Browse wiki

Safety Evaluation Report  and NUREG

Atomic Energy Act of 1954 +  and National Environmental Policy Act of 1969 +

Federal Energy Regulatory Commission +  and American Society of Civil Engineers +

Boron +, Iodine +, Uranium +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chlorine +, Chloride +, Lead +  and Aluminum +

BWRVIP-27 +, BWRVIP-42 +, BWRVIP-05 +, BWRVIP-06 +  and BWRVIP-74-A +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix H +, 10 CFR 51 Appendix B, Appendix B to Subpart A-Environmental Effect of Renewing the Operating License of a Nuclear Power Plant +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 54.22, Contents of Application--Technical Specifications +, 10 CFR 54.23, Contents of Application--Environmental Information +, 10 CFR 54.25, Report of the Advisory Committee On Reactor Safeguards +, 10 CFR 54.29 +, 10 CFR 100.11 +, 10 CFR 140.92 Appendix B +, 10 CFR 5421#a1 +, 10 CFR 54.4#a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 54.4#a1iii +, 10 CFR 50.49#b +, 10 CFR 50.49#b1 +, 10 CFR 50.67#b2 +...

05000324  +, 05000325  +, 00325  +  and 00324  +

IR 05000324/2005008 +, ML020770026 +  and ML033370195 +

Turbine Trip +  and Reactor Trip +

Mitra S +, Maurice Heath +  and NRC/NRR/ADRO/DLR +

ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +, ML061730123 +  and ML061730123 +

Alternate Source Term +  and License Renewal Application +

General Electric +  and Westinghouse +

NUREG-1856, Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2, Section 3 - Aging Management Review Results Through End +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

4.16KV +  and 4.16kV +

FPP +  and ISP +

Regulatory Guide 1.45 +, Regulatory Guide 1.29 +  and Regulatory Guide 1.188 +

3A-22 +  and 2G41-59-8-154 +

North Carolina +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Stator Cooling Water +...

TS-3.6.1.4 +  and TS-2.4.2.4 +

Safe Shutdown +, Reactor Vessel Water Level +, Grab sample +, Fire Barrier +, Anticipated operational occurrence +, Coatings +, Nondestructive Examination +, High Energy Line Break +, Aging Management +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Integrated leak rate test +, License Renewal +, Earthquake +, Fire Protection Program +, Core Exit Thermocouple +, Power Uprate +, Overspeed +, Control Room Habitability +, Spent fuel rack +  and Leak Before Break +