Browse wiki

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

Tennessee Department of Environment and Conservation +  and American Society of Civil Engineers +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50.69#b2ii +, 10 CFR 50.69#b2iii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#b2 +, 10 CFR 50.69#c1i +, 10 CFR 50.54#f +, 10 CFR 50.91#b1 +, 10 CFR 50.69#2 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 50.69#2I +, 10 CFR 50.69#b2I +  and 10 CFR 50.92#c +

05000327  +, 05000328  +  and 00327  +

Regulatory Guide 1.200 +, ML090930246 +, ML090970525 +, ML14237A034 +, ML070660454 +, ML17079A427 +, ML17086A431 +, ML14365A203 +, RIS 2007-06, Implementation +, ML061090627 +, ML15238B460 +, ML13329A881 +, TSTF-09-10, Transmittal of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Sections 3.1.1 - 3.7.5 +, ML010520133 +  and TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791) +

Tennessee Valley Authority +  and James Shea +

CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +  and CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +

NUREG-1431 +, NUREG/CR-6928 +, NUREG/CR-2300 +, NUREG/CR-5042 +, 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 +  and 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 +

TAC:ME9472 +, TAC:MF3128 +, TAC:MD5250 +  and TAC:M83674 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.76 +, Regulatory Guide 1.201 +, Regulatory Guide 1.91 +  and Regulatory Guide 1.59 +

1E-10 +, 1E-06 +, 1E-07 +, 1E-08 +  and 1E-05 +

Tennessee +, Washington +  and Arkansas +

TSTF-425 +  and TSTF-446 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, High winds +, Ultimate heat sink +, Mission time +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, Large early release frequency +, Loss of Offsite Power +, Turbine Missile +, Control Room Habitability +  and Basic Component +