ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report
| ML22074A281 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/15/2022 |
| From: | Boyce M Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ET 22-0004 | |
| Download: ML22074A281 (3) | |
Text
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 Michael T. Boyce Vice President Engineering March 15, 2022 ET 22-0004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
References:
- 1) Letter ET 21-0009, dated November 1, 2021, from Stephen L.
Smith, WCNOC, to USNRC, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage
- 2) Electronic mail dated February 14, 2021, from Samson Lee, USNRC, to Joshua Turner, WCNOC, Request for Additional Information - Steam Generator Inspection Report 24th Refueling (EPID L-2021-LRO-0060)
Subject:
Docket No. 50-482: Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report Commissioners and Staff:
In accordance with the Wolf Creek Generating Station (WCGS) Technical Specification (TS) 5.6.10, Steam Generator Tube Inspection Report, in Reference 1, Wolf Creek Nuclear Operating Corporation (WCNOC) provided the Steam Generator Tube Inspection Report detailing the results of WCGSs steam generator (SG) tube in-service inspection performed during Refueling Outage (RF24). By electronic mail dated February 14, 2021, the U.S. Nuclear Regulatory Commission (NRC) indicated that the staff had reviewed the inspection report and requested that additional information, written as a request for confirmation of information (RCI), be provided so that the NRC could complete their review of the Steam Generator Tube Inspection Report (Reference 2). The attachment to this letter provides the relevant information contained in Reference 2, as well as WCNOCs responses to the RCI inquiries.
ET 22-0004 Page 2 of 2 If you have any questions concerning this matter, please contact me at (620) 364-8831 X8687, or Ron Benham at (620) 364-4204.
Sincerely, Michael T. Boyce MTB/rlt
Attachment:
Wolf Creek Nuclear Operating Corporation (WCNOC), Unit 1 Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report cc:
S. S. Lee (NRC), w/a S. A. Morris, (NRC), w/a G. E. Werner (NRC), w/a Senior Resident Inspector (NRC), w/a
Attachment to ET 22-0004 Page 1 of 1 WOLF CREEK NUCLEAR OPERATING CORPORATION (WCNOC), UNIT 1 RESPONSE TO REQUEST FOR CONFIRMATION OF INFORMATION (RCI) REGARDING STEAM GENERATOR TUBE INSPECTION REPORT Regulatory Basis:
All pressurized water reactors have Technical Specifications (TS) according to § 50.36 of Title 10 of the Code of Federal Regulations that include a steam generator (SG) Program with specific criteria for the structural and leakage integrity, repair, and inspection of SG tubes. Wolf Creek TS Section 5.6.10 requires that a report be submitted within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection of the SGs performed in accordance with TS Section 5.5.9, which requires that a SG Program be established and implemented to ensure SG tube integrity is maintained.
Background:
By letter dated November 1, 2021, the licensee submitted information summarizing the results of the spring 2021 SG inspections performed at Wolf Creek. These inspections were performed during refueling outage 24. In addition, the 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.
Request:
To complete its review of the inspection report, the NRC staff requests the licensee to submit confirmation that the NRC staffs understanding described below is correct, or provide the corrected information:
Page 3 of 9 of the spring 2021 SG tube inspection report states, 100% Bobbin inspection of tubes in all four SGs, full length, except for Row 1 tubes [emphasis added] which were inspected with the bobbin from tube end to TSP#7 on both HL [hot leg] and CL [cold leg].
The NRC staffs understanding of the inspection scope is that a full-length bobbin probe inspection of all in-service tubes in each SG was performed, except for the U-bend sections in Rows 1 and 2 [emphasis added], which were inspected with a +Point' rotating probe in 50 percent of the tubes. Therefore, the NRC staff believes the statement on Page 3 of 9 of the spring 2021 SG tube inspection report should read,100% Bobbin inspection of tubes in all four SGs, full length, except for Rows 1 and 2 tubes [emphasis added] which were inspected with the bobbin from tube end to TSP#7 on both HL and CL. Please confirm the NRC staffs understanding of the SG tube inspection scope performed during spring 2021.
Response to Request:
As it pertains to the confirmation of information question, the response is no. The Wolf Creek SG Inspection Report is correct as provided in Reference 1. For Row 1 and Row 2 U-bend inspections, the following eddy current inspections were performed:
100% Bobbin inspection of tubes in all four SGs, full length, except for Row 1 tubes which were inspected with the bobbin from tube end to TSP#7 on both HL and CL.
50% Row 1 and Row 2 U-bends, mid-range +Point' probe examination.
The inspection plan did not require the Row 2 U-bends to be inspected with Bobbin. However, the Bobbin coil / Zephyr' probe inspections were performed full length for Rows 2 and higher.