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Letter  and Inspection Report

IWA-4222 +, IWA-4226 +  and IWA-4221 +

ASME Section XI +, ASME Section III +, ASME Section I +, ASME Section IX +  and ASME Section V +

Hydrogen +  and Lead +

10 CFR 50.72 +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 20.1602 +, 10 CFR 20.1701 +, 10 CFR 20.1904 +, 10 CFR 20.2207 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion IX +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 20.1905#g +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.55a#g4 +  and 10 CFR 20.1703#b +

G. Pry +, Marlone Davis +, Charles Phillips +, J. Mahan +, B. Murrell +, J. Schwertfeger +, D. Church +, L. Swenzinski +, T. Vehec +, R. Wheaton +, R. Porter +, F. Dohmen +, D. Olsen +, K. Kleinheinz +, L. Helms +, Mahesh Chawla +, C. Casey +  and Carol Hill +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

05000331  +  and 00331  +

EN-AA-203-1001 +, MA-AA-203-1001 +, ER-AA-113-1000 +  and EN-AA-302-1001 +

05000331/FIN-2014005-01 +, 05000331/FIN-2014005-02 +, 05000331/FIN-2014005-04 +, 05000331/FIN-2014005-08 +, 05000331/FIN-2014005-09 +, 05000331/FIN-2014005-03 +, 05000331/FIN-2014005-05 +, 05000331/FIN-2014005-06 +, 05000331/FIN-2014005-07 +, 05000331/FIN-2014003-04 +, 05000331/FIN-2014004-03 +  and 05000331/FIN-2015001-09 +

Boland A +  and Division Reactor Projects III +

IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +, IR 05000331/2014005 +...

IP 71111.12 +, IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71124.03 +, IP 71111.19 +, IP 71124.04 +, IP 71151 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.11Q +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.05Q +, IP 71111.08G +, IP 43004 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix C, Occupational Radiation Safety Significance Determination Process +, NRC Inspection Manual 0609/Appendix A +, NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +  and IMC 0310, Aspects within the Cross-Cutting Areas +

IP 71111.04-05 +, IP 71111.05-05 +, IP 71111.12-05 +, IP 71111.13-05 +, IP 71111.15-05 +, IP 71111.18-05 +, IP 71111.19-05 +, IP 71111.22-05 +, IP 71151-05 +, IP 71152-05 +, IP 71111.01-05 +, IP 71111.11-05 +, IP 71124.01-05 +, IP 71153-05 +, IP 71111.20-05 +, IP 71111.08-05 +, IP 71124.04-05 +, IP 71124.03-05 +  and IP 71114.04-06 +

IR 05000331/2014005 +  and IR 05000331/2014002 +

05000331/LER-2014-003, Regarding Both Doors in Secondary Containment Airlock Opened Concurrently +, 05000331/LER-2014-002, Regarding Both Doors in Secondary Containment Airlock Opened Concurrently +  and 05000331/LER-2013-006, Regarding Both Doors in Secondary Containment Airlock Opened Concurrently +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

Regulatory Guide 1.33 +  and Regulatory Guide 8.38 +

SR-3.6.4.1.2 +, SR-3.6.4.1.3 +  and SR-3.7.2.2 +

1Q122-BALL +, 1Q322-BALL +  and 1Q222-BALL +

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Low Pressure Coolant Injection +

TS-3.6.4.1 +, TS-3.9.7 +, TS-5.4.1.a +  and TS-5.7.1.e +

Bench test +  and Post maintenance test +

NextEra Energy +  and Vehec T +

Boric Acid +, Reactor Vessel Water Level +, High Radiation Area +, Non-Destructive Examination +, Water Inventory Control +, Commercial Grade Dedication +, Enforcement Discretion +, Probabilistic Risk Assessment +, Nondestructive Examination +, Temporary Modification +, Functionality Assessment +, Significance Determination Process +, Seismically rugged +, Shift Technical Advisor +, Integrated leak rate test +, Operability Determination +, Code Reconciliation +, Commercial Grade +, Deep Dose Equivalent +, Fuel cladding +, Liquid penetrant +, Fire Protection Program +, Substantial potential for an overexposure +, Operability Assessment +, Overexposure +, Overspeed +  and Dedication package +

WO 1287016 +, WO 40052460 +, WO 40187789 +  and WO 40136087 +