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Technical Specification, Bases Change  and Letter type:

ANSI/ANS 56.8-1994 +  and ANSI/ANS-56.8 1994 +

IWB-5000 +  and IWA-5000 +

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Uranium +, Carbon +, Zirconium +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +  and 10 CFR 50 Appendix I +

05000302  +  and 00302  +

Turbine Trip +  and Reactor Trip +

Florida Power Corp +  and Bernhoft S +

GDC 57 +, GDC 30 +, GDC 17, Electric power systems +  and GDC 19, Control room +

3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +, 3F0502-06, Technical Specifications Bases Control Program +  and 3F0502-06, Technical Specifications Bases Control Program +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 9.722222e-4 d (0.0233 hours, 1.388889e-4 weeks, 3.1962e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

IEEE 485 +, IEEE 308 +, IEEE 485-1983 +  and IEEE-450 +

NUREG-0677 +, 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-1366, Amends 170 & 152 to Licenses NPF-9 & NPF-17,respectively, Incorporating Guidance & Recommendations for Diesel Generators Contained in NUREG-1366,GL 93-05,Gl 94-01 & NUREG-1431 +

ES +, SP-17-LII +, SP-18-LI1 +, SP-17-LIR +, SP-22-LI1 +, SP-21-LIR +, SP-25-LI2 +, SP-26-LI2 +, SP-29-LI2 +, SP-30-LI2 +, SP-17-LI2 +, SP-21-LI2 +, SP-22-LI2 +, SP-21-LI +  and SP-18-L12 +

Regulatory Guide 1.97 +, Regulatory Guide 1.27 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.93 +, Regulatory Guide 1.6 +, Regulatory Guide 1.32 +  and Regulatory Guide 1.129 +

SR-3.7.12.4 +, SR-3.7.11.1 +, SR-3.4.13.1 +, SR-3.6.1.1 +, SR-3.6.6.3 +, SR-3.7.12.2 +, SR-3.0.4 +, SR-3.7.4.1 +, SR-3.7.11.2 +, SR-3.6.6.6 +, SR-3.6.6.2 +, SR-3.9.2.1 +, SR-3.6.6.7 +, SR-3.3.5.4 +, SR-3.4.15.2 +, SR-3.8.4.7 +, SR-3.9.1.1 +, SR-3.6.3.5 +, SR-3.7.12.1 +, SR-3.6.3.7 +, SR-3.6.3.6 +, SR-3.7.2.1 +, SR-3.8.4.8 +, SR-3.7.15.1 +, SR-3.6.5.1 +, SR-3.6.6.5 +, SR-3.3.7.1 +, SR-3.7.16.1 +, SR-3.4.15.1 +, SR-3.4.15.3 +...

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Main Turbine +, Control Room Emergency Ventilation +, Circulating Water System +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Emergency Feedwater Initiation and Control +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.14 +, TS-3.0.3 +, TS-3.8.1 +, TS-3.7.4 +, TS-3.3.3 +, TS-3.8.5 +, TS-3.0.4 +, TS-3.6.5 +, TS-3.6.3 +, TS-3.8.2 +, TS-3.6.1 +, TS-3.7.5 +, TS-3.2.3 +, TS-3.3.2 +, TS-3.9.3 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.3.4 +, TS-3.3.1 +, TS-3.4.6 +, TS-3.6.4 +, TS-3.8.9 +, TS-3.4.7 +, TS-3.1.5 +, TS-3.1.4 +, TS-3.2.2 +, TS-3.9.5 +, TS-3.0.6 +, TS-3.7.13 +, TS-3.8.10 +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Time of Discovery +, Offsite Dose Calculation Manual +, Stroke time +, Anticipated operational occurrence +, Post Accident Monitoring +, Stress corrosion cracking +, Loss of Offsite Power +, Control of Heavy Loads +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, Unidentified leakage +, Operational leakage +  and Control Room Habitability +