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

Carbon +, Sodium +, Chlorine +  and Lead +

10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 10 +, 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#c1i +, 10 CFR 50.54#f +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

RS-15-069, Enclosure 3: G.E. Ginna Nuclear Power Plant Combined Events Flood Analysis, Calculation 32-9190280-000, Rev. 0 +, NRC 1975 +, NRC 50 +  and RS-18-098, Seismic Probabilistic Risk Assessment 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 . +

05000244  +, 00244  +, 00317  +, 00318  +, 00220  +  and 00410  +

Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, ML12053A340 +, ML14099A196 +, ML15364A544 +, ML090930246 +, ML051400209 +, ML14237A034 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, ML17079A427 +, ML17086A431 +, ML16125A485 +, ML16166A294 +, ML15153A026 +, RIS 2015-06, Tornado Missile Protection +, RS-15-288, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident +, ML14134A133 +, CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information +, ML17062A466 +, ML18115A138 +, ML18180A062 +, 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) +, ML19200A216 +, ML1718A485 +, ML19053A469 +, ML19183A012 +, ML19217A143 +, ML19330D909 +, ML20076A194 +, RS-20-139, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 +...

Exelon +  and David Gudger +

ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +, ML21141A009 +...

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

NRC 1975 +  and NRC 50 +

NUREG/CR-4550 +, 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/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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  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 +

CAC:MF9861 +, TAC:MF3972 +, TAC:MF0104 +, CAC:MF9879 +, TAC:MD5250 +, EPID:L-2018-LLA-0493 +, EPID:L-2018-LLA-0482 +, EPID:L-2018-JLD-0010 +  and TAC:M83624 +

RS-18-098, Seismic Probabilistic Risk Assessment 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 . +  and RS-15-069, Enclosure 3: G.E. Ginna Nuclear Power Plant Combined Events Flood Analysis, Calculation 32-9190280-000, Rev. 0 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.147 +, Regulatory Guide 1.201 +  and Regulatory Guide 1.91 +

1E-6 +  and 1E-5 +

Calvert Cliffs +  and Ginna +

Illinois +, Washington +, New York +  and Arkansas +

Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Decay Heat Removal +  and Control Room Envelope +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, Ultimate heat sink +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Zebra Mussel +, Multiple Spurious Operation +, Incorporated by reference +, Fukushima Dai-Ichi +, Tornado Missile Protection +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Turbine Missile +, Seismic Walkdown Report +, Control Room Habitability +  and Basic Component +