ML16004A240
| ML16004A240 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/08/2016 |
| From: | Shawn Williams Plant Licensing Branch II |
| To: | Pierce C Southern Nuclear Operating Co |
| Williams S | |
| References | |
| CAC MF7015 | |
| Download: ML16004A240 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295 January 8, 2016
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 - REVIEW OF THE SPRING 2015 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT DURING REFUELING OUTAGE 26 (CAC NO. MF7015)
Dear Mr. Pierce:
By letter dated October 29, 2015 (Agencywide Documents Access and Management System Accession No. ML15302A277), Southern Nuclear Operating Company (the licensee), submitted information summarizing the results of the steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 1, during refueling outage 26.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their Technical Specifications and that no additional follow-up is required at this time. The NRC staff's review is enclosed.
If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Docket No. 50-348
Enclosure:
As stated cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REVIEW OF THE 2015 STEAM GENERATOR TUBE INSERVICE INSPECTIONS FOR REFUELING OUTAGE 26 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 DOCKET No. 50-348 TAC NO. MF7015 By letter dated October 29, 2015 (Agencywide Documents Access and Management System Accession No. ML15302A277), Southern Nuclear Operating Company (the licensee), submitted information summarizing the results of the steam generator (SG) tube inspections performed at Joseph M. Farley Nuclear Plant (Farley), Unit 1, during refueling outage (RFO) 26.
Farley, Unit 1, has three Westinghouse Model 54F replacement SGs, installed in 2000. Each of the SGs contains 3592 tubes fabricated from thermally treated Alloy 690 material. The tubes have an outside diameter of 0.875 inches, a wall thickness of 0.050 inches, and are supported by a stainless steel flow distribution baffle with octafoil shaped holes and seven stainless steel tube support plates with quatrefoil broached holes.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in respom~e to the inspection findings.
Based on a review of the.information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments/observations.
Tube support plate wear was observed for the first time in the Farley, Unit 1., SGs during RFO 26.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the NRC staff concludes that there are rio 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 inspection results appear to be consistent with industry operating experience at similarly
- designed and operated units.
Enclosure
ML16004A240 OFFICE LPL2-1/PM LPL2-1/LA DE/ESGB/BC NAME SWilliams SFigueroa GKulesa*
DATE 01/07/16 01/07/16 12/29/15