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Lead +  and Copper +

10 CFR 50 Appendix R +, 10 CFR 50.61 +  and 10 CFR 50.48#c +

SECY-98-144 +, SECY 88-147 +  and SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +

ML18249A340 +, ML18135A109 +, ML14135A076 +, ML072850981 +, ML19022A178 +, ML120480139 +, ML19066A390 +, ML19060A081 +, ML19162A422 +, ML19210D835 +, ML19260E683 +, ML13099A347 +, ML091540534 +, ML12347A049 +, ML19248C656 +, ML19248C655 +, ML12145A470 +, ML16270A522 +, ML16298A411 +, ML063550235 +  and SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +

60 FR 42622 +  and 50 FR 3218 +

NRC/RES/DRA +  and Nathan Siu +

ML20293A370 +, ML20293A370 +, ML20293A370 +, ML20293A370 +, ML20293A370 +  and ML20293A370 +

0.00775 d (0.186 hours, 0.00111 weeks, 2.54935e-4 months)  +, 0.00405 d (0.0972 hours, 5.787037e-4 weeks, 1.33175e-4 months)  +  and 0.00749 d (0.18 hours, 0.00107 weeks, 2.461835e-4 months)  +

Winter Storm +  and Hurricane Andrew +

NEI 91-04 +  and NEI 18-04 +

NUREG-1792 +, NUREG-1806 +, NUREG-1824 +, NUREG/CR-2300 +, NUREG-2150 +, NUREG/BR-0359 +, NUREG/CR-4839 +, NUREG-2122 +, NUREG/CP-0138 +, NUREG/BR-0353 +, NUREG-2156 +, 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/CR-6159 +, NUREG-2110 +, NUREG-1560, Forwards Draft NUREG-1560 Public Workshop Summary Rept from Workshop Held on 970407-09 in Austin,Texas.Rept Summarizes Discussions Held During Workshop & Documents All of Presentation Matl Distributed to Workshop by Attendees +, 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/CR-2934, Forwards NUREG/CR-2934, Review & Evaluation of Indian Point Probabilistic Safety Study, Final Sandia Rept.W/O 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-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +, 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) +  and NUREG-1350, News Release-25-011: Latest Edition of NRC Information Digest Now Available Online +

Sunil Weerakkody +, James Chang +, Tina Ghosh +, Keith Compton +, Nathan Siu +, Shivani Mehta +, Susan Cooper +  and Jing Xing +

SECY-98-144 +, SECY 88-147 +  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-3 +, 1E-7 +, 1x10-6 +, 1x10-4 +, 1x10-5 +, 5x10-5 +, 1x10-3 +  and 3x10-4 +

Maryland +, North Carolina +, Washington +, California +  and Wisconsin +

Steam Generator +, Feedwater +, Service water +, Reactor Pressure Vessel +, Control Rod +  and Containment Spray +

High winds +, Ultimate heat sink +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, B.5.b +, Fukushima Dai-Ichi +, Loss of Offsite Power +, Subsequent License Renewal +, Earthquake +, Chernobyl +  and Overexposure +