington +  and Virginia +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Transformer +, Main Turbine +, Reactor Pressure Vessel +, Circulating Water System +, Core Standby Cooling System +, Emergency Core Cooling System +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, High winds +, Ultimate heat sink +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, Arc flash +, FLEX +, Fukushima Dai-Ichi +, Loss of Offsite Power +, Earthquake +  and Chernobyl +