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Letter, License-Operating (New/Renewal/Amendments) DKT 50  and Safety Evaluation

ASME Section XI +  and ASME Section III +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.65 +, 10 CFR 50.55a +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#cii +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000272  +  and 00272  +

ML003769765 +, ML010430054 +, ML003738931 +, ML041540500 +, ML052720233 +, ML003691745 +, ML0037635950 +, LR-N05-0479, Supplement to Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, and Steam Generator Tube Inspection Report and to Revise Reactor Coolant +  and LR-N05-0373, Supplement to Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, and Steam Generator Tube Inspection Report and to Revise Reactor Coolant +

33 FR 18610 +, 70 FR 24655 +  and 69 FR 7661 +

Stewart Bailey +  and NRC/NRR/DLPM/LPD1 +

GDC 15 +, GDC 14 +, GDC 30 +, GDC 32 +  and GDC 19, Control room +

ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +, ML052720233 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 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)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

Reactor Coolant System +  and LR-N970790, Submits Response to Violations Noted in Insp Repts 50-272/97-18 & 50-311/97-18.Corrective Actions:Reopened Valves on 970916 & Locally Verified Open by Loss Prevention Personnel +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +  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 +

ML052720233 +  and ML052720233 +

SR-4.4.6.2.3 +, SR-4.4.6.2.c +, SR-4.4.5.1 +, SR-4.4.5.2 +, SR-4.4.6.2.a +, SR-4.4.6.2.e +, SR-4.4.6.2 +, SR-4.4.5.0 +, SR-4.4.5.3 +, SR-4.4.5.5 +, SR-4.4.6.2.d +  and SR-4.4.6.2.b +

Steam Generator +  and Reactor Coolant System +

TS-3.0.3 +, TS-3.4.5 +, TS-3.4.6.2 +, TS-1.19 +, TS-4.0.5 +, TS-4.4.6.2 +, TS-6.17 +, TS-6.8.4.i +, TS-6.9.1.7 +, TS-1.21 +, TS-6.9.1 +  and TS-1.15 +

PSEG +  and Levis W +

Non-Destructive Examination +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Pressure Boundary Leakage +, Flow Induced Vibration +  and Operational leakage +