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

Lead +  and Chlorine +

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

RS-16-180, Submittal of Mitigating Strategies Flood Hazard Assessment +, RS-14-052, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report +, RS-14-053, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report +, RS-15-112 +, NRC 1975 +  and RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +

05000454  +, 05000455  +, 05000456  +, 05000457  +, 00456  +, 00457  +, 00454  +  and 00455  +

ML090930246 +, ML14308A048 +, ML15344A346 +, ML17079A427 +, ML17086A431 +  and ML15061A237 +

David Gullott +  and Exelon +

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

RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +  and RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

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

NUREG/CR-6928 +, NUREG/CR-6890 +, NUREG/CR-7150 +, NUREG/CR-1829 +, NUREG/CR-2300 +, NUREG-1920 +, NUREG-1524 +, 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/CR-2169 +, 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-1829, White Paper on Continued Applicability of NUREG-1829 +  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 +

May Ma +  and Bryan Hanson +

TAC:ME9472 +, TAC:MF3893 +, TAC:M83600 +  and TAC:M83665 +

RS-16-180, Submittal of Mitigating Strategies Flood Hazard Assessment +, RS-14-052, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report +, RS-14-053, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report +, RS-15-112 +  and RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +

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

RIS 2007-06, Implementation +  and RIS 2008-14, Use of TORMIS Computer Code for Assessment of Tornado Missile Protection +

1E-6 +, 1E-5 +  and 1E-06 +

Byron +  and Braidwood +

Byron +, Braidwood +  and NPF-66 +

Illinois +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Service water +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Remote shutdown +, Decay Heat Removal +  and Safety Relief Valve +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Hot Short +, Safe Shutdown +, High winds +, Ultimate heat sink +, Mission time +, Tornado Missile +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, High Energy Line Break +, Tornado Missile Protection +, Large early release frequency +, Loss of Offsite Power +, TORMIS +, Control Room Habitability +  and Basic Component +

Cooling Tower +  and Kankakee River +

WCAP-15603 +, WCAP-16341-P +, WCAP-16362-NP +  and WCAP-1192 +

WCAP-15603 +, WCAP-16341-P +, WCAP-16362-NP +  and WCAP-1192 +