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Inspection Report  and Letter

10 CFR 21 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 37 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50.43#q +, 10 CFR 50.54#q +, 10 CFR 50.54#q3 +, 10 CFR 50.54#q2 +, 10 CFR 50.65#a2 +, 10 CFR 50.65#a3 +, 10 CFR 50.55a#g4 +, 10 CFR 20.1501#c +  and 10 CFR 50.71#e +

CR-RBS-2024-04013 +, CR-RBS-2024-04957 +, CR-RBS-2024-04624 +, CR-HQN-2024-00965 +, CR-HQN-2024-01160 +, CR-HQN-2024-01270 +, CR-RBS-2025-04165 +, CR-RBS-2025-02935 +, CR-RBS-2025-02974 +, CR-RBS-2025-04396 +, CR-RBS-2025-03250 +, CR-RBS-2025-04140 +, CR-RBS-2025-04234 +, CR-RBS-2025-00052 +, CR-RBS-2023-00079 +, CR-RBS-2023-00086 +, CR-RBS-2025-00032 +, CR-RBS-2024-00061 +, CR-RBS-2025-04664 +, CR-RBS-2025-04782 +, CR-RBS-2025-04725 +, CR-RBS-2025-04758 +, CR-RBS-2023-06964 +, CR-RBS-2023-06969 +, CR-RBS-2025-04927 +, CR-RBS-2025-03175 +, CR-RBS-2025-03316 +, CR-RBS-2025-06390 +, CR-RBS-2023-01650 +, CR-RBS-2024-05199 +...

FCBT-MPC-HAZSEC +  and FCBT-MPC-TSP +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

05000458  +  and 00458  +

IR 05000458/2023040 +, 05000458/LER-2025-002-01, For River Bend Station, Unit 1, Unidentified Drywell Leakage Increase Results in Shutdown +, ML25345A229 +, 05000458/LER-2025-004, Unit 1, Unsecured Pressure Boundary Door Resulting in Condition That Could Have Prevented Fulfillment of a Safety Function +  and 05000458/LER-2025-003, Unit 1, Turbine Control Valve Closure Results in Loss of Safety Function +

EC-64533 +  and EC-54283633 +

EN-LI-102 +, EN-OP-104 +, EN-EP-305 +, EN-EP-306 +, EN-EP-308 +, EN-RW-106 +, EN-LI-118 +, EN-WM-102 +, EN-LI-104 +, EN-LI-114 +, EN-QV-109 +, EN-RP-302 +, EN-RP-303 +, EN-RP-121 +, EN-RP-301 +, EN-RW-104 +, EN-RW-105 +, EN-RP-317 +, EN-RW-102 +, EN-RW-103 +, EN-RP-143 +, EN-RP-311 +, EN-RP-315 +, EN-RP-312 +, EN-RP-313 +  and EN-RP-304 +

05000458/FIN-2022003-02 +, 05000458/FIN-2022010-01 +, 05000458/FIN-2022004-05 +, 05000458/FIN-2023001-02 +, 05000458/FIN-2023001-04 +, 05000458/FIN-2023003-02 +, 05000458/FIN-2023003-04 +, 05000458/FIN-2023003-05 +, 05000458/FIN-2024002-04 +, 05000458/FIN-2024003-01 +, 05000458/FIN-2024003-05 +, 05000458/FIN-2024004-02 +, 05000458/FIN-2023402-01 +, 05000458/FIN-2024403-01 +, 05000458/FIN-2025002-01 +, 05000458/FIN-2025003-01 +, 05000458/FIN-2025003-03 +, 05000458/FIN-2025003-04 +, 05000458/FIN-2025003-05 +  and 05000458/FIN-2025003-02 +

Douglas Dodson +  and NRC/RGN-IV/DORS/PBC +

ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +, ML25345A229 +  and ML25345A229 +

NRC Inspection Manual 0609 Appendix C +, NRC Inspection Manual 2515 +  and NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +

IP 71111.12 +, IP 71111.18 +, IP 71111.04 +, IP 71111.05 +, IP 71124.08 +, IP 71111.13 +, IP 71114.03 +, IP 71124.05 +, IP 71114.06 +, IP 71114.02 +, IP 71114.05 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71130.01, Access Authorization +, IP 71111.11Q +, IP 71130.04, Security Equipment +, IP 71130.05 +, IP 92723 +, IP 71152A +, IP 71152, Problem Identification and Resolution (PI&R) +, IP 71111.24 +, IP 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response) Inputs +  and IP 71152S, Semiannual Trend Review +

Cs-137 +  and Sr-90 +

05000458/LER-2025-002 +, 05000458/LER-2025-004, Unit 1, Unsecured Pressure Boundary Door Resulting in Condition That Could Have Prevented Fulfillment of a Safety Function +  and 05000458/LER-2025-003, Unit 1, Turbine Control Valve Closure Results in Loss of Safety Function +

83CS-26 +  and 07-83-758 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Control Room Envelope +  and Moisture Separator Reheater +

TS-5.4.1.a +  and TS-3.7.7.B +

Hansett P +  and Entergy +

Fitness for Duty +, Ultimate heat sink +, Enforcement Discretion +, Probabilistic Risk Assessment +, Temporary Modification +, Functionality Assessment +, FLEX +, B.5.b +, Significance Determination Process +, Annual Radioactive Effluent Release Report +, Notice of Violation +, Process Control Program +, Large early release frequency +, Operability Determination +, Maintenance Rule Program +, Very Low Safety Significance Issue Resolution +, Pressure Boundary Leakage +, Fire Protection Program +, Substantial potential for an overexposure +, Overexposure +  and Control Room Habitability +

FLP-SEC-PT37SNM +  and FLP-ESPO-DESLIC +

WO 53029682 +, WO 00537910 +  and WO 00559096#01 +