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ASME Section XI +  and ASME Section III +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.46a#b +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 50.73#b +, 10 CFR 50.69#d2 +, 10 CFR 50.69#d +, 10 CFR 50.69#e +, 10 CFR 50.69#b +, 10 CFR 50.69#d1 +, 10 CFR 50.69#c +, 10 CFR 50.69#d2i +, 10 CFR 50.54#a +, 10 CFR 50.69#g +, 10 CFR 50.69#f +...

00424  +  and 00352  +

IR 05000424/2016008 +, ML090930246 +, ML061090627 +, ML052900163 +, ML041170141 +, ML17031A269 +, NL-19-1532, Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors +, IR 05000352/2020010 +, NL-20-0670, Response to Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, ML20077J704 +, ML020330051 +, ML22014A084 +, ML22075A287 +, IR 05000277/2023012 +, IR 05000317/2023011 +, ML22167A002 +, NL-19-0850, Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and . +  and NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +

John Hughey +, NRC/NRR/DRA/APOB +, Scarborough T +  and NRC/NRR/DEX +

NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +

ML24267A162 +, ML24267A162 +, ML24267A162 +, ML24267A162 +, ML24267A162 +, ML24267A162 +  and ML24267A162 +

IEEE 279 +  and IEEE 603-1991 +

IP 37060, 10 CFR 50.69 Risk-Informed Category and Treatment of Structures, Systems, and Components +  and IP 71152, Problem Identification and Resolution (PI&R) +

IR 05000317/2023011 +  and IR 05000277/2023013 +

NUREG/CR-6752 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Aron Lewin +, John Hughey +  and Thomas Scarbrough +

Regulatory Guide 1.201 +  and Regulatory Guide 1.174 +

Service water +, Residual Heat Removal +  and Containment Spray +

Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Incorporated by reference +, FLEX +, Earthquake +  and Operational leakage +