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

Carbon +, Chlorine +  and Lead +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 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#c +, 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 +

NRC 1975 +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA 0089 +  and RA-19-0085, License Amendment Request to Revise Technical Specifications to Adopt Risk-Inormed Completion Times TST-505, Revision 2, Provide RIsk-Informed Extended Completion Times - RITSTF Initiative 4b and TSTF-591, Revision 0. +

05000413  +, 05000414  +, 00413  +  and 00414  +

ML12053A340 +, ML090930246 +, ML14237A034 +, ML16137A308 +, 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 +, ML17230A088 +, ML16344A313 +, ML14093A052 +, ML16072A037 +, MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, ML16222A368 +, ML18040A454 +, ML13338A171 +, ML14108A201 +, CNS-14-038, DUKCORP042-PR-001, Seismic Hazard & Screening Report in Response to the 50.54(f) Information Request Re Fukishima Near-Term Task Force Recommendation 2.1 Seismic +, MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the +, ML13003A339 +, ML110670536 +, 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 +, ML18115A138 +, ML18180A062 +, CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task +, 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) +, RA-18-0162, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal +, ML19115A267 +...

Huecker J +  and Duke Energy +

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 +

RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +  and RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +

RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +  and ML16344A313 +

NEI 00-04 +, NEI 07-12 +, NEI 05-04 +, NEI 17-07 +  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/CR-2300 +, 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-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 +

TAC:ME9472 +, CAC:MF9879 +, TAC:MD5250 +, EPID:L-2018-LLA-0493 +, EPID:L-2018-LLA-0482 +  and EPID:L-2018-JLD-0010 +

RA-18-0089, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, RA 0089 +  and RA-19-0085, License Amendment Request to Revise Technical Specifications to Adopt Risk-Inormed Completion Times TST-505, Revision 2, Provide RIsk-Informed Extended Completion Times - RITSTF Initiative 4b and TSTF-591, Revision 0. +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, Regulatory Guide 1.201 +  and Regulatory Guide 1.17 +

1E-6 +, 1E-5 +, 1E-4 +, 1E-7 +  and 1E-07 +

NPF-35 +  and NPF-52 +

Tennessee +, Washington +, South Carolina +  and Arkansas +

Service water +, Emergency Diesel Generator +, Control Room Envelope +  and Auxiliary Feed Water +

TSTF-505 +  and TSTF-425 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High winds +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Incorporated by reference +, Fukushima Dai-Ichi +, Large early release frequency +, Loss of Offsite Power +, Flooding Focused Evaluation +, Turbine Missile +, Seismic Walkdown Report +, Basic Component +  and Spill +