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IWB-2500 +  and IWC-2500 +

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

Boron +, Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Chloride +  and Aluminum +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 50.55a +, 10 CFR 50.49#f +, 10 CFR 50.61#b2 +, 10 CFR 54.21#d +, 10 CFR 54.21#c +, 10 CFR 54.21#b +  and 10 CFR 50.55a#g +

05000305  +  and 07200064  +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +

ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +, ML14339A651 +  and ML14339A651 +

NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NRC Bulletin 80-11 +  and NRC Bulletin 88-09 +

NUREG/CR-6260 +, 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-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-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 +

Regulatory Guide 1.163 +, Regulatory Guide 1.137 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.99 +

07-09-028 +, 07-10-548 +, 07-09-469 +, 07-10-447 +, 07-09-597 +, 07-09-291 +, 07-09-680 +, 07-09-760 +, 07-09-777 +, 07-10-008 +, 07-10-324 +, 07-10-033 +, 07-10-665 +, 07-10-093 +, 07-10-286 +, 07-10-595 +  and 07-10-707 +

Steam Generator +, Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Reactor Pressure Vessel +, Residual Heat Removal +, Shield Building +, Circulating Water System +  and Control Rod +

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Coatings +, Nondestructive Examination +, Aging Management +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Control of Heavy Loads +, Liquid penetrant +, Fire Protection Program +, Dissimilar Metal Weld +, Power Uprate +, Overspeed +  and Leak-Before-Break +

WCAP-14574-A +, WCAP-15338-A +, WCAP-16641 +  and WCAP-16609 +

WCAP-14574-A +, WCAP-15338-A +, WCAP-16641 +  and WCAP-16609 +