Letter Sequence Approval |
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EPID:L-2021-LRO-0060, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage (Approved, Closed) |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23075A0742023-03-16016 March 2023 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 25 Owners Activity Report ML23075A1632023-03-16016 March 2023 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 25 Owners Activity Report ML22124A0062022-05-0505 May 2022 Review of the Spring 2021 Refueling Outage 24 Steam Generator Tube Inservice Inspection Report ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ML21217A3342021-08-0505 August 2021 Inservice Inspection Program Fourth Interval, Second Period, Refueling Outage 24 Owner'S Activity Report ML21217A3352021-08-0505 August 2021 Containment Inservice Inspection Program Third Interval, First Period, Refueling Outage 24 Owner'S Activity Report ML20042C8922020-02-0404 February 2020 Containment Inservice Inspection Program Third Interval, First Period, Refueling Outage 23 Owner'S Activity Report ML20042C8962020-02-0404 February 2020 Lnservice Inspection Program Fourth Interval, Second Period, Refueling Outage 23 Owner'S Activity Report ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ML18234A1322018-08-14014 August 2018 Submittal of Containment Inservice Inspection Program Second Interval, Third Period, Refueling Outage 22 Owner'S Activity Report ML18234A1312018-08-14014 August 2018 Lnservice Inspection Program Fourth Interval, First Period, Refueling Outage 22 Owner'S Activity Report ET 17-0008, Results of the Twentieth Steam Generator Tube Lnservice Inspection2017-05-0202 May 2017 Results of the Twentieth Steam Generator Tube Lnservice Inspection ET 17-0007, CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval2017-04-13013 April 2017 CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval ET 16-0005, Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval2016-02-23023 February 2016 Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval ET 15-0024, Results of the Nineteenth Steam Generator Tube Inservice Inspection2015-10-20020 October 2015 Results of the Nineteenth Steam Generator Tube Inservice Inspection ET 15-0022, Fourth Ten-Year Interval Submittal Snubber Program Plan and Inservice Testing Program Plan, WCOP-29, Revision 02015-09-0202 September 2015 Fourth Ten-Year Interval Submittal Snubber Program Plan and Inservice Testing Program Plan, WCOP-29, Revision 0 ML15217A0222015-07-28028 July 2015 Containment Inservice Inspection Program Second Interval, Second Period, Refueling Outage 20 Owner'S Activity Report ML15222A2512015-07-28028 July 2015 Inservice Inspection Program Third Interval, Third Period, Refueling Outage 20 Owner'S Activity Report ET 14-0018, 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval2014-06-26026 June 2014 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval ML14174B1232014-06-25025 June 2014 Review of 18th Steam Generator Tube Inspection Report ET 13-0030, Results of the Eighteenth Steam Generator Tube Inservice Inspection2013-09-30030 September 2013 Results of the Eighteenth Steam Generator Tube Inservice Inspection ML13199A2362013-07-11011 July 2013 Submittal of Containment Inservice Inspection Program Second Interval, Second Period, Refueling Outage 19 Owner'S Activity Report ET 11-0008, (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection2011-10-19019 October 2011 (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection ML11263A1492011-09-13013 September 2011 Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner'S Activity Report ML11263A1482011-09-13013 September 2011 Inservice Inspection Program Third Interval, Second Period, Refueling Outage 18 Owner'S Activity Report ET 10-0012, Results of the Sixteenth Steam Generator Tube Inservice Inspection2010-04-0808 April 2010 Results of the Sixteenth Steam Generator Tube Inservice Inspection ML1004907522010-02-0909 February 2010 Submittal of Inservice Inspection Program Third Interval, Second Period, Refueling Outage 17 Owner'S Activity Report ML0822603672008-08-0606 August 2008 Containment Inservice Inspection Program First Interval, Third Period, Owner'S Activity Reports ML0822603412008-08-0606 August 2008 Inservice Inspection Program Third Interval, First Period, Refueling Outage 16 Owner'S Activity Report ML0704304622007-01-31031 January 2007 Containment Inservice Inspection Program First Interval, Third Period, Refueling Outage 15 Owner'S Activity Report RA-07-0012, Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report2007-01-31031 January 2007 Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report ML0614503192006-05-19019 May 2006 10 CFR 50.55a Request I3R-05, Installation and Examination of Full Structural Weld Overlays for Repairing/Mitigating Pressurizer Nozzle-to-Safe End Dissimilar Metal Welds and Adjacent Safe End-to Piping Stainless Steel Welds ET 06-0011, CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval2006-03-0202 March 2006 CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval ET 06-0010, Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-042006-03-0202 March 2006 Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04 ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 02006-02-0101 February 2006 Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0 ET 05-0004, Steam Generator Tube Plugging Report2005-05-0404 May 2005 Steam Generator Tube Plugging Report WM 04-0046, Results of the Twelfth Steam Generator Tube Inservice Inspection2004-10-27027 October 2004 Results of the Twelfth Steam Generator Tube Inservice Inspection WM 04-0008, Request to Extend the Second 10-year Inservice Inspection (ISI) Interval for Reactor Pressure Vessel Examinations, 10 CFR 50.55a Request 12R-282004-04-15015 April 2004 Request to Extend the Second 10-year Inservice Inspection (ISI) Interval for Reactor Pressure Vessel Examinations, 10 CFR 50.55a Request 12R-28 ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program2003-08-26026 August 2003 Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program ML0319704482003-07-0808 July 2003 Inservice Inspection Program Second Interval, Second Period Owner'S Activity Reports ET 02-0046, Results of Eleventh Steam Generator Tube Inservice Inspection2002-12-11011 December 2002 Results of Eleventh Steam Generator Tube Inservice Inspection ET 02-0049, Containment Inservice Inspection Program First Interval, First Period Owner'S Activity Reports2002-11-0404 November 2002 Containment Inservice Inspection Program First Interval, First Period Owner'S Activity Reports 2023-03-16
[Table view] Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] |
Text
May 5, 2022 Mr. Cleveland Reasoner Chief Executive Officer and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1 - REVIEW OF THE SPRING 2021 REFUELING OUTAGE 24 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (EPID L-2021-LRO-0060)
Dear Mr. Reasoner:
By letter dated November 1, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21305B855), as supplemented by letter dated March 15, 2022 (ML22074A281), Wolf Creek Nuclear Operating Corporation (the licensee) submitted a summary of the results of the spring 2021 steam generator (SG) inspections performed at Wolf Creek Generating Station, Unit 1. The inspections were performed during Refueling Outage 24.
The SG tube inspection report was submitted in accordance with Technical Specification (TS) 5.6.10, Steam Generator Tube Inspection Report.
Based on its review, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee has provided the information required by TS 5.6.10, and that no follow-up is required at this time. A summary of the NRC staff's review is enclosed.
If you have any questions, please contact me at 301-415-3168 or via e-mail at Samson.Lee@nrc.gov.
Sincerely,
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Review of the Steam Generator Tube Inspection Report cc: Listserv
REVIEW OF THE SPRING 2021 REFUELING OUTAGE 24 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION, UNIT 1 DOCKET NO. 50-482 By letter dated November 1, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21305B855), as supplemented by letter dated March 15, 2022 (ML22074A281), Wolf Creek Nuclear Operating Company (the licensee) submitted information summarizing the results of the spring 2021 steam generator (SG) inspections performed at Wolf Creek Generating Station, Unit 1 (Wolf Creek). These inspections were performed during Refueling Outage 24 (RF24). In addition, the U.S. Nuclear Regulatory Commission (NRC) staff held a conference call with the licensee on April 16, 2021, regarding the ongoing SG inspection activities at Wolf Creek. A summary of the conference call regarding the spring 2021 SG inspections is available in ADAMS under Accession No. ML21127A132. The licensee provided additional information concerning the inspections in its letter dated March 15, 2022 Wolf Creek has four Westinghouse Model F SGs. Each SG contains 5,626 thermally treated Alloy 600 tubes. Each tube has a nominal outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are supported by stainless steel tube supports with quatrefoil-shaped holes and V-shaped chrome-plated Alloy 600 anti-vibration bars. The tubes are hydraulically expanded for the full depth of the tubesheet at each end.
The licensee provided the scope, extent, methods, and results of the SG tube inspections in its letter dated November 1, 2021, as supplemented. In addition, the licensee described corrective actions (e.g., tube plugging) that were taken in response to the inspection findings.
Based on the review of the information provided, the NRC staff has the following observations:
Wear was the only degradation mechanism found and 32 tubes were plugged due to wear during RF24. Thirty tubes with anti-vibration bars wear indications greater than 40 percent through-wall were plugged (5 in SG A, 12 in SG B, 3 in SG C, and 10 in SG D). Two tubes with new foreign object wear indications attributed to transient foreign objects were preventatively plugged (one each in SGs A and B).
No indications of primary water stress corrosion cracking or outside diameter stress corrosion cracking were found during RF24.
In the March 15, 2022, letter, the licensee clarified that full length Bobbin coil/Zephyr' probe inspections were performed in Rows 2 and higher. In addition, as stated in the licensees letter dated November 1, 2021, 50 percent of the Rows 1 and 2 U-bends received a mid-range +Point' probe inspection.
Enclosure
The area of channel head wastage due to cladding breach initially found in SG A during RF19 was visually and ultrasonically tested during RF24 and no changes were found.
No additional cladding degradation was found in any SG.
Based on the review of the information provided, the NRC staff concludes that the licensee provided the information required by Wolf Creek Technical Specification 5.6.10, Steam Generator Tube Inspection Report. In addition, the NRC staff concludes that there are no technical issues that warrant additional follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
ML22124A006 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DNRL/NCSG/BC NAME SLee PBlechman SBloom DATE 5/4/2022 5/4/2022 3/18/2022 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME JDixon-Herrity SLee DATE 05/05/2022 05/05/2022