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Letter  and Updated Final Safety Analysis Report (UFSAR)

ACI-318 +, ACI-304 +, ACI-305 +  and ACI-214 +

ANSI B31.1 +, ANSI B16.5 +, ANSI B31.7 +, ANSI N16.1-1975 +, ANSI C37.20 +, ANSI 101.2-1972 +  and ANSI B31.1.0-1967 +

ASME Section III +  and ASME Section VIII +

Environmental Protection Agency +  and American Society of Civil Engineers +

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Lead +, Aluminum +, Silver +, Tin +  and Platinum +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1301 +, 10 CFR 50.4 +, 10 CFR 72.104 +, 10 CFR 72.210, General License Issued +  and 10 CFR 50.71#e +

05000327  +, 05000328  +, 00327  +, 00328  +, 00553  +, 00554  +, 00315  +  and 00316  +

Turbine Trip +  and Reactor Trip +

Tennessee Valley Authority +  and James Shea +

GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +, ML11364A031 +  and ML11364A031 +

6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.967593e-4 d (0.00472 hours, 2.810847e-5 weeks, 6.4685e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +

Co-60 +, Cs-137 +, U-235 +  and Iodine-131 +

NUREG/CR-3759 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.155 +, Regulatory Guide 1.6 +, Regulatory Guide 1.21 +, Regulatory Guide 1.23 +, Regulatory Guide 1.32 +  and Regulatory Guide 1.113 +

1B-B +, 2B-B +, 1A-A +, 2A-A +, 6A-1 +, 6A-2 +, 6A-3 +, 1A-4 +, 1A-3 +, 15A-1 +, 7A-1 +, 7A-2 +, 7A-4 +, 7A-6 +, 7A-3 +, 7A-5 +, 15A-2 +, 15A-3 +, 15C-1 +, 15C-2 +, 15C-3 +, 15C-4 +, 15C-5 +, 15C-6 +, 15C-7 +, 6A-4 +, 15B-1 +, 15B-2 +, 15B-3 +, 15B-4 +...

Tennessee +, Kansas +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, New Jersey +, New York +, Oklahoma +, Missouri +  and Nebraska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, Shutdown Cooling +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Shield Building +, Circulating Water System +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Moisture Separator Reheater +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.0.3 +, TS-3.6.1.3 +, TS-3.6.3 +, TS-6.8.4.h +  and TS-4.6.1.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Packing leak +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Stroke time +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Coatings +, Tornado Missile Protection +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Deep Dose Equivalent +, Water hammer +, Control Room Habitability +  and Leak Before Break +

WCAP-7950 +  and WCAP-13632 +

WCAP-7950 +  and WCAP-13632 +