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

Lead +  and Chlorine +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 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#f1 +, 10 CFR 50.69#c1i +, 10 CFR 50.54#f +, 10 CFR 50.91#b1 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

Initiating Events +  and Mitigating Systems +

05000263  +  and 00263  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML090930246 +, ML090970525 +, ML14237A034 +, ML17103A235 +, ML17079A427 +, ML15167A401 +, ML16145A179 +, ML15167A411 +, ML14365A203 +, RIS 2007-06, Implementation +, ML061090627 +, ML052910035 +, L-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program +, ML031150485 +  and ML17086A450 +

Church C +  and Xcel Energy +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +  and L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +

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

NUREG-1921 +, NUREG/CR-4772 +, NUREG-1934 +, 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 +, 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 +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +

ES +  and TP +

TAC:ME9472 +, CAC:MF7359 +, TAC:MD5250 +  and TAC:M83644 +

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

Minnesota +, Washington +  and Arkansas +

Feedwater +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Core Spray +  and Control Room Envelope +

TS-5.5.11 +  and TS-5.5.13 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Ultimate heat sink +, Tornado Missile +, Internal Flooding +, Probabilistic Risk Assessment +, Large early release frequency +, Loss of Offsite Power +, Turbine Missile +  and Basic Component +