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| Issue date | Title | Topic | |
|---|---|---|---|
| BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) | 15 July 2022 | Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) | |
| ML20280A248 | 7 October 2020 | Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3 | |
| ML15253A913 | 11 September 2015 | ACRS Full Committee - Corrections to the Aging Management Programs Table | Boric Acid Aging Management |
| ML15229A148 | 3 September 2015 | Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR 50.54 Information Request - Flood Causing Mechanism Reevaluation | FLEX Fukushima Dai-Ichi |
| ML15226A598 | 3 September 2015 | Tables 1 and 2 8-11-2015 Edited-SB | |
| RS-15-059, Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application | 6 February 2015 | Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application | |
| ML14307B707 | 10 December 2014 | Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T | Probabilistic Risk Assessment Fukushima Dai-Ichi |
| RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites | 12 September 2013 | Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites | Fukushima Dai-Ichi Earthquake |
| ML110610795 | 2 March 2011 | E-mail Byron Station Unit 1 Supplemental Information Request to Support Baseline ISI Inspection Procedure | Nondestructive Examination Scaffolding |
| NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan | 23 July 2010 | Re-Submittal of the Exelon Cyber Security Plan | Cyber Security Incorporated by reference |
| RS-10-105, Byron Parent Guarantee Calculation RS-10-105 | 10 March 2010 | Byron Parent Guarantee Calculation RS-10-105 | |
| ML093431318 | 1 December 2009 | Updated Decommissioning Shortfalls as of December 1, 2009 | |
| ML081830087 | 31 March 2008 | Steam Generator Eddy Current Inspection Report, Refueling Outage 15, Attachment B, Inspection Scope, Through Attachment B.2, Cold Leg Bobbin Coil Inspection Scope. | |
| ML080250190 | 10 January 2008 | Amag Corrosion Factor for Reactor Coolant Loop Vs. Date for Byron Unit 1 | |
| ML080250184 | 10 January 2008 | Amag Loop Corrosion Factor Vs. Date for Byron Unit 2 | |
| ML080250151 | 10 January 2008 | Graphs | |
| RS-07-022, Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification | 15 February 2007 | Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification | Finite Element Analysis Liquid penetrant |
| ML061220683 | 27 April 2006 | Oak Ridge Institute for Science and Education, Analytical Results for 41 Water Samples in Batch Two from the Vicinity of the Byron Generating Station, Byron Illinois (Inspection Report No. 05000454/2006-003) (Rfta No. 06-001) | |
| BYRON 2006-0007, Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 22 | 3 January 2006 | Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 22 | |
| RS-04-191, Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-319 | 16 December 2004 | Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-319 | Earthquake |
| ML042260357 | 12 August 2004 | Figure 1 and 2, Results of the Spring 2004 Steam Generator Inspections |