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Letter type:L  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 50.92 +, 10 CFR 50.69#e +, 10 CFR 50.69#c1 +, 10 CFR 50.69#b2i +, 10 CFR 50.69#b2ii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#b2 +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#c +, 10 CFR 50.54#f +, 10 CFR 50.91#b1 +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +

NRC 1975 +, L-2025-015 +  and L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +

05000443  +  and 00443  +

Regulatory Guide 1.174 +, ML12053A340 +, ML15194A015 +, ML090930246 +, ML14237A034 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information +, 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 +, SBK-L-17084, Mitigating Strategies Assessment (MSA) Report for Impact of New Flooding Hazard Information on FLEX Strategies +, SBK-L-17136, Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information +, ML14365A203 +, RIS 2007-06, Implementation +, RIS 2015-06, Tornado Missile Protection +, ML061090627 +, ML052910035 +, ML15282A019 +, ML15208A049 +, SBK-L-14052, NextEra Energy Seabrook, LLC Seismic Hazard and Screening Report (CEUS Sites) 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- +, ML13364A311 +, ML12340A486 +, SBK-L-13159, Supplement to Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic +, 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) +, ML18039A920 +, CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information +, ML18115A509 +, ML17062A466 +, ML18157A260 +, ML18138A451 +...

Mack K +  and NextEra Energy Seabrook +

L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +  and L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +

8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +  and L-2025-015 +

ML20031D699 +  and ML20298A253 +

NEI 00-04 +, NEI 07-12 +, NEI 05-04 +, NEI 12-13 +, 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-7150 +, 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-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +, 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 +

ES-B4 +  and ES-A2 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, Regulatory Guide 1.201 +, Regulatory Guide 1.91 +  and Regulatory Guide 1.17 +

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

7E-12 +, 1E-7 +  and 8E-9 +

Tennessee +, Washington +, Massachusetts +, Arkansas +, New Hampshire +  and Maine +

Steam Generator +, Service water +, Emergency Diesel Generator +  and Control Room Envelope +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, Ultimate heat sink +, Fire Barrier +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Incorporated by reference +, FLEX +, Fukushima Dai-Ichi +, Large early release frequency +, Loss of Offsite Power +, Frazil ice +, Turbine Missile +, Seismic Walkdown Report +, Control Room Habitability +  and Basic Component +

Cooling Tower +  and Atlantic Ocean +