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

Sodium +, Chlorine +  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#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#f1 +, 10 CFR 50.69#c +, 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 +

05000272  +, 05000311  +, 00272  +  and 00311  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML12053A340 +, ML14136A126 +, ML15364A544 +, ML090930246 +, Regulatory Guide 1.115 +, ML16351A231 +, ML16041A033 +, ML14237A034 +, ML070810400 +, ML17101A604 +, 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 +, LR-N17-0076, Focused Evaluation of External Flooding +, ML14071A401 +, ML16265A085 +, LR-N16-0094, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident +, ML031140185 +, ML14365A203 +, ML061090627 +, ML052910035 +, ML14113A236 +, ML15169A283 +, ML031150485 +, LR-N12-0372, Response to Recommendation 2.3: Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident +, 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 +...

Reactor Trip +  and Turbine Trip +

OP-AA-108-111-1001 +  and ER-AA-310-101 +

PSEG +  and Sharbaugh D +

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 +

LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +, LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors +...

Westinghouse +  and General Electric +

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-7150 +, 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-2230, Review of Disposition of CNWRA Comments on Draft NUREG-2230 (09-23-2019) +, NUREG/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +, 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 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.147 +, Regulatory Guide 1.201 +  and Regulatory Guide 1.115 +

1E-6 +, 1E-5 +, 1E-7 +, 1E-02 +  and 1E-04 +

Washington +, New Jersey +, Arkansas +  and Delaware +

Service water +, HVAC +  and Emergency Core Cooling System +

TSTF-591 +  and TSTF-505 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, Non-Destructive Examination +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Zebra Mussel +, Multiple Spurious Operation +, Incorporated by reference +, FLEX +, Aging Management +, Fukushima Dai-Ichi +, Large early release frequency +, Loss of Offsite Power +, License Renewal +, Turbine Missile +, Seismic Walkdown Report +, Overspeed +, Control Room Habitability +  and Basic Component +