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

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 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

NRC 1975 +  and NRC 50 +

05000354  +  and 00354  +

Regulatory Guide 1.174 +, ML12053A340 +, ML14111A147 +, ML15364A544 +, ML090930246 +, ML052580075 +, ML17026A001 +, ML16049A609 +, ML052580118 +, ML103090242 +, ML14237A034 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, LR-N17-0077, Focused Evaluation of External Flooding +, 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 +, ML14071A505 +, LR-N17-0109, Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies +, ML17275A945 +, ML15169A282 +, LR-N15-0256, High Frequency Supplement to Seismic Hazard Screening Report, 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 +, ML14127A006 +, LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic +, ML14056A344 +, CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information +, LR-N18-0032, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension +, ML18180A062 +, ML18269A252 +, CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) +, ML19065A156 +...

PSEG +  and Fleming J +

LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +...

IR 05000354/2017010 +, LR-N17-0109, Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies +  and LR-N17-0075, Stations Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number . +

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 +

NRC 1975 +  and NRC 50 +

NUREG/CR-5750 +, NUREG/CR-4550 +, NUREG/CR-6928 +, NUREG/CR-7150 +, NUREG/CR-2300 +, NUREG/CR-4639 +, NUREG/CR-2728 +, NUREG-2168 +, NUREG-1715, Identical Letters - Request for Review of Reliability Study: NUREG-1715, Vol. X, Component Performance Study - Air-Operated Valves, 1987-1998 (Draft) +, 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 +  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 +

ESP +  and Emergency Operating Procedure +

TAC:ME9472 +, CAC:MF9861 +, CAC:MG0036 +, CAC:MF3924 +, TAC:MF0132 +, TAC:MD5250 +  and TAC:M83630 +

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

RIS 2015-06, Tornado Missile Protection +  and RIS 2007-06, Implementation +

1E-6 +, 1E-11 +, 1E-5 +, 1E-06 +, 5E-7 +  and 1E-12 +

Illinois +, Washington +, New Jersey +, New York +, Arkansas +  and Delaware +

Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +  and Circulating Water System +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, 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 +, Seismic Walkdown Report +, Overspeed +, Control Room Habitability +  and Basic Component +