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Letter, Technical Specification, Bases Change  and Manual

Boron +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50 Appendix K +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 50.65 +, 10 CFR 50.36#c2ii +, 10 CFR 50.65#a4 +, 10 CFR 50.36#c2xii +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g6i +  and 10 CFR 50.71#e +

05000390  +, 05000391  +, 00390  +  and 00391  +

Turbine Trip +  and Reactor Trip +

Tennessee Valley Authority +  and Simmons P +

NRC Generic Letter 80-30, Clarification of the Term "Operable" As It Applies to Single Failure Criterion For Safety Systems Required by TS +  and NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +

ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +, ML17306A802 +  and ML17306A802 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 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)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 0.00167 d (0.04 hours, 2.380952e-4 weeks, 5.4792e-5 months)  +

Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.52 +, Regulatory Guide 1.93 +, Regulatory Guide 1.14 +  and Regulatory Guide 1.133 +

SR-3.8.1 +, SR-3.8.1.1 +, SR-3.8.4 +, SR-3.0.3 +, SR-3.6.1.1 +, SR-3.0.4 +, SR-3.8.1.2 +, SR-3.7.10.2 +, SR-3.0.2 +, SR-3.3.2.6 +, SR-3.7.7.2 +, SR-3.6.15.4 +, SR-3.5.2.3 +, SR-3.7.10.3 +, SR-3.3.2 +, SR-3.7.7.1 +, SR-3.8.4.8 +, SR-3.5.2.8 +, SR-3.6.6.5 +, SR-3.4.6.3 +, SR-3.7.7.4 +, SR-3.4.1.4 +, SR-3.2.1.2 +, SR-3.7.7.3 +, SR-3.3.2.4 +, SR-3.4.6.2 +, SR-3.4.6.4 +, SR-3.6.11.2 +, SR-3.0 +, SR-3.6.11.3 +...

1B-B +, 2B-B +, 1A-A +, 2A-A +, 2A-4 +, 2A1-A +, 1B1-B +, 1A1-A +, 0s-02-00 +, 03-0s-05 +, 147W605-242 +, 1O-day +, 2A1-4 +  and 1B1-8 +

NPF-20 +  and Watts Bar +

Tennessee +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, HVAC +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Control Room Emergency Ventilation +, Shield Building +, Main Steam Safety Valve +, Remote shutdown +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +, Main Steam +, Containment Spray +  and Control Room Emergency Air Temperature Control System +

TS-3.0.3 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.0.1 +, TS-3.8.7 +, TS-3.7 +, TS-3.7.1 +, TS-3.3.3 +, TS-3.7.7 +, TS-3.8.4 +, TS-3.5.4 +, TS-3.9.9 +, TS-3.0.4 +, TS-3.6.5 +, TS-2.2.4 +, TS-3.6.3 +, TS-3.6.1 +, TS-3.4.16 +, TS-3.7.10 +, TS-3.7.11 +, TS-3.3.2 +, TS-3.3.5 +, TS-3.4.1 +, TS-3.4.6 +, TS-3.6.4 +, TS-3.8.9 +, TS-3.6.7 +, TS-3.3.6 +, TS-3.6.15 +, TS-3.0.2 +...

TSTF-358 +, TSTF-359 +  and TSTF-372 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Time of Discovery +, Shutdown Margin +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Post Accident Monitoring +, Qualified Offsite Circuit +, FLEX +, Missed surveillance +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Offsite Circuit +, Grace period +, Core Exit Thermocouple +, Power Uprate +, Overspeed +, Operational leakage +, Operational convenience +  and Pressure Temperature Limits Report +