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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.2 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.65#a +  and 10 CFR 50.55a#g +

M. McLaughlin +, R. Bement +, E. Montgomery +, C. King +, G. Andrews +, D. Elkinton +, C. Kharrl +, M. Lacal +, D. Heckman +, K. House +, T. Romay +, D. Mooris +, E. Arnold +, S. Schaeffer +, M. McKinley +, C. Arambula +, C. Sowers +, P. Beers +, W. Nau +, C. Hsia +, K. James +, F. Gaber +, Z. Hettel +, J. Tolar +  and W. Barrero +

Barrier Integrity +, Initiating Events +  and Mitigating Systems +

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

Thomas Farnholtz +  and Region 4 Engineering Branch 1 +

IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +, IR 05000528/2016007 +...

IP 71111.21 +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and IMC 0310, Aspects within the Cross-Cutting Areas +

Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps +, Information Notice 2013-17, Significant Plant Transient Induced by Safety-Related Direct Current Bus Maintenance at Power +, Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping +, Information Notice 2010-23, In: Malfunctions of Emergency Diesel Generator Speed Switch Circuits +  and Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers +

1E-6 +, 3E-PKA-F11 +, 3E-PKA-H1 +, 3E-PBB-S04 +, 3E-PGB-L32 +, 3E-PNA-N11 +, 3E-PK-F11 +, 3E-PGA-L31 +  and 3AFN-V012 +

Palo Verde +, NPF-51 +  and NPF-74 +

Arizona +  and Washington +

Steam Generator +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Remote shutdown +, Spray Pond +, Decay Heat Removal +, Auxiliary Feed Water +  and Containment Spray +

Arizona Public Service +  and Edington R +

Safe Shutdown +, Ultimate heat sink +, Probabilistic Risk Assessment +, Significance Determination Process +, Job Performance Measure +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Time Critical Operator Action +, Through-Wall Leakage +  and Gas accumulation +