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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23305A0412023-11-0101 November 2023
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Form OAR-1 Owner'S Activity Report
BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021
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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
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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
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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
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Submittal of Inservice Inspection Summary Report
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Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 1
ML18208A2942018-07-27027 July 2018
Fourth Ten-Year Interval Inservice Testing Program Plan
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ML15198A1952015-07-16016 July 2015
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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
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ML14318A2112014-11-14014 November 2014
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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
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ML13358A4002013-12-20020 December 2013
Inservice Inspection Summary Report for Refueling Outage 17
ML13037A5062013-02-0606 February 2013
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ML12251A3592012-08-17017 August 2012
(Returned to DCD) Braidwood Station, Unit 1, Steam Generator Tube Inspection Report for Refueling Outage 15
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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
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Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14)
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Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report
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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 .
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Inservice Inspection Summary Report for: Interval 2, Period 3, Outage 2 A2R13 Outage
ML0802205262008-01-22022 January 2008
Inservice Inspection Summary Report
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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
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Inservice Inspection Summary Report
2023-08-11
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Exe Iukn.
Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 October 29, 2004 BW040098 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Braidwood Station, Unit 1 Facility Operating License No. NPF 72 NRC Docket No. STN 50-456
Subject:
October 2004, Eleventh Refuel Outage Steam Generator Inservice Inspection Report In accordance with Technical Specification 5.6.9, "Steam Generator (SG) Tube Inspection Reports," Exelon Generation Company, LLC is reporting the number of tubes plugged or repaired during the SG inservice inspection activities conducted during the Braidwood Station, Unit 1 October 2004 eleventh refueling outage. Technical Specification 5.6.9.a requires that following each inservice inspection of the SG tubes, the number of tubes plugged or repaired in each SG shall be reported to the NRC within 15 days.
The Braidwood Station Unit 1 October 2004 eleventh refueling outage SG tube eddy current inspection scope included 100% full-length bobbin coil inspection of the 1B SG. Scope expansion into the 1A,1 C and 1D was also conducted. The 1A,1 C and 1D scope expansion included approximately 22% bobbin coil inspection of the hot leg tubing. In addition, the peripheral tube regions of the cold leg tubing were inspected equaling approximately 15.5% of the cold leg tubing.
+PointM coil inspection was conducted on bobbin coil indications classified as requiring additional diagnostic testing.
The SG tube inspections were completed on October 18, 2004. No tube sleeving was performed during this outage. The Braidwood Unit 1 Steam Generator Tube Plugging Summary summarizes the inspection results during the October 2004 eleventh refueling outage and number of tubes removed from service to date by tube plugging.
BRAIDWOOD UNIT 1 STEAM GENERATOR TUBE PLUGGING
SUMMARY
- SGA l SGB SG C SG D Total Prema* Rugged 10 12 3 0 25 Rugged Durting October 2004 Refueling outage 0 2 2 1 5 Total 10 14 5 1 30 Please direct any questions regarding this submittal to Dale F. Ambler, Braidwood Regulatory Assurance Manager, (815) 417-2800.
Sincerely, T.P.Jy Site Vice President Braidwood Station cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station
