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Letter, Technical Specifications  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ASME Section XI +, ASME Section III +  and ASME Section X +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.2 +, 10 CFR 50.44 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix G +, 10 CFR 100.11 +, 10 CFR 50.55a +, 10 CFR 50.91#b1 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#b +, 10 CFR 50.55a#c +, 10 CFR 50.55a#f4 +, 10 CFR 50.55a#f4ii +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

05000528  +, 05000529  +, 05000530  +, 00528  +, 00529  +  and 00530  +

ML062980233 +, ML070990057 +  and ML082460241 +

Arizona Public Service +  and Mims D +

GDC 38 +, GDC 41 +, GDC 55 +, GDC 35 +, GDC 39 +, GDC 40 +, GDC 42 +  and GDC 43 +

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" +

ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +, ML101310224 +  and ML101310224 +

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)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-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)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

NUREG-1432 +, NUREG-0677 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Regulatory Guide 1.137 +, Regulatory Guide 1.7 +  and Regulatory Guide 1.14 +

SR-3.7.5.2 +, SR-3.0.3 +, SR-3.7.5.3 +, SR-3.4.13.1 +, SR-3.7.1.1 +, SR-3.6.6.3 +, SR-3.4.10.1 +, SR-3.0.2 +, SR-3.6.6.2 +, SR-3.8.3.3 +, SR-3.5.3.4 +, SR-3.5.3.3 +, SR-3.4.11.1 +, SR-3.4.11.3 +, SR-3.7.2.1 +, SR-3.5.3.7 +, SR-3.4.15.1 +, SR-3.5.3.5 +, SR-3.4.11.2 +, SR-3.4.7.2 +, SR-3.7.5.5 +, SR-3.5.3.6 +, SR-3.4.13.3 +  and SR-3.5.3.8 +

Palo Verde +, NPF-51 +  and NPF-74 +

Texas +, Arizona +  and Washington +

Steam Generator +, Emergency Diesel Generator +, Shutdown Cooling +, Decay Heat Removal +  and Containment Spray +

TS-3.4.13 +, TS-3.4.4 +, TS-5.5.8 +, TS-5.5.14 +, TS-3.9.6 +, TS-5.5 +  and TS-3.9 +

TSTF-479 +  and TSTF-497 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Time to boil +  and Incorporated by reference +