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Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.69#e +, 10 CFR 50.69#b2i +, 10 CFR 50.69#b2ii +, 10 CFR 50.69#b2iii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#b2 +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#f1 +, 10 CFR 50.69#c +, 10 CFR 50.69#c1i +, 10 CFR 50.54#f +, 10 CFR 50.91#a1 +, 10 CFR 50.48#c +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

NRC 1975 +  and NRC 50 +

05000382  +  and 00382  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, ML12053A340 +, ML090930246 +, ML052580075 +, ML16159A419 +, ML052580118 +, ML12216A104 +, ML14237A034 +, ML17079A427 +, ML17086A431 +, ML16126A033 +, ML15363A374 +, ML14365A203 +, ML15335A050 +, ML061090627 +, ML052910035 +, ML031150485 +, W3F1-2014-0023, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Wa +, ML17062A466 +, ML14189A696 +  and ML071340053 +

Reactor Trip +  and Turbine Trip +

Entergy +  and Gaston R +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +, W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +  and W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +

NEI 00-04 +, NEI 07-12 +, NEI 05-04 +  and NEI 12-13 +

NRC 1975 +  and NRC 50 +

NUREG/CR-5750 +, NUREG-1921 +, NUREG/CR-7150 +, NUREG/CR-2300 +, NUREG-7150 +, 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-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

ES-C2-01 +, ES-C2 +, ES-A2 +, ES-A2-01 +, ES-A3-02 +, ES-B4 +  and ES-A3 +

CAC:ME7602 +, CAC:MF6366 +, TAC:MF3712 +  and TAC:MD5250 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.147 +  and Regulatory Guide 1.201 +

1E-6 +, 1E-5 +, 1E-7 +, 1E-06 +, 3E-6 +, 5E-03 +, W3F1-2014-0023, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Wa +  and W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors +

Washington +, Louisiana +, Mississippi +  and Arkansas +

Steam Generator +, Feedwater +, Emergency Diesel Generator +, Reactor Pressure Vessel +  and Containment Spray +

TSTF-505 +  and TSTF-425 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, Ultimate heat sink +, Mission time +, Fire Barrier +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, High Energy Line Break +, Fukushima Dai-Ichi +, Tornado Missile Protection +, Thermoset +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Fire Protection Program +, Fire Watch +, Seismic Walkdown Report +  and Basic Component +

Cooling Tower +  and Mississippi River +