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Technical Specification  and Bases Change

ASME Section III +  and ASME Section XI +

Iodine +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.2 +, 10 CFR 50.44 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 100.11 +  and 10 CFR 50.55a#c +

05000277  +  and 05000278  +

Turbine Trip +  and Reactor Trip +

05000321/FSAR-6.4#3 +, Category:05000321/FSAR Chapter 14 +, 05000321/FSAR-6.4#4 +, 05000321/FSAR-14.6#3 +, 05000321/FSAR-5.2 +, 05000321/FSAR-4.10#4 +, 05000321/FSAR-4.10#2 +, 05000321/FSAR-4.10#3 +, 05000321/FSAR-14.6#5 +, 05000321/FSAR-4.2#6 +, 05000321/FSAR-14.5#6.2 +, 05000321/FSAR-6.4#1 +, 05000321/FSAR-14.6 +, 05000321/FSAR-10.17#6 +, 05000321/FSAR-1.5 +, 05000321/FSAR-4.7 +, 05000321/FSAR-14.9 +, 05000321/FSAR-5.2#3.4 +, 05000321/FSAR-5.2#3.1 +, 05000321/FSAR-5.2#3.9 +, 05000321/FSAR-14.6#4 +, 05000321/FSAR-1.5#1.6 +  and 05000321/FSAR-10.7 +

Exelon +  and Gallagher M +

NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability +  and NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +

ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +, ML021190174 +  and ML021190174 +

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)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 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)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 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)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +

NUREG/CR-3052, Amends 141 & 77 to Licenses DPR-57 & NPF-5,respectively Modifying Tech Specs to Permit Only One Recirculation Loop in Operation & to Implement Jet Pump Suveillance Recommendations of NUREG/CR-3052 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

RT +  and Emergency Operating Procedure +

Regulatory Guide 1.45 +, Regulatory Guide 1.7 +  and Regulatory Guide 1.99 +

NEDO-20566A +, NEDC-32183P +, NEDC-32707P +, NEDC-32162P +, NEDO-22155 +, NEDC-32163P +, NEDO-24229 +  and NEDC-32427P +

05000321/SR-3.5.1.5 +, 05000321/SR-3.5.1.6 +, 05000321/SR-3.5.1.7 +, 05000321/SR-3.5.1.8 +, 05000321/SR-3.5.2.3 +, 05000321/SR-3.5.2.4 +, 05000321/SR-3.5.2.6 +, 05000321/SR-3.5.2.1 +, 05000321/SR-3.5.2.2 +, 05000321/SR-3.5.2.5 +, 05000321/SR-3.3.5.1.5 +, 05000321/SR-3.6.1.1.1 +, 05000321/SR-3.6.1.3 +, 05000321/SR-3.6.1.2.1 +, 05000321/SR-3.6.1.3.6 +, 05000321/SR-3.6.1.3.2 +, 05000321/SR-3.6.1.3.1 +, 05000321/SR-3.6.4.3.2 +, 05000321/SR-3.6.1.5.3 +, 05000321/SR-3.6.1.5.2 +, 05000321/SR-3.6.1.5.1 +, 05000321/SR-3.6.1.6.1 +, 05000321/SR-3.6.1.6.2 +, 05000321/SR-3.6.2.4.2 +, 05000321/SR-3.6.3.2.1 +, 05000321/SR-3.6.4.1.1 +, 05000321/SR-3.6.4.1.2 +, 05000321/SR-3.6.4.1.4 +, 05000321/SR-3.6.4.1.3 +, 05000321/SR-3.6.4.2.1 +...

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Low Pressure Coolant Injection +  and Main Turbine Bypass System +

05000321/TS-3.4.1 +, 05000321/TS-3.5.1 +, 05000321/TS-3.2.1 +, 05000321/TS-3.2.2 +, 05000321/TS-3.7.2 +, 05000321/TS-3.4.8 +, 05000321/TS-3.5.2 +, 05000321/TS-3.6.1.2 +, 05000321/TS-3.3.1.1 +, 05000321/TS-3.3.6.1 +, 05000321/TS-3.0.3 +, 05000321/TS-3.6.4.2 +, 05000321/TS-3.6.4.3 +, 05000321/TS-3.3.5.2 +, 05000321/TS-3.3.5.1 +, 05000321/TS-3.6.1.1 +, 05000321/TS-3.6.1.3 +, 05000321/TS-3.6.1.5 +, 05000321/TS-3.6.2.3 +, 05000321/TS-3.0.4 +, 05000321/TS-3.6.3.1 +, 05000321/TS-3.3.6.2 +, 05000321/TS-3.4.4 +, 05000321/TS-3.0.6 +, 05000321/TS-3.4.5 +, 05000321/TS-3.4.7 +, 05000321/TS-3.6.2.2 +, 05000321/TS-3.9.7 +, 05000321/TS-3.9.8 +, 05000321/TS-3.1.8 +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Unanalyzed Condition +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Grab sample +, Stroke time +, Post Accident Monitoring +, Hydrostatic +, Squib +, Abnormal operational transient +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Fuel cladding +, Pressure Boundary Leakage +, Unidentified leakage +, Operational leakage +  and Water hammer +