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ACI-318 +  and ACI-301 +

ASME Section III +  and ASME Section XI +

Carbon +  and Hydrogen +

BWRVIP-75 +, BWRVIP-41 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-74 +, BWRVIP-29 +, BWRVIP-05 +, BWRVIP-07 +  and BWRVIP-01 +

10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.29 +, 10 CFR 50.55a +, 10 CFR 54.29#a +  and 10 CFR 54.29#b +

05000277  +, 05000278  +, 00277  +  and 00278  +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 79-20, Cracking in Feedwater Lines +, NRC Generic Letter 85-20, Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock And Wilcox Plants +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, 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 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +, NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +

ML022590527 +, ML022590527 +, ML022590527 +, ML022590527 +, ML022590527 +, ML022590527 +, ML022590527 +  and ML022590527 +

IEEE 323 +, IEEE 43-1974 +  and IEEE 95-1977 +

Information Notice 91-46 +, Information Notice 92-20 +  and Information Notice 87-65 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-6335 +, NUREG-1568 +, NUREG-1526 +, NUREG/CR-6384 +, 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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, 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 +

Regulatory Guide 1.99 +, Regulatory Guide 1.89 +, Regulatory Guide 1.46 +  and Regulatory Guide 1.154 +

Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Control Rod +  and Main Steam +

Fire Barrier +, Coatings +, Aging Management +, Local Leak Rate Testing +, License Renewal +, Control of Heavy Loads +  and Thermal fatigue +