ML15281A387
| ML15281A387 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/26/2015 |
| From: | Martin R Plant Licensing Branch II |
| To: | Pierce C Southern Nuclear Operating Co |
| Martin R | |
| References | |
| CAC MF6052 | |
| Download: ML15281A387 (3) | |
Text
Mr. C. R. Pierce Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October'26, 2015 Southern Nuclear Operating Company, Inc.
Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
VOGTl,..E ELECTRIC GENERATING PLANT, UNIT 2 - REGARDING THE FALL
. 2014 STEAM GENERATOR TUBE INSPECTION (CAC NO. MF6052)
Dear Mr. Pierce:
By letters dated April 2 and August 28, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15092A834 and ML15240A381), Southern Nuclear Operating Company, Inc. submitted information summarizing the results of the fall 2014 steam generator (SG) tube inspections performed at Vogtle Electric Generating Plant (VEGP), Unit 2.
These inspections were performed during refueling outage (RFO) 17.
The VEGP, Unit 2, has four Westinghouse Model F SGs, each of which contains 5,626 U-bend 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. During SG fabrication, the tubes were hydraulically expanded, at both ends, over the full depth of the tubesheet. The vertical section of the tubes are supported by Type 405 stainless steel support plates with quatrefoil-shaped holes and the U-bend section of the tubes is supported by V-shaped, chrome-plated Alloy 600 anti-vibration bars.
You provided the scope, extent, methods, and results of the SG tube inspections in the documents referenced above. In addition, you described corrective actions (i.e., tube plugging) taken in response to the inspection findings. After reviewing the information provided by the licensee, the NRC staff noted that there were no crack indications identified during RFO 17.
Based on a review of the information provided, the NRC staff concludes that you provided the information required by your technical specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the
C. inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Docket No. 50-425 cc: Distribution via Listserv Sincerely, J3()j /J1 ar f,/1-
/~'.:~ Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML15281A387 Sincerely,
/RA/
Bob Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource AJohnson, NRR AHuynh, NRR
- by memo dated OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DE/ESGB/BC DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME BMartin SFigueroa GKulesa RPascarelli BMartin DATE 10/13/15 10/09/15 09/24/15*
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