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Category:Graphics incl Charts and Tables
MONTHYEARML22031A0442022-01-31031 January 2022 Form OAR-1 Owner'S Activity Report ML21202A1932021-07-21021 July 2021 Owner'S Activity Report (OAR) for Refueling Outage A1R22 RS-20-126, EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart2020-10-13013 October 2020 EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart ML19030B0872019-01-30030 January 2019 Submittal of Inservice Inspection Summary Report ML15253A9132015-09-11011 September 2015 ACRS Full Committee - Corrections to the Aging Management Programs Table RS-15-059, Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application2015-02-0606 February 2015 Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan RS-10-105, Byron Parent Guarantee Calculation RS-10-1052010-03-10010 March 2010 Byron Parent Guarantee Calculation RS-10-105 ML0934313182009-12-0101 December 2009 Updated Decommissioning Shortfalls as of December 1, 2009 ML0822700142008-08-13013 August 2008 Transmittal of Response to Request for Additional Information Regarding Fall 2007 Steam Generator Inspection ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0707300272007-03-0707 March 2007 Oak Ridge Institute for Science and Education - Letter Report for 18 Water Samples from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2007-003) (Rfta No. 06-001) RS-07-022, Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification2007-02-15015 February 2007 Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification ML0621602722006-07-28028 July 2006 Analytical Results for Fourteen Water Samples, Batch Eight, from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2006-004)(RFTA No. 06-001) ML0617103272006-02-0606 February 2006 Tritium Sample Results ML0617102252005-12-19019 December 2005 Orise Letter Dated 12/19/05, W/Personal Notes, Analytical Results for Water Samples Near the Braidwood Nuclear Generation Station in Braidwood, Illinois, Inspection Report 456/457/2005-010 - Rfta No. 06-001 ML0610106942005-12-16016 December 2005 Schematic of Regional Hydrogeology ML0609606442005-11-17017 November 2005 Tritium Sample Results; NRC Split Sample Results ML0522300142005-03-0909 March 2005 RIC 2005 Presentation - F4 - Dale Ambler - Rop/Cross Cutting Issues RS-04-191, Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-3192004-12-16016 December 2004 Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-319 ML0609605552001-01-31031 January 2001 Revision 5 of Table 11a (Continued) Teen Inhalation Dose Factors 2022-01-31
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23305A0412023-11-0101 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 Owner'S 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 Owner'S 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 ML0920502512009-07-16016 July 2009 Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14) ML0920502592009-07-16016 July 2009 Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report 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 ML0702906712007-01-29029 January 2007 Inservice Inspection Summary Report 2023-08-11
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles 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 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 102023-04-20020 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 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
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3.5J 00 So.uth. Ro.ute: 53.i S.uite. 84 Btac.eiJjilS;;. IL 6040N)6;t9, www.exeJbncorp.com January 30, 2019 BW190014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Renewed Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Braidwood Station, Unit 2 lnservice Inspection Summary Report Enclosed please find the post-outage summary report (i.e., 90-day report) for lnservice Inspection (ISi) examinations conducted prior to and during Braidwood Station, Unit 2 Refueling Outage 2 O (A2R20). This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for the lnservice Inspection of Nuclear Power Plant Components," and ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission - Section XI, Division 1." provides the Owner's Activity Report (OAR) for ISi activities conducted prior to and during A2R20 including a list of items with flaws or relevant conditions that required evaluation for continued service, and an abstract of repair/replacement activities required for continued service. In addition, Attachment 2 provides a summary description in relation to proper snubber receipt documentation from the A2R20 refueling outage.
Please direct any questions you may have regarding this submittal to Mr. Francis Jordan, Regulatory Assurance Manager, at (815) 417-2800.
Marri Marchionda-Palmer Site Vice President Braidwood Station Attachments:
- 1. Owner's Activity Report (OAR) for refueling outage A2R20
- 2. Identified Code Reconciliation for A2R20 Snubbers cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector- Braidwood Station NRR Project Manager- Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1, ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE TABLE 2, ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE
FORM OAR-1 OWNER'S ACTIVITY REPORT Plant Braidwood Generating Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60407 Unit No. 2 Commercial Service Date ___O-"--ct~ob-"--e'--r_1_7.._,_19""'8'""'8___ Refueling Outage Number _ __;..A=2.:...:
R=20.:.____
{if applicable)
Current Inspection Interval Third Inspection Interval (ISI), Second Inspection Interval (Containment ISi)
- (l", 2nd, Jrd, 4t11, other)
Current Inspection Period Third Inspection Period (ISi and Containment !SI)
(l", Zrvl, Jrd )
Edition and Addenda of Section XI applicable to the Inspection Plans ASME Section XI 2001 Edition through 2003 Addenda Date and Revision of Inspection Plans September 29, 2017 I Rev. 18; January 26, 2018 I Rev. 19; June 29, 2018 I Rev. 20 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above Code Cases used: N-460, N-508-4, N-513-4, N-532-5, N-566-2, N-597-2, N-639, N-652-2, N-700, N-706-1, N-729-4, N-731, N-747, N-753, N-798 N-800.
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of A2R20 conform to the requirements of Section XI (refueling outage number) 4-e. f/kr-7--
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~ 01/29/2019 Signed Date
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CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or .a loss of any kind arising from or connected with this inspection.
P-~
(Inspector's Signature)
Commission 15.5 3~
(National Board Number afxl Endorsement)
Date J/2}'r/Zo 1~
See Attachment 1 and Attachment 2 for complete A2R20 Outage Summary Report.
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Examination Item Cateaorv Number Item Description Evaluation Description C-H C?.10 Dry boric acid at 2RH619 IR 4183438.
flange bolting. EC 625976 to address Code Case N-566-2.
TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description Of Work Completed Plan Number 3 2SX03A-30" Replacement of pipe/fittings 2/1/2018 W04585755 based on NDE results. (Plan 2-17-007) 3 28X052A Replaced butterfly valve that 6/5/2018 W04681760 was previously installed (Plan 2-18-025) backwards.
3 2DG01KA-X1 Replaced upper channel head 6/1/2018 WO 1648835 with spare (IR 4145676). (Plan 2-18-027) 3 2CC94958 Replacement of valve parts 10/11/2018 WO 1865859 durino check valve inspection . (Plan 2-18-010) 2 28188568 Replacement of relief valve. 10/15/2018 W04617928 (Plan 2-18-020) 3 28XA9A-6" Replaced sections of degraded 10/19/2018 W04842302 pipe OR 4183923). (Plan 2-18-053) 1 2RC8001A Repair leak-off line (IR 10/15/2018 WO 4644410 4012940, 4200351, 4202190). tPlan 2-1tj-(n4J 1 2RC8001C Repair leak-off line (IR 10/16/2018 W04644409 4012941). (Plan 2-18-013) 1 2RC8001D Repair leak-off line (IR 10/17/2018 WO 4644408 4012943). (Plan 2-18-011) 1 2RC8002A Repair leak-off line (IR 10/16/2018 W04644406 4012945). (Plan 2-18-012) 1 251100315 Replacement of 281100318 due 10/16/2018 WO 4657610-52 to functional test failure (IR (Plan 2-18-042) 4183330).
3 2AF02A Broken stud on oil cooler head 10/19/2018 W04792976 (IR 4183969, IR 4200723, ECR (Plan 2-18-054) 439447, ECR 439497).
3 2AF05003V Required adjustment for 10/18/2018 W04842042 component support identified during Section XI exam (IR 4183474).
2 2RC48AD-3/8" Repair 2RC01 BD SG bowl 10/13/2018 W04838931 drain line (IR 4181129).
3 2AF03029X Required adjustment for 10/19/2018 WR 1411471 component support identified during Section XI exam (IR 4183476).
3 2SX011 Replace existing bolting on 9/19/2018 WO 4655919-01 valve based on Part 21 (Plan 2-17-028) notification from Curtiss-Wright (IR 4022393, 4022584).
3 2SX007 Replace cap screws based on 1/11/2018 WO 4656021-01 Part 21 notification (IR (Plan 2-17-030) 4022393, 4022584).
ATTACHMENT 2 IDENTIFIED CODE RECONCILIATION FOR A2R20 SNUBBERS
Braidwood IR 4214087 is a follow up to IR 4201815 and documents that the receipt documentation for snubbers 2SD23098S, 2Sl18049S, 2SI05013S, and 2AB23034S cannot be retrieved through plant records. Currently, all attempts to locate the receipt inspection paperwork for these four snubbers remains unsuccessful. The snubbers in question have been stored and controlled in either the Braidwood or Byron warehouse and through the Passport inventory system. They were all successfully functionally tested prior to installation during A2R20.
Certificate of Conformance and code data reports were obtained for these snubbers and documented compliance with Class 1 requirements to ASME Code Section Ill, Subsection NF, Division 1 of the 1977 Edition Winter 1977 Addenda. The applicable Braidwood Code of Construction is ASME Code Section Ill, Subsection NF, Division 1 of the 1974 Edition Summer 1974 Addenda. Thpri:>fnr"'. ~ r.nrle reconr.iliation i!':. required to resolve any varii:mce that may exist with the two code years menti.oned here. This condition was entered in the Braidwood Corrective Action Program (CAP) for identification and resolution. Again, reference IR 4214087 and IR 4201815 for complete details.