ML13114A960
| ML13114A960 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/02/2013 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Emily Larson FirstEnergy Nuclear Operating Co |
| Bamford P | |
| References | |
| TAC ME9853 | |
| Download: ML13114A960 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 May 2,2013 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2012 REFUELING OUTAGE (TAC NO. ME9853)
Dear Mr. Larson:
By letter dated October 24,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12299A088), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.1. These inspections were performed during the spring 2012 refueling outage. The report was submitted pursuant to BVPS, Unit No.1, Technical Specification (TS) 5.6.6.1. In response to questions from the U.S.
Nuclear Regulatory Commission (NRC) staff, supplemental information was provided by the licensee on March 8, 2013 (ADAMS Accession Number ML13070A227).
The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.1, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TAC is being closed.
Please contact me at 301-415-2833, if you have any questions.
Sincerely, Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensillg Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Staff Summary cc w/encl: Distribution via Listserv
STAFF
SUMMARY
REGARDING THE STEAM GENERATOR TUBE INSERVICE INSPECTIONS FOR THE SPRING 2012 REFUELING OUTAGE FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO.1 DOCKET NO. 50-334 By letter dated October 24, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12299A088), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.1. These inspections were performed during the spring 2012 refueling outage. The report was submitted pursuant to BVPS, Unit No.1, Technical Specification (TS) 5.6.6.1. In response to questions from the U.S.
Nuclear Regulatory Commission (NRC) staff, supplemental information was provided by the licensee on March 8, 2013 (ADAMS Accession Number ML13070A227).
The SGs at BVPS Unit No. 1 were replaced in 2006 with Westinghouse Model 54F SGs that contain 3592 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes have been hydraulically expanded into the tubesheet and the stainless steel Type 405 tube support plates contain broached quatrefoil holes (the flow distribution baffle has octafoil shaped holes).
The licensee provided the scope, extent, methods, and results of the SG tube inspections in the documents referenced above. The staff and the licensee held a telephone conference, on April 18, 2013, to clarify the active degradation mechanisms reported by the licensee. During the telephone conference, the licensee indicated that although one bobbin indication was initially attributed to anti-vibration bar (A VB) wear, further examinations with a Plus Point probe indicated no degradation was present. As a result, section b of the October 24, 2012, report should not list AVB wear as an active degradation mechanism.
Based on a review of the information provided, the staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the 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 inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
May 2,2013 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO.1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2012 REFUELING OUTAGE (TAC NO. ME9853)
Dear Mr. Larson:
By letter dated October 24,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12299A088), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit No.1. These inspections were performed during the spring 2012 refueling outage. The report was submitted pursuant to BVPS, Unit No.1, Technical Specification (TS) 5.6.6.1. In response to questions from the U.S.
Nuclear Regulatory Commission (NRC) staff, supplemental information was provided by the licensee on March 8, 2013 (ADAMS Accession Number ML13070A227).
The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.1, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TAC is being closed.
Please contact me at 301-415-2833, if you have any questions.
Sincerely, Ira!
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Staff Summary cc w/encl: Distribution via Listserv DISTRIBUTION:
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