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Letter, Technical Specification  and Bases Change

Boron +, Iodine +, Hydrogen +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50.36#c2ii +, 10 CFR 50.65#a4 +, 10 CFR 50.65#a +  and 10 CFR 50 Appendix I#J +

05000528  +, 05000529  +  and 05000530  +

Turbine Trip +  and Reactor Trip +

Arizona Public Service +  and Weber T +

GDC 57 +, GDC 54 +, GDC 10 +, GDC 18 +, GDC 17, Electric power systems +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 84-41 +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +

ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +, ML072550047 +  and ML072550047 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 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)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +

4.16KV +  and 4.16kV +

Regulatory Guide 1.27 +, Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.93 +  and Regulatory Guide 1.182 +

SR-3.1.5.3 +, SR-3.5.4.1 +, SR-3.8.1.3 +, SR-3.8.1 +, SR-3.8.1.1 +, SR-3.8.1.7 +, SR-3.0.3 +, SR-3.0.1 +, SR-3.4.13.1 +, SR-3.6.1.1 +, SR-3.8.1.1.2 +, SR-3.6.3.4 +, SR-3.0.4 +, SR-3.8.1.8 +, SR-3.7.4.1 +, SR-3.8.1.2 +, SR-3.7.9.2 +, SR-3.8.1.9 +, SR-3.0.2 +, SR-3.6.3.5 +, SR-3.3.6.2 +, SR-3.8.1.6 +, SR-3.6.3.7 +, SR-3.6.3.3 +, SR-3.4.14.1 +, SR-3.6.3.6 +, SR-3.8.1.5 +, SR-3.1.6.1 +, SR-3.8.1.4 +, SR-3.3.8.3 +...

36ST-9SA02 +  and 41pPEC-W +

Manual Scram +  and Automatic Scram +

Texas +, Arizona +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Steam Bypass Control System +, Main Steam Safety Valve +, Remote shutdown +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Steam +, Containment Spray +  and Control Room Emergency Air Temperature Control System +

TS-3.0.3 +, TS-3.8.1 +, TS-3.0.1 +, TS-3.5.3 +, TS-3.7 +, TS-3.3.11 +, TS-3.7.7 +, TS-3.5.4 +, TS-3.0.4 +, TS-3.4.9 +, TS-3.6.3 +, TS-3.8.2 +, TS-3.6.1 +, TS-3.7.5 +, TS-3.7.11 +, TS-3.1.7 +, TS-3.9.3 +, TS-3.1.6 +, TS-3.4.10 +, TS-3.6.6 +, TS-3.7.8 +, TS-3.1.2 +, TS-3.4.6 +, TS-3.1.5 +, TS-3.0 +, TS-3.7.12 +, TS-3.6.7 +, TS-3.1.1 +, TS-3.3.6 +, TS-3.0.4.a +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Stroke time +, Anticipated operational occurrence +, High Energy Line Break +, Missed surveillance +, Loss of Offsite Power +, Offsite Circuit +, Unidentified leakage +, Overspeed trip +, Overspeed +  and Operational convenience +