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ANSI B31.1 +, ANSI B16.5 +, ANSI N45.2.1 +, ANSI B36.19 +, ANSI B36.10 +  and NQA-2-1986 +

IWB-3410 +, IWB-2500 +, IWB-3000 +, IWB-5000 +, IWB-1220 +, IWB-2400 +, IWB-4000 +, IWA-5000 +, IWA-2240 +, IWA-3000 +, IWA-2220 +, IWA-2400 +, IWA-4000 +, IWA-2210 +, IWA-1500 +  and IWA-2230 +

ASME Section XI +, ASME Section III +, ASME Section V +, ASME Section II +  and ASME Section VIII +

Boron +, Cobalt +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Cadmium +, Chloride +, Lead +, Helium +, Lithium +, Mercury +, Manganese +, Chromium +  and Tungsten +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.2#v +  and 10 CFR 50.55a#g +

ASME Code Case N-640 +, ASME Code Case N-20-3 +  and ASME Code Case N-474-2 +

RA-19-0160, Amendment 62 to Final Safety Analysis Report, Drawings, Part 3 of 3 +  and ND-2300 +

Reactor Trip +  and Turbine Trip +

GDC 34 +, GDC 14 +  and GDC 30 +

NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +

ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +, ML19102A106 +  and ML19102A106 +

0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 5.902778e-4 d (0.0142 hours, 8.43254e-5 weeks, 1.94055e-5 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

RT +, CP +  and Emergency Operating Procedure +

Regulatory Guide 1.45 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.43 +, Regulatory Guide 1.14 +, Regulatory Guide 1.31 +, Regulatory Guide 1.83 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.36 +, Regulatory Guide 1.46 +, Regulatory Guide 1.67 +, Regulatory Guide 1.71 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

1A21-SA +, 1B21-SB +, 438B-4 +, 438B-5 +, 438B-6 +, 439B-4 +, 439B-5 +, 439B-6 +, 1RC-V280SB-1 +, 1RC-V285SB-1 +, 1RC-V282SB-1 +, 1RC-V281SA-1 +, 1RC-V284SA-1 +, 1RC-V283SA-1 +, 1RC-280SB-1 +, 1RC1-325SN-1 +, 1RC-V26JSA-1 +, 1RC1-Z92SN-1 +, 5RC1-J24-1 +, 2RC1-289SN-1 +, 2RC-V288SN-1 +, 1RC-VZ81SA-1 +, 2RC1-298SN-1 +  and 5RC12-143-I +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Main Transformer +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

Boric Acid +, Loop seal +, Packing leak +, Ultimate heat sink +, Non-Destructive Examination +, Grab sample +, Safe Shutdown Earthquake +, Weld Overlay +, Post Accident Monitoring +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Incorporated by reference +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, License Renewal +, Power Operated Valves +, Liquid penetrant +, Pressure Boundary Leakage +, Power change +, Flow Induced Vibration +, Unidentified leakage +, Power Uprate +, Measurement Uncertainty Recapture +, Overspeed +, Thermal fatigue +  and Water hammer +

WCAP-12910 +, WCAP-7769 +, WCAP-7735 +, WCAP-9292 +, WCAP-8324-A +, WCAP-8693 +, WCAP-7832-A +  and WCAP-15678 +

WCAP-12910 +, WCAP-7769 +, WCAP-7735 +, WCAP-9292 +, WCAP-8324-A +, WCAP-8693 +, WCAP-7832-A +  and WCAP-15678 +