BW120121, 10 CFR 50.59 Summary Report for June 19, 2010 Through June 18, 2012
BYRON 2011-0018, Regulatory Commitment Change Summary Report
BYRON 2010-0042, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)
BYRON 2010-0041, Steam Generator - Inservice Inspection Summary Report for Refueling Outage 15
BYRON 2010-0029, Annual Radioactive Effluent Release Report
BYRON 2010-0040, Cycle 16 Core Operating Limits Report
BYRON 2010-0034, Annual Dose Report for 2009
BYRON 2010-0017, Regulatory Commitment Change Summary Report
BYRON 2010-0003, Change to Operator Licensing Examination 2011 Dates
BYRON 2009-0107, Cycle 17 Core Operating Limits Report
BYRON 2009-0098, Affirmation of 10 CFR 26, Subpart I, Implementation Prior to October 1, 2009
BYRON 2009-0092, Affirmation of 10 CFR 26, Subpart I, Implementation Prior to October 1, 2009
BYRON 2009-0054, Independent Spent Fuel Storage Installation - Notification of Full Compliance to NRC Security Order EA-08-069 Requirements
BYRON 2009-0014, Annual Radiological Environmental Operating Report (AREOR)
BYRON 2009-0012, Submittal of 2008 Annual Radioactive Effluent Release Report
BYRON 2009-0048, Submittal of Annual Dose Report for 2008
BYRON 2009-0041, 2008 Regulatory Commitment Change Summary Report
BYRON 2009-0033, Unit 2, Response to NRC Annual Assessment Letter
BYRON 2009-0029, Change to Operator Licensing Examination 2011 Dates
BYRON 2009-0025, Updated Information to Response to NRC Request Concerning Unresolved Item 05000454-08-008 and 05000455-08-008
RA09-002, Cycle 3 Core Operating Limits Report
RA08-070, Submittal of Third 10-Year Inservice Testing (IST) Interval Program Plan
RA08-059, Cycle 12, Revision 3 Core Operating Limits Report (COLR)
RA08-035, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA08-036, Cycle 13 Startup Test Report Summary
RA08-034, Annual Radiological Environmental Operating Report
RA08-027, Annual Radioactive Effluent Release Report
RA-08-030, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report
RA08-008, Cycle 13 Core Operating Limits Report (COLR)
RA-07-079, Submittal of Program Plan Associated with the Third Inservice Inspection (ISI) Interval and the Second Containment Inspection (Cisi) Interval
RA07-081, Cycle 12, Revision 4 Core Operating Limits Report (COLR)
RA07-033, Units I & 2, Notification of NPDES Permit Renewal
RA07-012, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report
RA06-095, Daniel J. Enright Ltr. Re; Change of Maintenance-Modification Contractor
RA06-060, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report
RA06-013, Plant Specific ECCS Evaluation Changes
RA05-080, 2004 Regulatory Commitment Change Summary Report
05000374/LER-1992-016-07, :on 921116,discovered Reactor Scram on Loss of Air Due to Defective Procedure.Revised Procedure Utilized for cross-typing SA Compressor Cooling Water to Other Unit to Provide Provisions for Positive Control
05000374/LER-1992-016, :on 921116,reactor Scram on Loss of Air Occurred.Caused by Inadequate Out of Svc Review & Lack of Administrative Controls.Procedures Revised & Individuals Involved Counseled
BW130008, 2013 Braidwood Station Initial License Examination Proposed Exam Files
BW130038, 2013 Braidwood Station Initial Operator Licensing Examination Post Exam Comments and Grading
BW120117, 2013 Braidwood Station Initial Operator Licensing Examination Outline Transmittal Letter-Index
BW130043, Submittal of 2012 Radioactive Effluent Release Report
05000456/LER-2012-005, Incorrect Procedure Guidance Due to a Lack of Technical Rigor Resulted in Unplanned Inoperability of the 1A and 1 B Emergency Diesel Generators
BW130009, Regulatory Commitment Change Summary Report
BW130010, Steam Generator Tube Inspection Report for Refueling Outage 16
BW130007, Inservice Inspection Summary Report
BW120120, Reply to a Notice of Violation Regarding Inspection Reports 05000456/2012004-03; 05000457/2012004-03
BW120102, Response to NRC Request for Additional Information Involving Site Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan
BW120106, Core Operating Limits Report, Braidwood Unit 2 Cycle 17
BW120108, Readiness for 95001 Supplemental Inspection
BW120105, Reply to a Notice of Violation; 05000457/2012008-01
05000456/LER-2012-004, Regarding Notice of Enforcement Discretion Received for Ultimate Heat Sink Temperature Exceeding Technical Specifications Requirements Due to Prolonged Hot Weather
BW120081, Inservice Inspection Summary Report
05000456/LER-2012-003, Fuel Handling Incident Area Radiation Monitors Inoperable Due to Incorrect Alarm Setpoint
BW120072, Request for Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink
05000456/LER-2012-002, Regarding Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Indication Attributed to Primary Water Stress Corrosion Cracking
05000456/LER-2012-001, Regarding Two Main Steam Safety Valves Failed Pre-outage Setpoint Testing Due to Abnormal Spring Geometry
BW120048, Submittal of 2011 Annual Radiological Environmental Operating Report
BW120046, Core Operating Limits Report, Cycle 17
BW120036, Submittal of Analytical Evaluation in Accordance with ASME Code Section XI
BW120031, Request for Initial Operator License Waivers
BW120011, Regulatory Commitment Change Summary Report
BW120009, Notice of Change in Standard Revision Associated with the Simulator
BW120002, Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 12
05000456/LER-2011-004, Regarding Non-Conservative Historic Assumptions Identified in Turbine Building High Energy Line Break Analyses Result in Potential for Two Channels in a System to Become Inoperable
BW110138, Withdrawal of Licensee Event Report 2010-004-00 - Unplanned Limiting Condition for Operation Entry Due to Low Header Pressure on the 2B Essential Service Water Pump
BW110140, Station Readiness for Traditional Enforcement Violation Follow-Up Inspection
BW110117, Supplemental Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009
05000456/LER-2011-003, Withdrawal of LER 11-003-00 for Braidwood Station, Units 1 & 2 Re Drained Sections of Piping in Auxiliary Feedwater Suction Lines
05000457/LER-2011-002, Regarding Auxiliary Feedwater System Incomparability Due to Additional Asiatic Clam Shells in Essential Service Water Supply Piping
BW110084, Inservice Inspection Summary Report
BW110085, Steam Generator Tube Inspection Report for Refueling Outage 15
BW110081, Initial License Examination Post Examination
05000457/LER-2011-001, For Braidwood Station, Unit 2, Regarding Asiatic Clam Shells in Essential Service Water Supply Piping to the 2A Auxiliary Feedwater Pump Resulted in Auxiliary Feedwater Inoperability
BW110049, Annual Radiological Environmental Operating Report
05000456/LER-2011-002, Regarding Loss of Unit 1 Train a Bus 141 Degraded Undervoltage Function
BW110046, Core Operating Limits Report, Cycle 16
05000456/LER-2011-001, Regarding Through Wall Crack on 1A Safety Injection Pump Discharge Line Due to Outside Diameter (Transgranular) Stress Corrosion Cracking Initiated at External Diameter of Pipe
BW110032, Notification of Full Compliance to NRC Security Order EA-2010-050 Requirements for Braidwood Station Independent Spent Fuel Storage Installation
BW110030, Reply to a Notice of Violation; EA-10-220
BW110021, Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009
05000454/LER-2010-001, Regarding Technical Specifications Allowed Outage Time Extension Request for Component Cooling System Contained Inaccurate Design Information That Significantly Impacted the Technical Justification
05000455/LER-2010-002, Regarding Essential Service Water System Inoperable Due to Inadequate Seismic Restraint from Original Construction Error
05000455/LER-2010-001, Reactor Protection and Auxiliary Feedwater System Actuation Signals from Low Steam Generator Level Due to Inadequate Surveillance Testing
05000454/LER-2009-001, Drain Procedure for ECCS Suction Line Creates an Unanalyzed Condition Due to Inadequate Configuration Requirements
05000373/LER-2006-001, Regarding Three Control Rods Fail to Indicate Fully Inserted Following Automatic Reactor Scram
05000373/LER-2005-004, Re Trip of System Auxiliary Transformer (SAT) Feed Breaker to Bus 143 Due to Ground Fault in Potential Transformer
05000373/LER-2005-002, Re Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum Pump Discharge Check Valve 1E51-F028 Failed Local Leak Rate Test
05000374/LER-2005-003, Re Multiple Containment Isolations Following Loss of 480 Vac Safety Related Buses Due to Failed Neutral Overcurrent Relay
05000373/LER-2005-003, Regarding Main Steam Line High Flow Main Steam Isolation Valve Isolation Differential Pressure Switches Failed Due to Manufacturing Error
05000374/LER-2005-002, Regarding Pressure Boundary Leakage Discovered in 2D MSIV Drain Line Weld During Refueling Outage VT-2 Examination
05000373/LER-2005-001, Regarding Single Failure Vulnerability of Division 1 and 2 Protective Relay Circuitry Due to Latent Design Deficiency
05000455/LER-2009-001, Re Late Entry Into Technical Specification Condition Associated with Reactor Coolant System Leakage Characterization Resulting in a Condition Prohibited by Technical Specifications