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Letter, Report  and Miscellaneous

ANSI B31.1 +, ANSI B30.2-1976 +  and ANSI B30.11-1973 +

IWB-3500 +, IWC-3500 +  and IWB-3520 +

ASME Section XI +  and ASME Section III +

Iron +, Copper +, Carbon +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 54.3 +, 10 CFR 54.49 +, 10 CFR 50.55a +, 10 CFR 54.4#a3 +, 10 CFR 50.49#j +, 10 CFR 54.3#a6 +, 10 CFR 54.21#d +, 10 CFR 54.21#c +, 10 CFR 50.63#a +  and 10 CFR 50.63#a1 +

05000280  +, 05000281  +, 05000338  +  and 05000339  +

Hartz L +  and Dominion +

GDC 14 +  and GDC 31 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +

ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +, ML022130481 +  and ML022130481 +

NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +

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-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-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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1344, Advises That Util 890710 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion &/Or Corrosion Acceptable,Based on Confirmation That Erosion/Corrosion Program Meets or Exceeds App a to NUREG-1344 Requirements +, 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 +

07-01-647 +, 07-02-332 +, 07-02-297 +  and 07-02-360 +

Surry +  and North Anna +

Washington +, Virginia +  and Idaho +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Main Steam +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, High Energy Line Break +, Aging Management +, Design basis earthquake +, Flow Accelerated Corrosion +, Loss of Offsite Power +, License Renewal +, Earthquake +, Maintenance Rule Program +, Control of Heavy Loads +, Biofouling +, Fire Protection Program +, Thermal fatigue +  and Leak-Before-Break +