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Letter, Technical Specification  and Bases Change

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Nitrogen +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 100.11 +, 10 CFR 50.36#c2ii +, 10 CFR 50.65#a4 +, 10 CFR 50.55a#b3iii +  and 10 CFR 50.71#e +

RA 09-0053 +  and L 12 +

Turbine Trip +  and Reactor Trip +

Wolf Creek +  and Flannigan R +

GDC 35 +, GDC 18 +, GDC 17, Electric power systems +  and GDC 19, Control room +

ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +, ML090750624 +  and ML090750624 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-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-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 0.00167 d (0.04 hours, 2.380952e-4 weeks, 5.4792e-5 months)  +

NUREG-0881, Safety Evaluation Accepting Licensee Submittals & Addl Info on Environ Qualification & Design for Instrumentation,Per Reg Guide 1.97 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

JF +, EP-8818C +, EP-8818D +, EP-8818A +  and EP-8818B +

Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.121 +  and Regulatory Guide 1.22 +

SR-3.8.1 +, SR-3.8.1.7 +, SR-3.6.1.1 +, SR-3.7.2.2 +, SR-3.5.2.1 +, SR-3.6.3.4 +, SR-3.8.1.8 +, SR-3.8.1.2 +, SR-3.8.1.9 +, SR-3.3.2.8 +, SR-3.3.2.6 +, SR-3.5.2.3 +, SR-3.7.3.3 +, SR-3.6.3.5 +, SR-3.3.2.5 +, SR-3.6.3.7 +, SR-3.6.3.8 +, SR-3.6.3.3 +, SR-3.6.3.6 +, SR-3.7.2.1 +, SR-3.3.2 +, SR-3.5.2.8 +, SR-3.7.3.1 +, SR-3.5.2.2 +, SR-3.5.2.6 +, SR-3.5.2.7 +, SR-3.7.3.2 +, SR-3.3.2.4 +, SR-3.5.2.4 +, SR-3.5.2.5 +...

26A-002 +, 1F-I-F +  and F1F-F +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Residual Heat Removal +, Control Room Emergency Ventilation +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Steam +  and Containment Spray +

TS-3.0.3 +, TS-3.7.2 +, TS-3.8.1 +, TS-3.7.3 +, TS-3.4.13 +, TS-3.6.5 +, TS-3.4.5 +, TS-3.6.1 +, TS-3.4.16 +, TS-3.4.4 +, TS-3.4.6 +, TS-3.6.4 +, TS-3.4.7 +, TS-5.5.14 +  and TS-5.5 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, High Radiation Area +, Ultimate heat sink +, Stroke time +, High Energy Line Break +, Stress corrosion cracking +, Loss of Offsite Power +, Power Operated Valves +, Offsite Circuit +, Overspeed +, Operational leakage +, Water hammer +  and Gas accumulation +

F-FIF-F +  and F-14-F +