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Technical Specification, Bases Change  and Letter type:

ASME Section XI +  and ASME Section I +

Boron +, Iodine +, Xenon +  and Lead +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 Appendix J +  and 10 CFR 50.65#a4 +

05000302  +  and 00302  +

Progress Energy Florida +  and Infanger P +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +  and NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +

3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +, 3F0506-05, 2005 Technical Specifications Bases Control Program +  and 3F0506-05, 2005 Technical Specifications Bases Control Program +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 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)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 9.722222e-4 d (0.0233 hours, 1.388889e-4 weeks, 3.1962e-5 months)  +

ES +, SP-25-LI1 +, SP-26-LI1 +, SP-25-LIR +, SP-30-LI1 +, SP-29-LI1 +, SP-29-LIR +  and CP-253 +

Regulatory Guide 1.97 +, Regulatory Guide 1.137 +, Regulatory Guide 1.93 +  and Regulatory Guide 1.182 +

SR-3.4.4.1 +, SR-3.8.1.1 +, SR-3.0.3 +, SR-3.0.1 +, SR-3.8.3.2 +, SR-3.4.10.1 +, SR-3.2.3.1 +, SR-3.8.3.4 +, SR-3.5.2.1 +, SR-3.0.4 +, SR-3.8.1.2 +, SR-3.5.3.1 +, SR-3.7.8.1 +, SR-3.6.6.6 +, SR-3.2.2.1 +, SR-3.0.2 +, SR-3.6.6.7 +, SR-3.2.5.1 +, SR-3.6.3.5 +, SR-3.2.1.3 +, SR-3.8.3.1 +, SR-3.8.3.3 +, SR-3.6.3.7 +, SR-3.8.9.1 +, SR-3.6.3.6 +, SR-3.6.6.5 +, SR-3.2.4.1 +, SR-3.2.1.1 +, SR-3.2.1.2 +, SR-3.7.18.1 +...

1E-9 +, 5E-10 +  and 3F0506-05, 2005 Technical Specifications Bases Control Program +

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Steam Safety Valve +, Remote shutdown +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.0.3 +, TS-3.8.1 +, TS-3.0.1 +, TS-3.4.13 +, TS-3.8.7 +, TS-3.9.2 +, TS-3.7.7 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.0.4 +, TS-3.4.5 +, TS-3.8.2 +, TS-3.1.6 +, TS-3.7.8 +, TS-3.3.1 +, TS-3.4.6 +, TS-3.4.7 +, TS-3.9.5 +, TS-3.0.4.a +, TS-3.0.4.b +, TS-3.0.2 +, TS-3.4.11 +, TS-3.0.5 +, TS-3.0.6 +, TS-3.8.10 +, TS-3.9.4 +, TS-3.2.5 +, TS-3.3.17 +, TS-3.0.4.c +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Time of Discovery +, High Radiation Area +, Grab sample +, Stroke time +, Anticipated operational occurrence +, Post Accident Monitoring +, Probabilistic Risk Assessment +, Qualified Offsite Circuit +, Missed surveillance +, Foreign Material Exclusion +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Power Operated Valves +, Pressure Boundary Leakage +, Offsite Circuit +, Fire Watch +, Unidentified leakage +, Manual Operator Action +, Operational leakage +, Loss of condenser vacuum +  and Operational convenience +