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MONTHYEARML0801804372008-01-18018 January 2008 Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report Project stage: Request ML0802205262008-01-22022 January 2008 Inservice Inspection Summary Report Project stage: Request ML0816401642008-06-16016 June 2008 RAI, Steam Generator Tube Inspection Reports for Refueling Outage A1R13, Project stage: RAI ML0822700142008-08-13013 August 2008 Transmittal of Response to Request for Additional Information Regarding Fall 2007 Steam Generator Inspection Project stage: Response to RAI ML0828100202008-10-20020 October 2008 Review of Fall 2007 Steam Generator Tube Inservice Inspection Reports Project stage: Approval 2008-10-20
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24241A0062024-08-28028 August 2024 Attachment 1: Braidwood Generating Station - Form OAR-1 Owners Activity Report ML23305A0412023-11-0101 November 2023 Updated Steam Generator Tube Inspection Report RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23223A0542023-08-11011 August 2023 Attachment 1 - Braidwood Station, Unit 2: Form OAR-1 Owners Activity Report BW230019, Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 20222022-10-31031 October 2022 Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 BW220019, Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22)2022-04-27027 April 2022 Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22) ML22031A0442022-01-31031 January 2022 Form OAR-1 Owners Activity Report BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021 Revision to Unit 1 Inservice Inspection Summary Report ML21202A1932021-07-21021 July 2021 Owner'S Activity Report (OAR) for Refueling Outage A1R22 BW210032, Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 20282021-04-28028 April 2021 Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 2028 BW200095, Inservice Inspection Summary Report2020-12-0909 December 2020 Inservice Inspection Summary Report BW210002, Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 32020-11-25025 November 2020 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 3 RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2020-07-24024 July 2020 Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20017A1332020-01-17017 January 2020 Inservice Inspection Summary Report NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 RS-19-084, Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval2019-08-27027 August 2019 Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants ML19030B0872019-01-30030 January 2019 Submittal of Inservice Inspection Summary Report ML18264A1552018-09-21021 September 2018 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 1 ML18208A2942018-07-27027 July 2018 Fourth Ten-Year Interval Inservice Testing Program Plan ML18208A3272018-07-27027 July 2018 Lnservice Inspection Summary Report ML17236A4572017-08-24024 August 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 ML17244A2332017-08-18018 August 2017 Inservice Inspection Summary Report ML17058A0852017-02-27027 February 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 ML17024A3982017-01-24024 January 2017 Inservice Inspection Summary Report for Refueling Outage 19 (A1R19) ML16021A0802016-01-21021 January 2016 Inservice Inspection Summary Report ML15198A1952015-07-16016 July 2015 Inservice Inspection Summary Report RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2015-05-29029 May 2015 Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML14318A2112014-11-14014 November 2014 Steam Generator Tube Inspection Report for Refueling Outage 17 RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2014-09-0808 September 2014 Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML14232A3242014-08-20020 August 2014 Inservice Inspection Summary Report ML13358A4002013-12-20020 December 2013 Inservice Inspection Summary Report for Refueling Outage 17 ML13037A5062013-02-0606 February 2013 Inservice Inspection Summary Report ML12251A3592012-08-17017 August 2012 (Returned to DCD) Braidwood Station, Unit 1, Steam Generator Tube Inspection Report for Refueling Outage 15 ML12230A2262012-08-17017 August 2012 Inservice Inspection Summary Report ML11227A2532011-08-10010 August 2011 Inservice Inspection Summary Report RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-04-19019 April 2011 Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations RS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside.2011-04-11011 April 2011 Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside. ML1103505122011-02-0404 February 2011 Inservice Inspection Summary Report ML1003302732010-01-27027 January 2010 Inservice Inspection Summary Report ML0921105382009-07-27027 July 2009 Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval ML0920502592009-07-16016 July 2009 Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report ML0920502512009-07-16016 July 2009 Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14) ML0908607152009-03-25025 March 2009 Submittal of Third Inservice Inspection (ISI) Interval Program Plan RS-08-160, Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure .2008-12-10010 December 2008 Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure . ML0829007072008-08-13013 August 2008 Inservice Inspection Summary Report for: Interval 2, Period 3, Outage 2 A2R13 Outage ML0802205262008-01-22022 January 2008 Inservice Inspection Summary Report ML0801804372008-01-18018 January 2008 Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report ML0727403892007-10-17017 October 2007 Review of Twelfth Refueling Outage Steam Generator Tube Inservice Inspection Report ML0705403462007-02-23023 February 2007 Second 10-Year Inservice Inspection Interval, Relief Request I2R-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzle Safe-Ends and Associated Alternative Repair Techniques 2024-08-28
[Table view] Category:Letter
MONTHYEARIR 05000456/20240032024-11-12012 November 2024 Integrated Inspection Report 05000456/2024003 and 05000457/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak 2024-09-23
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Text
January 18, 2008 BW080003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555-0001 Braidwood Station, Unit 1 Facility Operating License No, NPF 72 NRC Docket No.STN 50-456
Subject:
Braidwood Station, Unit 1 Thirteenth Refueling Outage Steam Generator!nservice Inspection Summary Report In accordance with Technical Specification 5.6.9,"Steam Generator (SG)Tube Insoection Report"Exelon Generation Company, LLC is reporting the results of the SG inspections, which were completed during the Braidwood Station, Unit 1 thirteenth refueling outage (Al Ri 3).The attached report is also being submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition, Section Xl,"Rules for Inservice Inspection of Nuclear Power Plant Components,"
Article IWA-6000,"Records and Reports,"and Article lV-7000,"Report of Examination,"
of Mandatory Appendix IV,"Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubing."If there are any questions regarding this submittal, please contact Mr.David Gullott, Regulatory Assurance Manager, at (815)417-2800.Respectfully, Thomas Coutu Site Vice President Braidwood Station
Attachment:
Exelon Braidwood Station Unit 1 Thirteenth Refueling Outage Steam Generator lnservice Inspection Summary Report Exelon Nuclear BRAIDWOOD STATION UNIT 1 35100 South Rte.53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION:
July 29, 1988 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT THIRTEENTH REFUELING OUTAGE (A1R13)October 2007 Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Document Completion Date: January 11, 2008 TABLE OF CONTENTS
1.0 INTRODUCTION
2.0
SUMMARY
3.0 CERTIFICATIONS
3.1 Procedures/Examinations/Equipment
3.2 Personnel
4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE 4.1 Examination Techniques
4.2 Steam
Generator Inspection Scope 4.3 Recording of Examination Data 4.4 Witness and Verification of Examination
5.0 EXAMINATION
RESULTS 5.1 Eddy Current Inspection
5.2 Other
Inspection Results 6.0 RESULTS OF CONDITION MONITORING 6.1 Fan BarWear 6.2 Lattice Grid Wear 6.3 Foreign Object Wear 7.0 REPAIR
SUMMARY
8.0 DOCUMENTATION
9.0 FIGURES/TABLES/ATTACHMENTS January 18, 2008 BW080003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555-0001 Braidwood Station, Unit 1 Facility Operating License No, NPF 72 NRC Docket No.STN 50-456
Subject:
Braidwood Station, Unit 1 Thirteenth Refueling Outage Steam Generator!nservice Inspection Summary Report In accordance with Technical Specification 5.6.9,"Steam Generator (SG)Tube Insoection Report"Exelon Generation Company, LLC is reporting the results of the SG inspections, which were completed during the Braidwood Station, Unit 1 thirteenth refueling outage (Al Ri 3).The attached report is also being submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition, Section Xl,"Rules for Inservice Inspection of Nuclear Power Plant Components,"
Article IWA-6000,"Records and Reports,"and Article lV-7000,"Report of Examination,"
of Mandatory Appendix IV,"Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubing."If there are any questions regarding this submittal, please contact Mr.David Gullott, Regulatory Assurance Manager, at (815)417-2800.Respectfully, Thomas Coutu Site Vice President Braidwood Station
Attachment:
Exelon Braidwood Station Unit 1 Thirteenth Refueling Outage Steam Generator lnservice Inspection Summary Report Exelon Nuclear BRAIDWOOD STATION UNIT 1 35100 South Rte.53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION:
July 29, 1988 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT THIRTEENTH REFUELING OUTAGE (A1R13)October 2007 Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Document Completion Date: January 11, 2008 TABLE OF CONTENTS
1.0 INTRODUCTION
2.0
SUMMARY
3.0 CERTIFICATIONS
3.1 Procedures/Examinations/Equipment
3.2 Personnel
4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE 4.1 Examination Techniques
4.2 Steam
Generator Inspection Scope 4.3 Recording of Examination Data 4.4 Witness and Verification of Examination
5.0 EXAMINATION
RESULTS 5.1 Eddy Current Inspection
5.2 Other
Inspection Results 6.0 RESULTS OF CONDITION MONITORING 6.1 Fan BarWear 6.2 Lattice Grid Wear 6.3 Foreign Object Wear 7.0 REPAIR
SUMMARY
8.0 DOCUMENTATION
9.0 FIGURES/TABLES/ATTACHMENTS