Browse wiki

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

Tin +  and Lead +

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#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#c +, 10 CFR 50.54#f +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +

WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response 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 the Fukushima Dai-ichi Accident +, NRC 1975 +  and WO 14-0042, Operating Corp.S Seismic Hazard and Screening Report (CEUS Sites), Response 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 the Fukushima +

ML12053A340 +, ML15194A015 +, ML090930246 +, ML14237A034 +, ML17073A148 +, NL-16-2382, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process +, ML17079A427 +, 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 +, ML15216A320 +, ML16335A371 +, ML17086A451 +, ML15350A220 +, ML18012A506 +, WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response 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 the Fukushima Dai-ichi Accident +, ML14034A054 +, ML123420431 +, 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 +, ML17086A450 +, ML18262A415 +, 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) +, RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +, ML19200A216 +, ML19053A469 +, ML19183A012 +, ML19217A143 +, ML111720076 +...

Boyce M +  and Wolf Creek +

NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +, ML25030A384 +...

WO 04-0051, Operating Corporation Response to Generic Letter 2003-01: Control Room Habitability +, ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI +  and CAC:9639 +

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-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-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, 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 +

TAC:ME9472 +, TAC:MD5250 +  and EPID:L-2020-LLA-0091 +

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

1E-5 +  and 1E-6 +

Tennessee +, Kansas +, Washington +  and Arkansas +

Emergency Diesel Generator +  and Service water +

TSTF-505 +  and TSTF-425 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High winds +, Ultimate heat sink +, 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 +

WO 14-0042, Operating Corp.S Seismic Hazard and Screening Report (CEUS Sites), Response 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 the Fukushima +  and WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response 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 the Fukushima Dai-ichi Accident +