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| Issue date | Title | Topic | |
|---|---|---|---|
| BYRON 2002-0032, Cycle 12 Core Operating Limits Report, Revision 1 for Byron Station Unit 1 | 22 March 2002 | Cycle 12 Core Operating Limits Report, Revision 1 for Byron Station Unit 1 | |
| BYRON 2003-0064, Revision to Reactor Coolant System Pressure & Temperature Limits Report | 17 July 2003 | Revision to Reactor Coolant System Pressure & Temperature Limits Report | Hydrostatic Pressure and Temperature Limits Report |
| BYRON 2004-0035, Regulatory Commitment Change Summary Report | 1 April 2004 | Regulatory Commitment Change Summary Report | Grace period |
| BYRON 2005-0071, Steam Generator Inservice Inspection Summary Report | 3 June 2005 | Steam Generator Inservice Inspection Summary Report | Nondestructive Examination Flow Induced Vibration |
| BYRON 2005-0077, Day Response to First Revised NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors. | 22 June 2005 | Day Response to First Revised NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors. | Boric Acid Nondestructive Examination |
| BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR) | 17 April 2007 | Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR) | Hydrostatic Pressure and Temperature Limits Report |
| BYRON 2010-0001, Form NIS-2 Owner'S Report for Repair/Replacement Actitivity as Required by the Provisions of the ASME Code Section XI | 16 September 2009 | Form NIS-2 Owner'S Report for Repair/Replacement Actitivity as Required by the Provisions of the ASME Code Section XI | Hydrostatic VT-2 |
| BYRON 2014-0003, Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate | 13 February 2014 | Pressure and Temperature Limits Report (PTLR) for Measurement Uncertainty Recapture (Mur) Power Uprate | Pressure and Temperature Limits Report |
| BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill | 27 March 2014 | Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill | Hydrostatic Pressure and Temperature Limits Report |
| BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report | 10 December 2020 | 10 CFR 72.48 Evaluation Summary Report | |
| BYRON 2020-0085, 10 CFR 50.59 Summary Report | 10 December 2020 | 10 CFR 50.59 Summary Report | Safe Shutdown Boric Acid Safe Shutdown Earthquake Open Phase Condition Fire Protection Program |
| BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment | 13 October 2022 | Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment | |
| ML031770346 | 17 June 2003 | Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC | |
| ML052290083 | 19 August 2005 | Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors | |
| ML063460131 | 7 December 2006 | Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier | Deep Dose Equivalent Fuel cladding |
| ML070180612 | 18 September 2006 | Form NIS-2 Owner'S Report for Repair/Replacement Activity as Required by the Provisions of the ASME Code Section XI | Boric Acid Weld Overlay Hydrostatic |
| ML070240261 | 23 January 2007 | Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) | Hydrostatic Pressure and Temperature Limits Report |
| ML080230485 | 14 January 2008 | Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report | Earthquake |
| ML080250484 | 22 January 2002 | AR 00091771, Unexplained Differences Between Byron & Braidwood. | |
| ML080250485 | 22 January 2002 | AR 00091771 Unexplained Differences Between Byron & Braidwood. | |
| ML080290231 | 12 February 2004 | Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 | Power change |
| ML080290369 | 17 February 2004 | Actions from Initial Byron Tracer Test Results | |
| ML080290393 | 26 February 2004 | Synopsis of PORC Review of FW Tracer Test Results | |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| ML092520265 | 4 September 2009 | Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) | |
| ML100050366 | 18 September 2009 | Exelon Nuclear, Form NIS-2 Owner'S Report for Repair/Replacement Activity as Required by the Provisions of the ASME Code Section Xi | Hydrostatic |
| ML111790038 | 23 June 2011 | Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate | Shutdown Margin |
| 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 | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Fire Barrier Anticipated operational occurrence Weld Overlay Internal Flooding Hydrostatic Coatings Operator Manual Action Pressure and Temperature Limits Report Design basis earthquake Fuel cladding Fire Protection Program Flow Induced Vibration Coast down |
| ML12083A123 | 30 June 2011 | WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). | Finite Element Analysis |
| ML13338A642 | 9 December 2013 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Byron Station, Units 1 and 2, TAC Nos.: MF0893 and MF0894 | Safe Shutdown Boric Acid High winds Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Frazil ice Earthquake |
| ML14079A423 | 12 March 2014 | Enclosure 1, Byron Nuclear Generating Station, Flood Hazard Reevaluation Report, Revision 0 | High winds Ultimate heat sink Safe Shutdown Earthquake Internal Flooding Hydrostatic Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
| ML14178B222 | 24 June 2014 | Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology | Hot Short Safe Shutdown Multiple Spurious Operation Emergency Lighting Fire Protection Program Backfit |
| ML16356A020 | 7 October 2016 | 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. | Weld Overlay Nondestructive Examination |
| ML17234A478 | 22 August 2017 | Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE | High Radiation Area Ultimate heat sink Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake Power-Operated Valves Power Operated Valves |
| ML17255A830 | 1 July 2009 | Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted | |
| ML17255A831 | 31 October 2011 | Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted | |
| ML17255A832 | 1 July 2013 | Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted | |
| ML17255A837 | 12 June 2008 | Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted | Past operability |
| ML17255A840 | 30 June 2008 | Full Action Request Report AR 792213, MSLB Calc. Energy Release Error, Redacted | |
| ML17360A174 | 7 October 2016 | Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) | Weld Overlay Nondestructive Examination |
| ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | |
| ML20195B159 | 10 July 2020 | Attachment 1 - Description and Assessment | Anticipated operational occurrence Pandemic Coronavirus COVID-19 |
| ML20195B161 | 25 June 2020 | Attachment 6 - Intertek Report No. Aim 200510800-2Q-1(NP), Byron Unit 2 Operational Assessment Addressing Deferment of B2R22 Steam Generator Tube Examinations to B2R23, April 2022 | |
| ML20195B162 | 30 June 2020 | Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 | |
| NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | 30 June 2022 | Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | Mururoa |
| RS-05-129, LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2. | 31 August 2005 | LTR-CDME-05-32-NP, Rev. 2, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet at Byron 2 & Braidwood 2. | Nondestructive Examination Finite Element Analysis |
| RS-06-039, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 31 March 2006 | Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | Boric Acid Non-Destructive Examination Nondestructive Examination Finite Element Analysis Pressure Boundary Leakage |
| RS-07-059, Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2. | 3 May 2007 | Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2. | Hydrostatic |
| RS-07-079, Plant Specific ECCS Evaluation Change - 10 CFR 50.46 Report | 10 May 2007 | Plant Specific ECCS Evaluation Change - 10 CFR 50.46 Report | |
| RS-07-100, Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report | 22 June 2007 | Emergency Core Cooling System Evaluation Model Error - 10 CFR 50.46 Report |