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ACI-349 +  and ACI-201 +

ASME Section XI +, ASME Section III +  and ASME Section X +

Iron +, Carbon +, Chloride +  and Lead +

BWRVIP-86 +, BWRVIP-139 +, BWRVIP-135 +, BWRVIP-42 +, BWRVIP-102 +, BWRVIP-48-A +  and BWRVIP-86-A +

10 CFR 21 +, 10 CFR 50 Appendix A +, 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 G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.49#e +  and 10 CFR 50.49#f +

NRC Generic Letter 07-01 +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 80-95, Generic Activity A-10 +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +  and NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +

ML11308A097 +, ML11308A097 +, ML11308A097 +, ML11308A097 +, ML11308A097 +, ML11308A097 +, ML11308A097 +, ML11308A097 +  and ML11308A097 +

NUREG/CR-6260 +, 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 +

35  +  and 49  +

115KV +, 4.16kV +  and 115kV +

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

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Circulating Water System +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Boric Acid +, Ultimate heat sink +, Fire Barrier +, Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, High Energy Line Break +, Aging Management +, Local Leak Rate Testing +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, License Renewal +, Fire Protection Program +, Dissimilar Metal Weld +  and Spent fuel rack +