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OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING  and TEXT-LICENSE APPLICATIONS & PERMITS

10 CFR 100 +, 10 CFR 50.60 +, 10 CFR 51.22#c9 +, 10 CFR 51.22#c +, 10 CFR 50.22#c9 +, 10 CFR 50.92#c +  and 10 CFR 50#60 +

05000302  +  and 00302  +

Reactor Trip +  and Turbine Trip +

Cowan J +  and Duke Energy +

ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +, ML20212F267 +  and ML20212F267 +

3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174 +, 3F0767-03, Provides 120-day Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations. Submittal of Commitments Made in Ltr, Encl +, 3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes +  and 05000302/LER-1997-007, :on 970306,building Temperature Variations Larger than Assumed Resulting in Unknown Instrument Uncertainties Was Discovered.Caused by Lack of Commitment. Established Ambient Temperature Requirements +

SR-3.5 +  and SR-3.5.3.1 +

3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174 +, 3F1097-18 +, 13F1097-18 +, 3F1087-18, Application for Amend to License DPR-72,consisting of Suppl 2 to Tech Spec Change Request 152.Suppl Updates Fuel Cycle 7 Design to Reflect 465 -61/+10 EFPDs Cycle 6 Length.Approval & Implementation of Change Prior to Mode 4 Entry Requested +, 3F0797-21, TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt +, 3F0797-10, TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys +, 3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes +  and 3l-operabl +

Florida +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +  and Decay Heat Removal +

TS-3.7.4 +, TS-3.5.2 +, TS-3.7.5 +, TS-3.7.6 +, TS-3.3.12 +, TS-3.3.17 +  and TS-3.7.18 +

Post Accident Monitoring +, Pressure boundary leak +, Unidentified leakage +  and Operational leakage +