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Issue date | Title | Topic | |
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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 |
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 |
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 |
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 |
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 |
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 |
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 | |
ML19228A023 | 15 August 2019 | Proposed Alternative to Utilize Code Case N-879 | |
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 |
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 |
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 |
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-15-259, 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. | |
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 |
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 | |
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-14-082, 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 | |
RS-12-159, Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 1 | 13 February 2014 | Enclosure 2 to RS-14-034 - Updated Transmittal 2 (Annex B) Seismic Walkdown Report in Report to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 3.4. Part 1 | Safe Shutdown Unanalyzed Condition Ultimate heat sink Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Design basis earthquake Earthquake |
ML14119A377 | 13 February 2014 | Enclosure 1 to RS-14-034 - Update Transmittal 2 (Annex B) Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
ML13338A624 | 9 December 2013 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Braidwood Station, Units 1 and 2, TAC Nos.: MF0895 and MF0896 | 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 |
ML11206B180 | 20 July 2011 | ARS1-11-01372 - Braidwood Water Sample Results | |
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 |
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 |
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 |
ML111090279 | 15 April 2011 | ARS1-10-02678, Revised Laboratory Analysis Report. | |
ML092520265 | 4 September 2009 | Attachment 3, Corrected Pages to WCAP-17072-NP (Non-Proprietary) | |
ML091811030 | 30 June 2009 | Startup Report for the Installation of Areva Np, Inc. Advanced Mark-BW(A) Fuel Assemblies in Braidwood Unit 1 Cycle 15 | |
ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
ML17255A841 | 30 June 2008 | Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted | |
RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted | 30 June 2008 | Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted | |
RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted | 20 June 2008 | Braidwood, Units 1 and 2 - Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted | Safe Shutdown Past operability Finite Element Analysis |
ML17255A839 | 20 June 2008 | Full Action Request Report AR 789791, Potential Loss of Margin in Ms Tunnel Pressurization Calc., Redacted | Safe Shutdown Past operability Finite Element Analysis |
ML091070227 | 31 January 2008 | Guidance for Post Fire Safe Shutdown Circuit Analysis | Hot Short Safe Shutdown Fire Barrier Operator Manual Action Multiple Spurious Operation Emergency Lighting Thermoset Exemption Request Power-Operated Valves Fire Protection Program |
ML080230484 | 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-07-059, 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 |
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 |
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-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 |
ML052290083 | 19 August 2005 | Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors | |
ML050330480 | 24 January 2005 | Pressure and Temperature Limits Reports (Ptlrs), Revision 3 | Hydrostatic Pressure and Temperature Limits Report |