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

Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 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#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 +

L-2017-058, License Amendment Request to Revise the National Fire Protection Association Standard 805 Modifications +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2014-089, Florida Power & Light (FPL) Seismic Hazard & Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc +, L-92-222, Describes Seismic Program to Comply W/Suppl 4 to GL 88-20, IPEEE for Severe Accident Vulnerabilities, Per NRC .Implementation for Both Policy Statement on Severe Accidents & USI A-46 Employ Similar Methodologies +, L-94-107, Forwards Addl Info in Response to NRC on GL 87-02 Re Resolution of USI A-46 +, NRC 1975 +, L-93-171, Responds to Info Requested by NRC During 930720 Meeting Re USI A-46,including Narrative Describing How Safe Shutdown Will Be Accomplished & Proprietary Flowchart W/Regard to Relay Functionality.Flowchart Withheld,Per 10CFR2.790 +, L-91-336, Forwards Individual Plant Exams of External Events for Severe Accident Vulnerabilities,As Requested Per Generic Ltr 88-20,Suppl 4 +  and L-2014-242, Application to Adopt TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B +

05000335  +, 05000389  +, 00335  +  and 00389  +

ML12053A340 +, ML090930246 +, ML14237A034 +, ML15344A346 +, ML17079A427 +, ML17086A431 +, ML15352A053 +, ML17291A045 +, ML15127A066 +, L-2014-089, Florida Power & Light (FPL) Seismic Hazard & Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc +  and L-2014-242, Application to Adopt TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B +

Turbine Trip +  and Reactor Trip +

NextEra Energy +  and Deboer D +

NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +...

L-2017-058, License Amendment Request to Revise the National Fire Protection Association Standard 805 Modifications +, L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, L-2014-089, Florida Power & Light (FPL) Seismic Hazard & Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc +, L-92-222, Describes Seismic Program to Comply W/Suppl 4 to GL 88-20, IPEEE for Severe Accident Vulnerabilities, Per NRC .Implementation for Both Policy Statement on Severe Accidents & USI A-46 Employ Similar Methodologies +, L-94-107, Forwards Addl Info in Response to NRC on GL 87-02 Re Resolution of USI A-46 +, L-93-171, Responds to Info Requested by NRC During 930720 Meeting Re USI A-46,including Narrative Describing How Safe Shutdown Will Be Accomplished & Proprietary Flowchart W/Regard to Relay Functionality.Flowchart Withheld,Per 10CFR2.790 +, L-91-336, Forwards Individual Plant Exams of External Events for Severe Accident Vulnerabilities,As Requested Per Generic Ltr 88-20,Suppl 4 +  and L-2014-242, Application to Adopt TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B +

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

NUREG/CR-2300 +, NUREG-2178, Response to October 28, 2015, Letter Regarding the Availability of NUREG-2178, Refining and Characterizing Heat Release Rates from Electrical Enclosures During Fire (RACHELLE-FIRE), Volume 1: Peak Heat Release Rates and Effect of Obstruct +, 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-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 +

Emergency Operating Procedure +, EOP-15 +, ES-D1 +  and ES-D1-01 +

TAC:ME9472 +, EPID:L-2017-LRM-0020 +, TAC:MF3495 +, TAC:MD5250 +, CAC:MF1371 +  and TAC:M83636 +

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

1E-6 +, 1E-5 +, 1RAB43-59 +, 2RAB43-35 +, 2RAB43-36 +  and 2RAB-10-16B +

Illinois +, Washington +, New York +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Service water +, Shutdown Cooling +, Control Room Envelope +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Ultimate heat sink +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, Fukushima Dai-Ichi +, Large early release frequency +, Excess Flow Check Valve +, Earthquake +, Fire Protection Program +, Control Room Habitability +  and Basic Component +