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Technical Specification  and Bases Change

ASME Section III +  and ASME Section XI +

Boron +, Iodine +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 100.11 +, 10 CFR 50.36#c2ii +, 10 CFR 50.55a#g +  and 10 CFR 50.55a#c +

Reactor Trip +  and Turbine Trip +

GDC 55 +, GDC 30 +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +

ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +, ML21194A270 +  and ML21194A270 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 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)  +, 6.25e-4 d (0.015 hours, 8.928571e-5 weeks, 2.0547e-5 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

NUREG-0677 +, NUREG-609 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +

Regulatory Guide 1.45 +, Regulatory Guide 1.121 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.32 +

SR-3.4.4.1 +, SR-3.4.13.1 +, SR-3.4.10.1 +, SR-3.4.3.1 +, SR-3.4.14.2 +, SR-3.4.6.1 +, SR-3.4.15.2 +, SR-3.4.11.1 +, SR-3.4.14.1 +, SR-3.4.5.1 +, SR-3.4.1.1 +, SR-3.4.16.2 +, SR-3.4.9.1 +, SR-3.4.8.2 +, SR-3.4.15.1 +, SR-3.4.6.3 +, SR-3.4.2.1 +, SR-3.4.11.2 +, SR-3.4.12.7 +, SR-3.4.1.4 +, SR-3.4.15.3 +, SR-3.4.15.4 +, SR-3.4.15.5 +, SR-3.4.1.2 +, SR-3.4.1.3 +, SR-3.4.5.2 +, SR-3.4.5.3 +, SR-3.4.6.2 +, SR-3.4.6.4 +, SR-3.4.7.1 +...

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Shutdown Cooling +, Residual Heat Removal +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +  and Control Rod +

TS-3.4.14 +, TS-3.0.3 +, TS-3.4.13 +, TS-3.8.5 +, TS-3.4.5 +, TS-3.8.2 +, TS-3.4.16 +, TS-3.4 +, TS-3.4.4 +, TS-3.4.8 +, TS-3.4.12 +, TS-3.4.3 +, TS-3.2.3 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.4.10 +, TS-3.1.3 +, TS-3.8.8 +, TS-3.4.6 +, TS-3.4.7 +, TS-3.1.5 +, TS-3.1.1 +, TS-3.1.4 +, TS-3.4.15 +, TS-3.9.5 +, TS-3.0.4.b +, TS-3.4.11 +, TS-3.8.10 +, TS-3.4.17 +, TS-3.2.4 +...

Unanalyzed Condition +, Boric Acid +, Non-Destructive Examination +, Grab sample +, Stroke time +, Anticipated operational occurrence +, Hydrostatic +, Surveillance Frequency Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, Core Exit Thermocouple +, Unidentified leakage +, Manual Operator Action +, Operational leakage +, Water hammer +, Gas accumulation +  and Leak-Before-Break +

WCAP-14040-NP-A +  and WCAP-7769 +

WCAP-14040-NP-A +  and WCAP-7769 +