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Boron +, Nitrogen +, Oxygen +, Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.65 +, 10 CFR 50.55a#f +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#b +, 10 CFR 50.55a#b3 +, 10 CFR 50.55a#f6i +, 10 CFR 50.55a#f5 +, 10 CFR 50.55a#f5iii +, 10 CFR 50.55a#f4ii +, 10 CFR 50.55a#f4iv +, 10 CFR 50.55a#fiv +  and 10 CFR 50.55a#f1 +

05000293  +  and 00293  +

Entergy +  and Riggs W +

NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +  and NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +

ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +, ML023500381 +  and ML023500381 +

0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

Union Pump +  and General Electric +

NUREG-1493 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1352, Informs Commission of Status of Activities That NRC Performing & Has Planned to Resolve Concerns W/Performance of MOVs & Check Valves in Nuclear Power Plants +  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 +

Bryan Ford +  and Travis Tate +

ST +  and RT +

Regulatory Guide 1.163 +  and Regulatory Guide 1.26 +

6D-2 +, 11C-6 +, 21G-4 +, 25AE-6 +, 8J-17 +, 81R-01 +, 8M3-2VR0 +, 8VR-01 +  and 0C-U +

Washington +  and Vermont +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

TS-7.1 +  and TS-8.1.1.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High Radiation Area +, Ultimate heat sink +, Stroke time +, Squib +, Locked High Radiation Area +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Excess Flow Check Valve +, Cold shutdown justification +, Power-Operated Valves +, Power Operated Valves +, Scaffolding +  and Downpower +