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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 20.1101#c +, 10 CFR 50.75#g +  and 10 CFR 20.2203#a3i +

R. Anderson +, Kenneth Riemer +, J. Morris +, M. Lingenfelter +, Marlone Davis +, D. Curtland +, R. Porter +, J. Swales +, F. Dohmen +, K. Kleinheinz +, S. Catron +, B. Kindred +, G. Rushworth +, D. Barta +, C. Harberts +, B. Eckes +, S. Funk +, P. Giroir +, C. Dieckmann +, N. McKenney +, J. Cadogan +, K. Feintuck +, D. Albrecht +, G. Park +  and Dante Johnson +

Control rod 14-23 +  and Control rod 10-11 +

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

H.14 +  and P.3 +

05000331  +  and 00331  +

ML072610036 +  and IR 05000331/2005002 +

05000331/FIN-2009002-01 +, 05000331/FIN-2009002-03 +, 05000331/FIN-2005002-02 +, 05000331/FIN-2009002-04 +, 05000331/FIN-2009002-02 +, 05000331/FIN-2005005-02 +  and 05000331/FIN-2009002-00 +

Kenneth Riemer +  and NRC/RGN-III/DRP/B2 +

IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +, IR 05000331/2009002 +...

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 0.0208 d (0.5 hours, 0.00298 weeks, 6.852805e-4 months)  +

IP 71111.12 +, IP 71111.18 +, IP 71111.04 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.08 +, IP 71111.19 +, IP 71151 +, 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 71111.07, Heat Sink Performance +, IP 71111.05Q +, IP 71111.12Q +, IP 71004 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix D +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0608 +, NRC Inspection Manual 0609/Appendix B +, IMC 0305, Operating Reactor Assessment Program +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.22 +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71121.02 +, IP 71121.01 +, IP 71122.03 +, 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 71151-05 +, IP 71111.07-05 +, IP 71121.01-05 +, IP 71121.02-05 +, IP 71153-05 +, IP 71111.20-05 +, IP 71111.08-05 +  and IP 71122.03-05 +

IR 05000331/2009002 +  and IR 05000331/2005002 +

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

Washington +  and Iowa +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control rod blade +, Control Rod +  and Main Steam +

TS-5.5.8 +, TS-3.9.4 +  and TS-3.9 +

Duane Arnold +  and Richard Anderson +

High Radiation Area +, Water Inventory Control +, Past operability +, Nondestructive Examination +, Temporary Modification +, Significance Determination Process +, Flow Accelerated Corrosion +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Liquid penetrant +, Fire Protection Program +, Power change +, Downpower +, Power Uprate +  and Overspeed +