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

ASME Section XI +  and ASME Section III +

10 CFR 20 +, 10 CFR 50.36 +, 10 CFR 51 +, 10 CFR 50.60 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 50.60#a +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e +

05000456  +, 05000457  +, 00456  +  and 00457  +

NUREG-2190, V2 - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 +, ML15232A441 +, ML061890003 +, ML062610513 +, ML20163A046 +, ML21300A074 +, RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) +, ML20022A336 +, ML22173A181 +, ML14290A097 +  and RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures for +

Joel Wiebe +  and Plant Licensing Branch III +

ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +, ML22173A181 +...

ML15232A441 +, ML062610513 +, ML20163A046 +, ML20022A330 +, BW210064, Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 23, Revision 14 +, RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) +, BW060101, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +  and RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures for +

Arkansas +  and Illinois +

Reactor Coolant System +  and Reactor Pressure Vessel +

TS-5.6.6 +  and TS-5.6.6.b +

Constellation +  and Rhoades D +

Anticipated operational occurrence +, Internal Flooding +, Hydrostatic +, Probabilistic Risk Assessment +, Eddy Current Testing +, License Renewal +, Exemption Request +  and Pressure Temperature Limits Report +