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| Issue date | Title | Topic | |
|---|---|---|---|
| RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 | 29 September 2023 | Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 | Boric Acid VT-2 Finite Element Analysis Liquid penetrant Exclusive Use |
| RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 | 20 April 2023 | Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 | Non-Destructive Examination Code Reconciliation |
| 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 | |
| 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-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | 1 September 2021 | R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | Finite Element Analysis Aging Management |
| RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld | 12 May 2021 | Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld | Hydrostatic VT-2 Finite Element Analysis |
| RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | 4 January 2021 | Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | Nondestructive Examination |
| 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 2020-0084, 10 CFR 72.48 Evaluation Summary Report | 10 December 2020 | 10 CFR 72.48 Evaluation Summary Report | |
| ML20195B159 | 10 July 2020 | Attachment 1 - Description and Assessment | Anticipated operational occurrence Pandemic Coronavirus COVID-19 |
| 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 | |
| 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 | |
| ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | |
| 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 |
| 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 |
| 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 |
| RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds | 15 March 2016 | Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds | Boric Acid |
| RS-15-267, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | 30 November 2015 | Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation |
| RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 24 September 2014 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | Through-Wall Leak |
| 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 |
| 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 |
| 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 |
| RS-14-082, ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report | 27 February 2014 | ECCS Evaluation Model Error - 10 CFR 50.46 30-Day Report | |
| 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 |
| 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 |
| ML17255A832 | 1 July 2013 | Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted | |
| RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted | 1 July 2013 | Byron, Units 1 and 2 - Full Action Request Report AR 1531420, No Actions Tracking Update to Calculation 3C8-0282-001, Redacted | |
| ML17255A831 | 31 October 2011 | Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted | |
| RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted | 31 October 2011 | Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted | |
| 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 |
| RS-12-023, WCAP-17330-NP, Rev. 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). | 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 |
| 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 |
| 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 |
| 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 |
| ML092520265 | 4 September 2009 | Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) | |
| ML17255A830 | 1 July 2009 | Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted | |
| RS-17-119, Byron, Units 1 and 2 - Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted | 1 July 2009 | Byron, Units 1 and 2 - Engineering Change EC 366685, Revision 67, OP Eval. 07-006, Aux Feed Tunnel Covers Installation, Redacted | |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| ML17255A840 | 30 June 2008 | Full Action Request Report AR 792213, MSLB Calc. Energy Release Error, Redacted | |
| ML17255A837 | 12 June 2008 | Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted | Past operability |
| RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted | 12 June 2008 | Byron, Units 1 and 2 - Full Action Request Report AR 789344, Error in Ms Tunnel Pressurization Calculation, Redacted | Past operability |
| RS-08-075, LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone. | 3 June 2008 | LTR-CDME-08-11, Rev. 3 Np, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone. | Finite Element Analysis |
| ML080230485 | 14 January 2008 | Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report | Earthquake |
| 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 | |
| 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-07-059, 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 |
| 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 |
| ML070240261 | 23 January 2007 | Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) | Hydrostatic Pressure and Temperature Limits Report |
| 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 |