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License-Application for Facility Operating License (Amend/Renewal) DKT 50  and Letter type:

ASME Section XI +, ASME Section III +  and ASME Section IX +

Chlorine +, Lead +  and Bromine +

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#c1 +, 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#c1i +, 10 CFR 50.54#f +, 10 CFR 50.48#c +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

1CAN052102 +  and NRC 1975 +

05000313  +, 00313  +, 00373  +  and 00374  +

Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, ML12053A340 +, ML14136A126 +, ML090930246 +, ML17261B103 +, ML15344A109 +, ML063550238 +, ML17257A042 +, ML14237A034 +, ML17093A859 +, ML16223A481 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, ML17079A427 +, ML17086A431 +, CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, ML16260A060 +, ML17248A493 +, 0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3 +, ML14310A033 +, ML17214A029 +, 0CAN111401, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima +, ML14051A188 +, ML123420302 +, NL-18-0188, License Amendment Request to Incorporate Seismic Probabilistic Risk Assessment Into the 10 CFR 50.69 Categorization Process, Response to Request for Additional Information (RAIs 4-11) +, CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information +, ML18157A260 +, ML011710071 +, ML011710100 +...

Entergy +  and Gaston R +

1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +...

0CAN051703, Mitigating Strategies for Flooding +  and 0CAN051701, Response to Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations +

NEI 00-04 +, NEI 07-12 +, NEI 05-04 +, NEI 12-13 +  and NEI 12-06, Ne 12-06, Appendix H, Revision 2, H.4.3 Path 3: GMRS ≫ SSE ≪ IHS, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information +

NUREG-1921 +, NUREG/CR-7150 +, NUREG/CR-2300 +, NUREG-7150 +, NUREG-2180, Enclosure, NRC Response to NEI Concerns Dated July 28, 2016, Regarding Tabletop Pilot Results Using NUREG-2180 +, NUREG-2169, NUREG 2169 Suppression Data Set +, 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/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  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 +

CAC:MF3822 +, CAC:MF9861 +, TAC:MF3419 +, CAC:MF9809 +, TAC:MF0090 +, TAC:MD5250 +, EPID:L-2020-LLA-0017 +  and TAC:M69426 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.147 +, Regulatory Guide 1.76 +  and Regulatory Guide 1.201 +

SR-3.7.9.4 +  and SR-3.0.2 +

1E-6 +, 1E-5 +, 1E-7 +, 1E-9 +  and 1E-08 +

LaSalle +  and DPR-51 +

Tennessee +, Washington +  and Arkansas +

Service water +, Decay Heat Removal +  and Control Room Envelope +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, Ultimate heat sink +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, Incorporated by reference +, FLEX +, Fukushima Dai-Ichi +, Tornado Missile Protection +, Large early release frequency +, Loss of Offsite Power +, Flooding Focused Evaluation +, Fire Protection Program +, Very Early Warning Fire Detection +, Seismic Walkdown Report +, Overspeed +, Control Room Habitability +  and Basic Component +