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ANSI/ANS 3.1-1978 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

IWC-3000 +, IWB-3000 +, IWA-3000 +, IWA-2432 +  and IWA-4000 +

ASME Section XI +, ASME Section IX +  and ASME Section V +

Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chlorine +, Chloride +, Lead +, Lithium +, Aluminum +, Silicon +, Titanium +  and Tungsten +

BWRVIP-79 +, BWRVIP-130 +  and BWRVIP-29 +

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.55a +  and 10 CFR 50.49#b1 +

SECY-99-148 +  and SECY-99-149 +

05000293  +  and 00293  +

EN-DC-167 +, EN-DC-141 +, EN-WM-101 +, EN-DC-343 +, EN-DC-174 +  and EN-DC-147 +

Shaw +, Entergy +, LLP +, Pillsbury +, Winthrop +, Pittman +  and Gaukler P +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +, ML080160268 +  and ML080160268 +

Union of Concerned Scientists +  and Pilgrim Watch +

LBP-06-23 +  and LBP-07-12 +

A109 +  and Westinghouse +

NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +  and NEI 07-07, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 +

NRC Bulletin 80-13 +  and NRC Bulletin 89-01 +

Information Notice 97-19 +, Information Notice 84-18 +, Information Notice 91-05 +, Information Notice 97-88 +  and Information Notice 96-11 +

NUREG/CR-6876 +, NUREG-1522 +, NUREG-1544 +, NUREG/CR-6490 +, NUREG-6876 +, NUREG/CR-6001 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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 +

Brian Sullivan +, Mary Lampert +  and Joseph Pechacek +

RT +  and CP +

SECY-99-148 +  and SECY-99-149 +

07-61-160 +  and 4rE-S +

Texas +, Tennessee +, Connecticut +, Washington +, Massachusetts +, New York +, Oklahoma +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Coatings +, Nondestructive Examination +, VT-2 +, Aging Management +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Biofouling +, Fire Protection Program +  and Downpower +