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Boron +, Oxygen +, Hydrogen +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.2206 +, 10 CFR 50.4 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.54#o +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c +  and 10 CFR 20.1601#a +

P.1(a) +, P.1(e) +  and P.1(s) +

05000282  +  and 05000306  +

Nuclear Management Co +  and Nazar M +

NRC Generic Letter 99-02 +, NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +  and NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +

ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +, ML021060604 +  and ML021060604 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.0014 d (0.0336 hours, 2.000661e-4 weeks, 4.60405e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 3.240741e-4 d (0.00778 hours, 4.62963e-5 weeks, 1.0654e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0.00287 d (0.0689 hours, 4.100529e-4 weeks, 9.4364e-5 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +

IEEE 485 +  and IEEE-450 +

4kV +  and 4.16kV +

RT +  and ST +

Regulatory Guide 1.163 +, Regulatory Guide 1.9 +, Regulatory Guide 1.52 +, Regulatory Guide 1.93 +, Regulatory Guide 1.6 +, Regulatory Guide 8.38 +, Regulatory Guide 4.8 +  and Regulatory Guide 1.32 +

SR-3.8.1 +, SR-3.8.1.1 +, SR-3.0.3 +, SR-3.8.3.4 +, SR-3.8.2.1 +, SR-3.8.4.1 +, SR-3.0.2 +, SR-3.3.4.1 +, SR-3.9.4.1 +, SR-3.6.3.5 +, SR-3.8.6.1 +, SR-3.8.9.1 +, SR-3.8.6.6 +, SR-3.8.1.5 +, SR-3.8.4.3 +, SR-3.8.4.2 +, SR-3.3.3.1 +, SR-3.8.5.1 +, SR-3.8.8.1 +, SR-3.8.10.1 +, SR-3.9.4.2 +  and SR-3.3.6.5 +

1R-12 +, 1R-10 +, 2t-hours +, T2j-amps +, F413e-250 +  and 1f-n +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shield Building +, Emergency Core Cooling System +  and Main Steam Line +

TS-3.0.3 +, TS-3.8.1 +, TS-3.4.13 +, TS-3.8.7 +, TS-3.9.2 +, TS-3.5.3 +, TS-3.3.3 +, TS-3.8.3 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.9.4.c +, TS-3.8.2 +, TS-3.6.1 +, TS-3.4 +, TS-3.4.12 +, TS-3.4.3 +, TS-3.8.6 +, TS-3.2.3 +, TS-3.3.2 +, TS-3.3.5 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.4.10 +, TS-3.1.3 +, TS-3.3.4 +, TS-3.7.8 +, TS-3.8.8 +, TS-3.4.6 +, TS-3.8.9 +, TS-3.4.7 +...

TSTF-258 +, TSTF-37 +, TSTF-1 +, TSTF-152 +, TSTF-204 +, TSTF-279 +  and TSTF-364 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Battery sizing +, Deep Dose Equivalent +, Recently irradiated fuel +, Offsite Circuit +, Eddy-Current Testing +  and Pressure Temperature Limits Report +

WCAP-9272-P-A +, WCAP-14040-NP-A +, WCAP-10054-P-A +, WCAP-10924-P-A +  and WCAP-13677 +

WCAP-9272-P-A +, WCAP-14040-NP-A +, WCAP-10054-P-A +, WCAP-10924-P-A +  and WCAP-13677 +