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Safety Evaluation  and Code Relief or Alternative

ANSI N101.4 +, ANSI N45.2.13-1976 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

IWB-3514 +, IWC-3000 +, IWB-2500 +, IWB-3000 +, IWC-5221 +, IWC-2500 +, IWC-5222 +, IWB-3142 +, IWB-5222 +, IWB-2412 +, IWB-5220 +, IWC-1220 +, IWB-2420 +, IWC-2412 +, IWC-2420 +, IWC-5210 +, IWA-2300 +, IWA-5000 +, IWA-5250 +, IWA-3100 +, IWA-2211 +, IWA-2314 +, IWA-2317 +, IWA-5242 +, IWA-4000 +, IWA-4540 +, IWA-9000 +, IWA-2210 +, IWA-2213 +, IWA-4170 +...

ASME Section XI +, ASME Section III +  and ASME Section V +

Iron +, Nitrogen +, Carbon +, Silicon +  and Chromium +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.65 +, 10 CFR 5.55a#a3i +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g5 +, 10 CFR 50.55a#g5iii +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#b2 +, 10 CFR 50.55a#b2xiv +, 10 CFR 50.55a#b2ixB +, 10 CFR 50.55a#b3v +, 10 CFR 50.55a#g6iiC +, 10 CFR 50.55a#b2xvA +, 10 CFR 50.55a#b2xviB +, 10 CFR 50.55a#c2ii +  and 10 CFR 50.55a#bxvA +

ASME Code Case N-460 +, ASME Code Case N-604 +, ASME Code Case N-435-1 +, ASME Code Case N-616 +, ASME Code Case N-598 +, ASME Code Case N-498-1 +, ASME Code Case N-639 +, ASME Code Case N-546 +, ASME Code Case N-528-1 +, ASME Code Case N-623 +, ASME Code Case N-605 +, ASME Code Case N-566-1 +  and ASME Code Case N-528 +

05000346  +  and 00346  +

ML022700279 +  and ML022410047 +

61 FR 41303 +  and 64 FR 51370 +

Anthony Mendiola +  and NRC/NRR/DLPM/LPD3 +

NRC Generic Letter 90-09, Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +, ML022700279 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 4.62963e-4 d (0.0111 hours, 6.613757e-5 weeks, 1.522e-5 months)  +

ML022410047 +, ML022270104 +, ML022190535 +  and ML020430484 +

TAC:MB1607 +, TAC:MA7210 +, TAC:MB5849 +, TAC:MA4549 +, TAC:MB0665 +, TAC:M93310 +, TAC:M87188 +  and TAC:M77942 +

Regulatory Guide 1.147 +, Regulatory Guide 1.33 +, Regulatory Guide 1.58 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.123 +

Ohio +, Washington +, Virginia +, South Carolina +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Steam +  and Containment Spray +

TS-3.0.3 +, TS-3.5.2 +, TS-3.4.6 +, TS-3.4.9.1 +  and TS-3.4.2 +

FirstEnergy +  and Myers L +

Boric Acid +, Hydrostatic +, Coatings +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Incorporated by reference +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Moisture barrier +, Pressure boundary leak +, Through-Wall Leakage +, Dissimilar Metal Weld +, Scaffolding +, Backfit +  and Operational convenience +