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Iron +, Lead +  and Zinc +

10 CFR 50.73 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 2.106 +, 10 CFR 2.206 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50 Appendix B Criterion III, Design Control +  and 10 CFR 5#O +

LO-CAR-2007-03001 +, LO-CAR-2007-00300 +, LO-CAR-2006-07357 +, LO-CAR-2007-00230 +, LO-CAR-2007-00222 +, LO-CAR-2006-00624 +  and LO-CAR-2005-06711 +

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

ULNRC-03681, Forwards marked-up Replacement Page 5 of Attachment 1 to & Two Replacement Page mark-ups for Insert 3/4 3-25 of Attachment 3 to +  and ULNRC-03628, Application for Amend to License NPF-30,revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 as Listed +

P.4(o) +, P.4(s) +, P.4(n) +, H.11 +, H.13 +  and P.2 +

05000483  +  and 00482  +

ML093140803 +, ML021640348 +, ML1105S0846 +, ML093140a03 +, ML100430713 +, ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 +  and 05000482/LER-2009-009-01, For Wolf Creek, Regarding Defeating Feedwater Isolation on Low Tavg Coincident with P-4 Function Results in Missed Mode Change +

Turbine Trip +  and Reactor Trip +

- No Known Affiliation +  and Lawrence Criscione +

ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +, ML120030235 +...

3.819444e-4 d (0.00917 hours, 5.456349e-5 weeks, 1.25565e-5 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-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 0.00145 d (0.0347 hours, 2.066799e-4 weeks, 4.75625e-5 months)  +  and 0.00162 d (0.0389 hours, 2.314815e-4 weeks, 5.327e-5 months)  +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +  and NRC Inspection Manual 0612, Power Reactor Inspection Reports +

IR 05000482/2009004 +, IR 05000482/2009005 +  and IR 05000462/2009004 +

ML20198F341 +  and ML16342D859 +

NUREG-1431 +  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 +

AM +  and Emergency Operating Procedure +

TAC:ME7332 +  and TAC:ME3762 +

SR-3.3.2 +  and SR-3.3.2.9 +

1E-7 +, 10CFR2-206 +, 23D-3959 +, 07-68-122 +  and 1D-0014 +

NPF-30 +  and NPF-42 +

Kansas +, Illinois +, Washington +  and Missouri +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Decay Heat Removal +  and Control Rod +

TS-3.0.3 +, TS-3.8.1 +, TS-3.3.2 +, TS-3.3.1 +, TS-5.5.14 +  and TS-5.1.2.a +

TSTF-490 +  and TSTF-444 +

Thadani M +, Polickoski J +  and Plant Licensing Branch IV +

Boric Acid +, Shutdown Margin +, High Radiation Area +, Locked High Radiation Area +, Operability Determination +, Fuel cladding +, Substantial potential for overexposure +, Overexposure +  and Water hammer +