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ASME Section II +  and ASME Section III +

Boron +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 52 +, 10 CFR 50.2 +, 10 CFR 50.34 +, 10 CFR 50.71 +, 10 CFR 50 Appendix E +, 10 CFR 52.47 +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50 Criterion XI +, 10 CFR 50.43#e +, 10 CFR 50.34#b6iii +, 10 CFR 52.47#a22 +, 10 CFR 52.47#a2 +, 10 CFR 30.53#c +, 10 CFR 52.79#a28 +  and 10 CFR 50 Appendix B Criterion XVII, Quality Assurance Records +

ML15240A044 +, ML15234A007 +, ML15296A568 +, ML16251A336 +, ML15303A502 +, ML16012A550 +, ML16182A597 +, ML16221A563 +, ML15201A768 +, ML15343A502 +, ML15292A501 +, ML16142A015 +, ML16056A002 +, ML15306A018 +, ML16182A588 +, ML15303A462 +, ML16182A554 +, ML15306A358 +, ML16169A374 +, ML15303A547 +, ML16167A540 +, ML1619A348 +, ML16084A989 +, ML15196A596 +, ML16188A428 +, ML16132A380 +, ML16032A106 +, ML16319A333 +, ML16077A291 +, ML15227A013 +...

Turbine Trip +  and Reactor Trip +

NRC/NRO/DNRL/LB2 +  and Roy T +

GDC 15 +, GDC 14 +, GDC 18 +, GDC 30 +, GDC 40 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 1, Quality standards and records +

ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +, ML17023A258 +  and ML17023A258 +

IEEE 387 +, IEEE 387-1995 +  and IEEE 338 +

NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

RAP +  and RT +

Regulatory Guide 1.9 +, Regulatory Guide 1.33 +, Regulatory Guide 1.68.2 +, Regulatory Guide 1.28 +, Regulatory Guide 1.68 +, Regulatory Guide 1.20 +, Regulatory Guide 1.79 +, Regulatory Guide 1.69 +, Regulatory Guide 1.206 +  and Regulatory Guide 1.245 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, HVAC +, Steam Bypass Control System +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Michael Mccoppin +  and NRC/NRO/DNRL/LB2 +

Boric Acid +, Shutdown Margin +, High Radiation Area +, Stroke time +, Anticipated operational occurrence +, Hydrostatic +, Emergency Lighting +, Loss of Offsite Power +, Integrated leak rate test +, Fire Protection Program +, Core Exit Thermocouple +, Unidentified leakage +, Water hammer +  and Gas accumulation +