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Letter  and Inspection Report

Boron +, Iron +, Nitrogen +, Lead +  and Silver +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 20.1501 +, 10 CFR 20.1602 +, 10 CFR 20.1802 +, 10 CFR 50.65 +, 10 CFR 61.55 +, 10 CFR 61.56 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 2.790 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.54#t +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b5 +, 10 CFR 50.47#b15 +, 10 CFR 20.1101#c +, 10 CFR 20.1703#f +  and 10 CFR 20.1601#i +

J. McCarthy +, P. Smith +, R. Turner +, Anton Vegel +, P. Louden +, D. Spaulding +, K. Locke +, A. Cayia +, S. Thomas +, R. Ladd +, P. Schwartz +, M. Holzmann +, B. Kopetsky +, J. Strharsky +, J. Jensen +, R. Hopkins +, B. Jensen +, T. Kendall +, F. Flentje +, C. Sizemore +, J. Schweitzer +, C. Jilek +, G. Casadonte +, J. Boesch +, J. Connolly +, D. Fadel +, D. Shannon +, R. Milner +, C. Krause +, T. Breene +...

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

05000266  +, 05000301  +, 00266  +  and 00301  +

Emergency Facility +  and Emergency Operations Facility +

05000266/FIN-2003009-01 +, 05000266/FIN-2003009-03 +, 05000266/FIN-2003009-06 +, 05000301/FIN-2003009-03 +, 05000266/FIN-2003009-02 +, 05000301/FIN-2003009-02 +, 05000301/FIN-2003009-04 +, 05000301/FIN-2003009-05 +, 05000266/FIN-2003009-07 +, 05000301/FIN-2003009-07 +, 05000301/FIN-2003009-08 +  and 05000301/FIN-2003009-09 +

Reynolds S +  and Division Reactor Projects III +

IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +, IR 05000266/2003009 +...

8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-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)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

TI 2515/150 +  and TI 2515/152 +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71114.03 +, IP 71111.08 +, IP 71114.06 +, IP 71114.02 +, IP 71111.19 +, IP 71151 +, IP 71114.05 +, 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 71111.07, Heat Sink Performance +, IP 71111.23 +, IP 71111.14 +, IP 71111.16 +  and IP 71111.20, Refueling and Other Outage Activities +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0350 +, 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 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0609/Appendix F +  and IMC 0305, Operating Reactor Assessment Program +

IP 95003 +, IP 71111.08 +, IP 71122.02 +, IP 71121.02 +, IP 71121.01 +, IP 71121.03 +  and IP 71122.03 +

NFPA 13 +  and NFPA 15 +

NRC Bulletin 01-01 +, NRC Bulletin 79-19 +  and NRC Bulletin 03-02 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-1765, NSP000017-Revised Testimony of Steven Skoyen-NUREG-1765 Excerpts +

2P-10B +, 2P-10A +, 1P-29 +, 2P-29 +, 1P-11A +, 2MS-2019 +, 1AF-4000 +, 2SI-856A +, 2SI-856B +, 1SI-866A +, 2CV-203 +  and 2SC-966A +

DPR-24 +  and DPR-27 +

Washington +  and Wisconsin +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

Nuclear Management Co +  and Middlesworth G +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Fire Barrier +, Past operability +, Probabilistic Risk Assessment +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Significance Determination Process +, Foreign Material Exclusion +, Shift Technical Advisor +, Process Control Program +, Large early release frequency +, Stress corrosion cracking +, Eddy Current Testing +, Operability Determination +, Pressure Boundary Leakage +, Fire Protection Program +, Scaffolding +, Substantial potential for an overexposure +, Siren +  and Overexposure +