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IWA-6000 +, IWA-1400 +, IWA-1320 +, IWA-4000 +, IWA-9000 +, IWA-4120 +  and IWA-1000 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Lead +  and Carbon +

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.12 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 50.69#b1 +, 10 CFR 50.69#b1v +, 10 CFR 50.69#d2 +, 10 CFR 50.69#b2 +, 10 CFR 50.69#c +, 10 CFR 50.54#a4 +, 10 CFR 50.54#a3 +, 10 CFR 50.54#a3ii +, 10 CFR 50.69#69 +, 10 CFR 50.69#a +, 10 CFR 50.69#c1v +, 10 CFR 50.54#a4ii +, 10 CFR 50.69#b3 +, 10 CFR 50.57#a +, 10 CFR 50.55a#z1 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#f +, 10 CFR 50.55a#h +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +...

ASME Code Case N-660 +, ASME Code Case N-752 +, ASME Code Case N-752-1 +  and ASME Code Case N-752-2 +

NRC-002 +, RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. +, RA 0174 +, SECY-23-0061, Clarification of the Staff’S Position on Certain American Society of Mechanical Engineers Code Alternatives for More than One 10-Year Inservice Inspection Interval Under Title 10 of the Code of Federal Regulations 50.55a +  and SECY 04-0109 +

DPO-2024-002 +  and DPO-2024-001 +

05000269  +, 05000270  +, 05000287  +  and 00348  +

Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, ML090930246 +, ML14237A034 +, NL-14-0580, Pilot 10 CFR 50.69 License Amendment Request - Response to Request for Additional Information +, NL-12-0932, Pilot 10 CFR 50.69 License Amendment Request +, ML031430373 +, 0CAN052003, Relief Request Number EN-20-RR-001 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems, Section XI, Division 1 +, 0CAN112001, Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 1 +, 0CAN042105, Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operations Quality Assurance Program Manual Description +, ML21132A279 +, ML21118B039 +, ML22235A655 +, RA-23-0051, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities +, ML23038A183 +, ML23178A068 +, DT-23-17, Management Directive 10.159, NRC Differing Professional Opinion Program +, RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. +, ML23270B836 +, ML23269A041 +, ML23284A332 +, ML23219A140 +, RA-23-0282, Second Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement +, ML23331A921 +, ML23262A967 +, ML24101A388 +, ML24311A153 +, 0CAN042101, Response to Request for Additional Information Reduction of Commitment to the Entergy Operations Quality Assurance Program Manual Description +, 0CAN102002, Reduction of Commitment to the Entergy Operations Quality Assurance Program Manual Description +, Information Notice 2025-01, Lessons Learned with Implementing ASME Code Case N-752 +...

69 FR 68008 +, 69 FR 68014 +, 50 FR 50764 +, 69 FR 68047 +  and 69 FR 68019 +

Mark King +, Office of Nuclear Reactor Regulation +, Jordan Hoellman +  and Figueroa-Toledo G +

NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +, ML25160A235 +  and ML25160A235 +

IEEE 279 +  and IEEE 603-1991 +

RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. +  and ML20304A369 +

NEI 00-04 +  and NEI 16-09 +

LIC-105 +  and LIC-102 +

NUREG/CR-6752 +, NUREG/CR-5140 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Michael King +, Brian Smith +, Jay Collins +, Stephen Cumblidge +, Victor Hall +, Stewart Bailey +, Dan Widrevitz +, Andrea Veil +, David Pelton +, Robert Tregoning +, Sheldon Clark +, Thomas Scarbrough +, Samuel Lee +, Matthew Mitchell +, John Honcharik +  and Jordan Hoellman +

EPID:L-2022-LLR-0060 +  and TAC:ME9472 +

RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. +  and RA 0174 +

Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, Regulatory Guide 1.201 +, Regulatory Guide 1.84 +  and Regulatory Guide 1.26 +

SECY 04-0109 +  and SECY-23-0061, Clarification of the Staff’S Position on Certain American Society of Mechanical Engineers Code Alternatives for More than One 10-Year Inservice Inspection Interval Under Title 10 of the Code of Federal Regulations 50.55a +

1x10-8 +  and 1E-5 +

Emergency Feedwater System +  and Reactor Coolant System +

Jay Collins +, Stephen Cumblidge +, Dan Widrevitz +, Thomas Scarbrough +, Matthew Mitchell +, John Honcharik +  and Office of Nuclear Reactor Regulation +

Non-Destructive Examination +, Probabilistic Risk Assessment +, Nondestructive Examination +, Incorporated by reference +, Aging Management +, Flow Accelerated Corrosion +, License Renewal +, Very Low Safety Significance Issue Resolution +, Liquid penetrant +, Backfit +  and Thermal binding +