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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 type:BW
MONTHYEARBW230058, Submittal of Integrated Initial License Training Written Examination Materials2023-12-20020 December 2023 Submittal of Integrated Initial License Training Written Examination Materials BW230048, Outage 23 and Unit 2 Refueling Outage 23 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-11-0101 November 2023 Outage 23 and Unit 2 Refueling Outage 23 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements BW230046, 10 CFR 72.48 Evaluation Summary Report2023-10-0909 October 2023 10 CFR 72.48 Evaluation Summary Report BW230045, Registration of Use of Casks to Store Spent Fuel2023-09-27027 September 2023 Registration of Use of Casks to Store Spent Fuel BW230039, Inservice Inspection Summary Report2023-08-11011 August 2023 Inservice Inspection Summary Report BW230024, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2023-05-12012 May 2023 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW230007, Regulatory Commitment Change Summary Report2023-02-10010 February 2023 Regulatory Commitment Change Summary Report BW230003, Inservice Inspection Summary Report2023-01-18018 January 2023 Inservice Inspection Summary Report BW220080, 10 Gfr 50.59 Summary Report2022-12-15015 December 2022 10 Gfr 50.59 Summary Report BW220078, Submittal of Licensee Event Report 2022-001-00 - Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation2022-11-30030 November 2022 Submittal of Licensee Event Report 2022-001-00 - Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation BW220048, Registration of Use of Casks to Store Spent Fuel2022-08-10010 August 2022 Registration of Use of Casks to Store Spent Fuel BW220044, Registration of Use of Casks to Store Spent Fuel2022-07-0606 July 2022 Registration of Use of Casks to Store Spent Fuel BW220041, Registration of Use of Casks to Store Spent Fuel2022-06-29029 June 2022 Registration of Use of Casks to Store Spent Fuel BW220037, Registration of Use of Casks to Store Spent Fuel2022-06-15015 June 2022 Registration of Use of Casks to Store Spent Fuel BW220028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-05-13013 May 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW220024, Annual Dose Report for 20212022-04-14014 April 2022 Annual Dose Report for 2021 BW220011, Inservice Inspection Summary Report2022-01-31031 January 2022 Inservice Inspection Summary Report BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021 Revision to Unit 1 Inservice Inspection Summary Report BW210082, Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor2021-12-15015 December 2021 Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor BW210060, National Pollutant Discharge Elimination System2021-08-20020 August 2021 National Pollutant Discharge Elimination System BW210048, Submittal of Analytical Evaluation in Accordance with ASME Code Section XI2021-07-0707 July 2021 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI BW210030, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-05-15015 May 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW210026, Annual Dose Report for 20202021-04-15015 April 2021 Annual Dose Report for 2020 BW200090, CFR 50.59 Summary Report2020-12-15015 December 2020 CFR 50.59 Summary Report BW200095, Inservice Inspection Summary Report2020-12-0909 December 2020 Inservice Inspection Summary Report BW200082, Registration of Use of Casks to Store Spent Fuel2020-10-21021 October 2020 Registration of Use of Casks to Store Spent Fuel BW200072, Registration of Use of Casks to Store Spent Fuel2020-09-23023 September 2020 Registration of Use of Casks to Store Spent Fuel BW200069, Request Registration of Use of Casks to Store Spent Fuel2020-08-27027 August 2020 Request Registration of Use of Casks to Store Spent Fuel BW200057, Bwd 2020 Ile Post-Exam Package Cover2020-06-27027 June 2020 Bwd 2020 Ile Post-Exam Package Cover BW200038, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-05-15015 May 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW200035, Annual Dose Report for 20192020-04-29029 April 2020 Annual Dose Report for 2019 BW190114, Ile Outline Submittal Letter2019-12-16016 December 2019 Ile Outline Submittal Letter 2023-09-27
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Exelon Generation Company, Ll.C Braidwood Station Exelon Generation" 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 December 15, 2021 10 CFR 50.55a(g)
BW210083 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRC Docket No. STN 50-456 .
Subject:
Braidwood Station, Revision to Unit 1 lnservice Inspection Summary Report
Reference:
Letter from M. Marchionda Palmer (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, " Braidwood Station, Unit 1 lnservice Inspection Summary Report" dated January 17, 2020 Enclosed please find the revision to post-outage summary report for lnservice Inspection (ISi)
- examinations conducted prior to and during Braidwood Station, Unit 1 Refueling Outage 21 (A 1R21 ). 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."
Attachment 1 has been revised from the original report (Reference 1) to provide the Owner's Activity Report (OAR) for ISi activities conducted prior to and during A 1R21 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. Ncite 1 has been included for the clarification of the revision.
Please direct any questions you may have regarding this submittal to Mr. Richard Schliessmann, acting Regulatory Assurance Manager, at (815) 417-2820.
Keenan Jo hn P. ON:cn=Keenan,JohnP.
Digitally signed by Keenan, John P.
I Date: 2021.12.13 06:55:48 -06'00' John Keenan Site Vice President Braidwood Station
Attachment:
- 1. Owner's Activity Report (OAR) for A 1.R21 cc: Regional Admiflistrator - NRC Region Ill NRC Senior Resident Inspector- Braidwood Station NRR Project Manager- Braidwood Station Illinois Emergency Management Ag~ncy - 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 Report Number Plant A1R21 Braidwood Generating Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60407 Unit No. ____1_-,-_ Commercial Service Date ---"'"Ju=lyL..=2""9""'1""9-"8=8_ _ _ Refueling Outage Number AlR21 (if applicable)
Current Inspection Interval Fourth Inspection Interval (ISI), Third Inspection Interval (Containment ISI)
(1't, 2nd, 3'd, 4'h, other)
Current Inspection Period First Inspection Period (ISi and Containment ISi)
(l", 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans ASME Section XI 2013 Edition, No Addenda Date and Revision of Inspection Plans _O_ct_o_b_er_9_1_.h,_2_0_1_8..,/_R_e_v_._O._;- - - - . , - - - - - - - - - - - - - - - - - - - -
Edition and Addenda of Section XI applicable to repair/replacement a!=tivlties, if different than the insp~ction plans Same as above Code Cases used: N-513~4, N-532-5 N-639, N-729-4 N-731 N-747, 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 <::ode,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of A1R21 conform to the requirements of Section XI (refueling outage number)
Signed Mcw.J.;r s~ , - ~ - Date 12/02/2021 (Owner or Owner's designee. Title)
CERTIFICATE OF INSERVICE INSPECTION I, the undersign.ed, 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 ~his 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.
..,.JAAew,J,._ ~ .
IIJWU/.A-1'~ Commission 1'18 /Jl,,U. /N/C.
. . ~ r ' s Signature) ~ (National Board Number and Endorsement)
Date
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Examination Item Cateaorv Number Item Description Evaluation DescriDtion
(C-C) C3.20 Luo Attach for 1 MS07002C 1MS-07-SW0B (EC-374961)
TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Descriotion Of Work Comoleted Plan Number 3 1DG5048A Replace valve, valve is hard to 04/06/2019 WO # 4624252-01 open. (Plan 1-19-001) 2 1FW035B Replace valve plug retaining 10/11/2019 WO # 4606972-01 rina per IR 2731940 (Plan 1-19-009) 3 1CC9520B Disc and Bushing O-ring 3/15/2019 WO # 1942260-01 needed replaced per IA (Plan 1-19-012) 4225422.
2 1AF014G Exiting valve replaced due to 10/18/2019 WO# 4755065-01 "As Found" test failure per IR (Plan 1-19-058) 4289020 2 1AF014C Exiting valve replaced due to 10/18/2019 WO# 4755066-01 "As Found" test failure per IA (Plan 1-19-059) 4289127 3 0WO01CB Replace 2 degraded fasteners 11/16/2019 WO# 01631000-39 on the west condenser head (Plan 1-19-061) per IR 4297028 2 1S102003S Snubber did not meet functional 10/14/2019 WO # 4835025-82 test criteria and requires (Plan 1-19-055) replacement. Per IR 4287321 .
1 1RC02006S-B Snubber did not meet functional 10/18/2019 WO # 4835025-28 .
test criteria and requires (Plan 1-19-053) replacement per IR 4287143 1 1RC02006S-A Snubber did not meet functional 10/17/2019 WO # 4835025-26 test criteria and requires (Plan 1-19-052) replacement per IR 4287141 2 1CV41036S Degraded snubber requires 10/14/2019 WO # 4835025-22 replacement *per IR 4286524 (Plan 1-19-050 1 1CV16034V Variable Spring Can found out 10/19/2019 WO # 4970350-01 of tolerance per IR 4287731 Corrective Measure (1WF3122.2(a))
2 1FW05024C Constant Spring Can found out 10/19/2019 WO # 4970362-01 of tolerance per IA 4287727 Corrective Measure (1WF3122.2(a))
IR 4454067 has been generated to update Table 1 to remove Code Case N-513 for line 1SX93AB, as UT results from the original inspection were above new calculated minimum wall thickness. Therefore, Code Case N-513 was not used to evaluate the flaw.