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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 |
| ML23055A284 | 24 February 2023 | Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping | Fitness for Duty Ultimate heat sink Non-Destructive Examination Safe Shutdown Earthquake Coatings Operating Basis Earthquake Finite Element Analysis Aging Management Foreign Material Exclusion |
| BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 9 | 20 October 2022 | Pressure and Temperature Limits Report (Ptlr), Revision 9 | Hydrostatic Pressure and Temperature Limits Report |
| 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 |
| ML22178A172 | 27 June 2022 | Long Term Coupon Surveillance Program | Aging Management |
| ML22147A178 | 27 May 2022 | Owner'S Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling Outage | Boric Acid Moisture barrier |
| BW210065, Pressure and Temperature Limits Report, Revision 8 | 27 October 2021 | Pressure and Temperature Limits Report, Revision 8 | Hydrostatic Pressure and Temperature Limits Report |
| 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 |
| ML21210A325 | 30 July 2021 | Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report | |
| BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval | 30 June 2021 | ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval | Safe Shutdown |
| 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 |
| ML21077A180 | 18 March 2021 | 10 CFR 50.46 Annual Report and 30-day Report for Framatome'S Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA) | |
| 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 |
| RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections | 16 December 2020 | Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections | Anticipated operational occurrence Pandemic Coronavirus COVID-19 |
| 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 |
| ML20280A508 | 6 October 2020 | Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | Incorporated by reference Fuel cladding |
| 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 | |
| ML20034E346 | 7 February 2020 | Review of the Spring 2019 Steam Generator Tube Inspection Report | |
| ML19347A779 | 12 December 2019 | License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies | Shutdown Margin Anticipated operational occurrence Fuel cladding |
| ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | |
| ML19072A096 | 11 March 2019 | Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld Overlay | Weld Overlay Hydrostatic Design basis earthquake Earthquake Dissimilar Metal Weld |
| ML18348A979 | 14 December 2018 | Transmittal of 10 CFR 50.59 Summary Report | Boric Acid Ultimate heat sink Probabilistic Risk Assessment FLEX Earthquake Fuel cladding |
| ML18348A972 | 12 December 2018 | Submittal of Analytical Evaluation in Accordance with ASME Code Section XI | 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 |
| RS-16-223, 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) | 7 December 2016 | 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) | Boric Acid High winds Shutdown Margin Ultimate heat sink Time to boil Safe Shutdown Earthquake Internal Flooding FLEX Tornado Generated Missile Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake |
| 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 |
| 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 |
| ML16250A518 | 30 April 2016 | Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Surveillance Frequency Control Program |
| 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-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. | 30 September 2015 | Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. | |
| ML15077A103 | 16 April 2015 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation | Safe Shutdown Ultimate heat sink Fukushima Dai-Ichi Frazil ice Earthquake |
| ML15075A339 | 10 March 2015 | NUH32PHB-0101, Revision 4, Design Criteria Document (DCD) for the Nuhoms 32PHB System for Storage | Hydrostatic Coatings Nondestructive Examination Control of Heavy Loads Fuel cladding |
| ML15042A137 | 3 February 2015 | Gesc, NAC International, Atlanta Corporate Headquarters, 655 Engineering Drive, Norcross, Georgia (Engineering Report #NS3-020, Effects of 1300F on Unfilled NS-3, While Bisco Products, Inc., 11/84), Enclosure 4 | |
| 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 |
| ML14212A308 | 25 July 2014 | NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc. | Nondestructive Examination Finite Element Analysis Fuel cladding Liquid penetrant |
| ML14212A307 | 25 July 2014 | NUH32PHB.0101, Rev. 2, Design Criteria Document (DCD) for Nuhoms 32PHB System for Storage. | Hydrostatic Coatings Nondestructive Examination Control of Heavy Loads Fuel cladding |
| 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 |
| ML14206B007 | 19 May 2014 | Considerations for Using Marinite in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-009, Revision 4 | Fire Barrier |
| RS-14-064, Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report | 31 March 2014 | Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening Report | |
| RS-14-064, Section 5 - Summary of Regulatory Commitments | 31 March 2014 | Section 5 - Summary of Regulatory Commitments | |
| ML14091A006 | 31 March 2014 | Section 2 - Braidwood Station, Units 1 and 2, Selsmic Hazard and Screening 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 |
| 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 |