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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +  and ANSI N18.1 +

Boron +, Iodine +, Hydrogen +, Xenon +, Lead +  and Samarium +

10 CFR 55 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 2 +, 10 CFR 9 +, 10 CFR 50.34 +, 10 CFR 55.21 +, 10 CFR 55.23 +, 10 CFR 55.31 +, 10 CFR 55.41 +, 10 CFR 55.43 +, 10 CFR 55.45 +, 10 CFR 55.47 +, 10 CFR 55.57 +, 10 CFR 55.59 +, 10 CFR 2.790 +, 10 CFR 45 +, 10 CFR 35.35 +, 10 CFR 55.35 +, 10 CFR 2.103#b2 +, 10 CFR 50.54#k +, 10 CFR 55.45#b +, 10 CFR 55.45#b1 +, 10 CFR 55.31#a5 +, 10 CFR 55.47#a1 +, 10 CFR 55.13#a2 +  and 10 CFR 55.35#a +

NRC-398 +, NRC 398 +  and NRC 15 20 +

Reactor Trip +  and Turbine Trip +

ML20214P296 +, ML20214P296 +, ML20214P296 +, ML20214P296 +, ML20214P296 +  and ML20214P296 +

0.00579 d (0.139 hours, 8.267196e-4 weeks, 1.9025e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

Westinghouse +, General Electric +  and C700 +

NRC-398 +, NRC 398 +  and NRC 15 20 +

NRC Form 396 +, NRC Form 398 +, NRC Form 308 +, NRC Form 157 +  and NRC Form 157s +

NUREG-1123, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors +, NUREG-1122, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, 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 +

ES +, ST +, ES-110 +, ES-201-2 +, ES-202 +, ES-403 +, ES-601-1 +, ES-402 +, ES-201-3 +, ES-401 +, ES-201 +, ES-302 +, ES-403-1 +, ES-203-1 +, ES-301-1 +, ES-301 +, ES-201-1 +, ES-204 +, ES-303-1 +, ES-601 +, ES-303 +, ES-109 +, ES-108-1 +, ES-203 +, ES-104 +, ES-201-6 +, ES-111 +, ES-102 +, ES-502 +, ES-410 +...

Regulatory Guide 1.33 +, Regulatory Guide 1.149 +, Regulatory Guide 1.134 +, Regulatory Guide 1.8 +  and Regulatory Guide 1.114 +

Maryland +, North Carolina +, Washington +, New York +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Electrohydraulic Control +, Rod Worth Minimizer +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

Boric Acid +, Shutdown Margin +, Systematic Assessment of Licensee Performance +, Fuel cladding +  and Power change +