Browse wiki

Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation  and Technical Specifications

Boron +, Iodine +, Cesium +, Uranium +, Copper +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Lead +  and Aluminum +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 40 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.4 +, 10 CFR 50.49 +, 10 CFR 50 Appendix I +, 10 CFR 100.11 +, 10 CFR 50.55a +, 10 CFR 50.67#b +, 10 CFR 50.54#0 +, 10 CFR 54.21#d +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e4 +

L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +  and L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +

05000250  +, 05000251  +, 00250  +  and 00251  +

ML053460347 +, ML011210348 +, ML012190402 +, ML110800666 +, L-2011-141, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Systems Issues +, L-2010-293, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) No. 196 and Meteorological Data Sensitivity +, L-2010-226, Summary of NRC Public Meeting Discussion on Meteorological Data for Alternative Source Term and Conforming License Amendment Request 196 +, L-2010-197, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System +, L-2010-136, Revised Meteorological Data for 2005-2009 with T Bias Supporting Alternative Source Term and Conforming License Amendment Request 196 +, L-2010-137, Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 196 +, L-2010-131, Response to 5/28/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 +, L-2010-121, Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 196 +, L-2010-083, Supplement to License Amendment Request (LAR) 196 and 3/24/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) +, L-2010-082, Supplement to License Amendment Request 196 (ADAMS Accession No. ML092050112) - Revised Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results +, L-2010-065, Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 196 +, L-2010-048, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 +, L-2009-163, Transmittal of Meteorological Data Cd Supporting Alternative Source Term and Conforming License Amendment Request 196 - Supplemental Information +, L-2009-195, Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term +, L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results +, L-2009-133, License Amendment Request 196 Alternative Source Term and Conforming Amendment +  and L-2010-021, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request +

74 FR 68870 +  and 75 FR 39978 +

Jason Paige +  and Plant Licensing Branch II +

GDC 18 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 1, Quality standards and records +

ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +, ML110800666 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 0.00353 d (0.0847 hours, 5.042989e-4 weeks, 1.160525e-4 months)  +, 7.291667e-4 d (0.0175 hours, 1.041667e-4 weeks, 2.39715e-5 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 0.00935 d (0.224 hours, 0.00134 weeks, 3.07444e-4 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0.0177 d (0.424 hours, 0.00252 weeks, 5.802625e-4 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 7.060185e-4 d (0.0169 hours, 1.008598e-4 weeks, 2.32105e-5 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

Tritium +, Kr-85 +  and Iodine-131 +

L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +  and L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +

IR 05000250/2003002 +, L-2010-197, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System +, ML100351459 +, ML102380468 +, L-2010-121, Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 196 +, L-2010-065, Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 196 +, L-2009-163, Transmittal of Meteorological Data Cd Supporting Alternative Source Term and Conforming License Amendment Request 196 - Supplemental Information +, L-2009-195, Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term +, L-2009-133, License Amendment Request 196 Alternative Source Term and Conforming Amendment +  and L-2010-021, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request +

NEI 99-03 +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NUREG-1431 +, NUREG/CR-5950 +, NUREG/CR-6604 +, NUREG/CR-2858 +, NUREG-0917 +, NUREG/CR-4102 +, NUREG/CR-55009 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG/CR-5009, Forwards NUREG/CR-5009, Assessment of Use of Extended Burnup Fuel in Lwrs. Rept Concludes That Environmentally, Burnup Increase Would Have No Significant Impact Over That of Normal Burnup.W/O Encl +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, 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 +, NUREG-0409, Discusses NUREG-0409 Iodine Behavior in PWR Cooling Sys Following Postulated Steam Generator Tube Rupture Accident +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Dan Hoang +, John Parillo +, Matthew Yoder +  and Jason White +

TAC:ME1624 +  and TAC:ME4470 +

TAC:ME1624 +  and TAC:ME4470 +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.163 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.23 +  and Regulatory Guide 1.145 +

SR-4.7.9 +  and SR-4.4.8 +

5A-1 +, 95th-percent +, 3D-second +  and 3D-minute +

Fort Calhoun +  and Turkey Point +

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Control Room Emergency Ventilation +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.0.1 +, TS-3.0.4 +, TS-3.4.6.2 +, TS-3.7.5 +, TS-3.4.8 +, TS-3.7.9 +, TS-6.8.4.h +, TS-6.8 +, TS-6.8.4.j +, TS-1.13 +, TS-1.12 +, TS-3.4.8.b +, TS-6.9.1.2 +, TS-4.7.5.b +  and TS-4.7.5.c +

NextEra Energy +  and Nazar M +

Safe Shutdown +, Boric Acid +, Packing leak +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, High Energy Line Break +, Tornado-Generated Missile +, Annual Radioactive Effluent Release Report +, Design basis earthquake +, Stress corrosion cracking +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, GOTHIC +, Power Uprate +, Manual Operator Action +, Operational leakage +, Loss of condenser vacuum +  and Control Room Habitability +