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Letter  and Updated Final Safety Analysis Report (UFSAR)

ANSI B31.1 +  and ANSI/ANS 56.8 +

IWB-3600 +  and IWB-2500 +

Iron +, Copper +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +, Aluminum +  and Calcium +

BWRVIP-75 +, BWRVIP-48 +, BWRVIP-94 +, BWRVIP-25 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-139 +, BWRVIP-130 +, BWRVIP-05 +, BWRVIP-104 +, BWRVIP-78 +, BWRVIP-1 +, BWRVIP-27-A +, BWRVIP-18-A +, BWRVIP-49-A +, BWRVIP-74-A +, BWRVIP-86-A +  and BWRVIP-58-A +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 54.21#C +, 10 CFR 54.21#c11i +  and 10 CFR 50.55#a +

05000219  +  and 00219  +

AmerGen +  and Gallagher M +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, 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 +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +, ML061800302 +  and ML061800302 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, 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 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

4kV +  and 4.16kV +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.54 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Standby Liquid Control +, Stator Cooling Water +, Stator Water +, Reactor Building Closed Loop Cooling +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Non-Destructive Examination +, Fire Barrier +, Coatings +, Met Tower +, Nondestructive Examination +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Operability Determination +, Moisture barrier +, License Renewal +, Biofouling +  and Thermography +