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IWB-2500 +, IWB-5222 +, IWB-5221 +, IWB-5210 +, IWA-5000 +, IWA-2210 +  and IWA-2000 +

ASME Section XI +  and ASME Section X +

Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +  and Aluminum +

BWRVIP-75-A +, BWRVIP-48 +, BWRVIP-116 +, BWRVIP-139 +, BWRVIP-130 +, BWRVIP-27-A +, BWRVIP-48-A +, BWRVIP-49-A +  and BWRVIP-86-A +

10 CFR 50 Appendix A +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix H +, 10 CFR 54.4 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +, 10 CFR 50.49#e +, 10 CFR 50.49#f +  and 10 CFR 50.55a#a3 +

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 +

ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +, ML083030242 +  and ML083030242 +

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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, 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 +

Nozzle:N4A +  and Nozzle:N10 +

4.16kV +  and 345kV +

TAC:MD0283 +, TAC:MD0323 +, TAC:MD0284 +, TAC:MD0515 +  and TAC:MD0285 +

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

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Main Steam Line +, Control Rod +  and Main Steam +

Boric Acid +, Loop seal +, Packing leak +, Non-Destructive Examination +, Fire Barrier +, Hydrostatic +, Coatings +, Nondestructive Examination +, VT-2 +, Condition Adverse to Quality +, High Energy Line Break +, Aging Management +, Local Leak Rate Testing +, Notice of Violation +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, Main Steam Line Radiation Monitor +, Moisture barrier +, License Renewal +, Fire Protection Program +, Scaffolding +, Eddy Current Test +, Thermography +, Spent fuel rack +  and Metamic +