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| Issue date | Title | |
|---|---|---|
| BYRON 2018-0109, 10 CFR 50.59 Summary Report | 10 December 2018 | 10 CFR 50.59 Summary Report |
| ML16357A507 | 15 December 2016 | Byron/Braidwood Nuclear Stations, Submittal of Revision 16 to Updated Final Safety Analysis Report and Updated Fire Protection Report (Fpr), Amendment 27 |
| RS-16-248, Byron/Braidwood Nuclear Stations, Submittal of Revision 16 to Updated Final Safety Analysis Report and Updated Fire Protection Report (Fpr), Amendment 27 | 15 December 2016 | Byron/Braidwood Nuclear Stations, Submittal of Revision 16 to Updated Final Safety Analysis Report and Updated Fire Protection Report (Fpr), Amendment 27 |
| RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure | 26 May 2016 | Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure |
| IR 05000454/2015002 | 22 July 2015 | IR 05000454/2015002, 05000455/2015002, 07200068/20150001; on 04/01/2015 - 06/30/2015; Byron Station, Units 1 and 2; Routine Integrated Inspection Report |
| RS-14-196, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) | 28 August 2014 | Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) |
| RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. | 31 March 2014 | Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. |
| ML14051A671 | 4 March 2014 | FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014 |
| NRC-2014-0037, FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014 | 4 March 2014 | FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014 |
| RA-13-109, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns | 27 November 2013 | Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns |
| ML13162A370 | 31 May 2013 | Applicant'S Environmental Report Operating License Renewal Stage, Byron Station, Units 1 and 2. Appendix F |
| ML13155A423 | 29 May 2013 | Environmental Report, Part 2 |
| RS-13-145, Byron, Units 1 and 2 - Environmental Report, Part 2 | 29 May 2013 | Byron, Units 1 and 2 - Environmental Report, Part 2 |
| ML12341A161 | 7 November 2012 | Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 1, Report No. 12Q0108.20-R-001, Revision 1 |
| ML12341A166 | 7 November 2012 | Enclosure 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2, Report No: 12Q0108.20-R-002, Revision 1 |
| ML12122A071 | 14 May 2012 | Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 |
| ML111790042 | 21 June 2011 | Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate |
| IR 05000454/2011014 | 13 May 2011 | IR 05000454-11-014 & 05000455-11-014, on 03/23/2011 - 04/27/2011, Byron Station, Units 1 and 2, Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event |
| RS-10-045, Response to Request for Additional Information Regarding the One-Time Extension of the Essential Service Water Train Completion Time | 9 March 2010 | Response to Request for Additional Information Regarding the One-Time Extension of the Essential Service Water Train Completion Time |
| RS-09-121, License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time | 24 September 2009 | License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time |
| ML040610869 | 18 March 2004 | Braidwood/Byron - Issuance of Amd 136/130 One Time Change to the Completion Time for Restoration of a Unit Specific Essential Service Water Train. (Tacs. MB9547. MB9548, MB9545, MB9546) |
| ML033560302 | 9 December 2003 | Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability. |
| RS-03-065, Units 1 & 2, Request for License Amendment for One-Time Extension of Essential Service Water Train Completion Time | 11 June 2003 | Units 1 & 2, Request for License Amendment for One-Time Extension of Essential Service Water Train Completion Time |
| ML20216D796 | 2 March 1998 | Requests Temporary Relief for Plant from Requirement of 1974 Edition of ASME Boiler & Pressure Vessel Code,Section III Re Use of Line Stopping Equipment on Essential Svc Water ASME Class 3 Piping |
| ML20211L215 | 3 October 1997 | Safety Evaluation Supporting Licensee Relief Request,Per 10CFR50.55a(a)(3)(i) |
| ML20140D686 | 11 April 1997 | Requests Temporary Relief for Units 1 & 2 from Requirements of 1974 Edition of ASME Boiler & Pressure Vessel Code, Section Iii,Subsections Na & Nd,Articles NA-3700,ND-2100, ND-3100,ND-3500 & ND-4100 |
| ML20151T141 | 5 August 1988 | Proposed Tech Specs,Revising Tech Spec Action Statement Re UHS |
| ML20203N324 | 17 September 1986 | Responds to Re Mitchell Allegations Re as-built Drawings at Byron Station.Allegations Will Be Vigorously Pursued.Recommendation to Pursue Investigation at Byron 2 & Braidwood 1 & 2 Premature |
| ML20107F501 | 22 October 1984 | Forwards Supplemental Info Re Evaluation of Slenderness Ratio & Lateral Unbraced Length Limitations on Component Support Steel Members.Mod Control Plan Encl.Related Correspondence |
| ML20098G440 | 25 September 1984 | Forwards C Reed & Byron Integrated Design Insp Response,For Review.Document Relevant to Intervenor Pending Motion to Reopen Record to Include Byron Station Design as Issue.Related Correspondence |
| ML20097B779 | 10 September 1984 | Proposed Supplemental Initial Decision Re Reinsp Program. Certificate of Svc Encl |
| ML20090A812 | 9 July 1984 | Testimony of Bf Maurer Re Analysis of Structural Adequacy of Main Control Panels Designed & Fabricated by Sys Control Corp |
| ML20083J707 | 30 December 1983 | Forwards Response to Unresolved Items Identified in Integrated Design Insp Rept 50-454/83-32 & Addresses NRC Conclusions Presented in |
| ML20023D955 | 31 May 1983 | Proposed Findings of Fact & Conclusions of Law Re Seismology,Water Hammer & ALARA |
| ML20084N033 | 31 May 1983 | Forwards Rockford League of Women Voters Proposed Findings of Fact & Conclusions of Law Re Contention 106 on Seismology,Per 820818 Stipulation |
| ML20065A902 | 15 February 1983 | Testimony of Ak Singh Re Rockford League of Women Voters Contention 106 on Ground Acceleration Values for Design. Ground Acceleration Values & OBE Std Appropriate for Plant. Prof Qualifications Encl |
| ML20065A898 | 15 February 1983 | Testimony of Ak Yonk Re Rockford League of Women Voters Contention 106 on Strain Gauge Tests.Last Movement of Faults Over 200,000 Yrs Ago.Faults Are Not Capable Under 10CFR100, App a Criteria.Prof Qualifications Encl |
| ML20054E758 | 4 June 1982 | Affidavit of G Klopp Re Contention 4.Intervenor Interpretation of Single Failure Demonstrates Misunderstanding of NRC Requirement on Accident Analysis |