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License Fee Requirements Letter  and Safety Evaluation Report

Atomic Energy Act of 1954 +  and National Environmental Policy Act of 1969 +

Nitrogen +, Hydrogen +  and Aluminum +

BWRVIP-75 +, BWRVIP-41 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-74 +  and BWRVIP-05 +

10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50 Appendix G +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 54.22, Contents of Application--Technical Specifications +, 10 CFR 54.23, Contents of Application--Environmental Information +, 10 CFR 54.29 +, 10 CFR 140.92 Appendix B +, 10 CFR 51.53#c3i +, 10 CFR 51.53#c3ii +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#a1 +, 10 CFR 54.21#b +, 10 CFR 54.21#c2 +, 10 CFR 54.21#a +, 10 CFR 54.19#b +, 10 CFR 54.19#a +, 10 CFR 50.71#e +  and 10 CFR 54.17#e +

05000277  +, 05000278  +, 00277  +  and 00278  +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +, ML030370649 +  and ML030370649 +

NUREG-1739 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-1437, Supplement 15, Second Renewal, Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Virgil C. Summer Nuclear Station, Unit 1 Final Report +

Pennsylvania +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Safety Relief Valve +, Control Room Envelope +, Rod Worth Minimizer +, Main Condenser +, Control Rod +  and Main Steam +

Safe Shutdown +, Nondestructive Examination +, Incorporated by reference +, Aging Management +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Integrated leak rate test +, License Renewal +  and Fire Protection Program +