ML17286A009

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Review of the Steam Generator Tube Inservice Inspection Report for Refueling Outage 24 (CAC No. MF9272; EPID L-2017-LRO-0004)
ML17286A009
Person / Time
Site: Beaver Valley
Issue date: 12/12/2017
From: Booma Venkataraman
Plant Licensing Branch 1
To: Bologna R
FirstEnergy Nuclear Operating Co
Venkataraman B, NRR/DORL/LPL1
References
CAC MF9272, EPID L-2017-LRO-0004
Download: ML17286A009 (3)


Text

Mr. Richard D. Bologna Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 12, 2017 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 THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR REFUELING OUTAGE 24 (CAC NO. MF9272; EPID L-2017-LR0-0004)

Dear Mr. Bologna:

By letter dated February 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17044A360), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the fall 2016 steam generator (SG) tube inspections at Beaver Valley Power Station, Unit No. 1. These inspections were performed during refueling outage (RFO) 24.

The SGs at Beaver Valley, Unit No. 1, were replaced in 2006 with Westinghouse Model 54F SGs that contain 3,592 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 are supported by stainless steel Type 405 tube support plates with broached quatrefoil holes (the flow distribution baffle has octafoil shaped holes).

The licensee provided the scope, extent, methods, and results of its SG tube inspections in its February 13, 2017, letter. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.

After a review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments/observations:

The licensee performed foreign object search and retrieval and identified 16 objects, with 12 objects being retrieved. The licensee stated that the 4 objects that were not retrieved were bounded by the unit-specific loose parts evaluation and determined to be acceptable for continued operation for at least three operating cycles (i.e., until the next inspection).

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by its technical specifications. In addition, the staff concludes that there are no technical issues that warrant followup action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation. The NRC staff concludes that the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

If you have any questions regarding this matter, I may be reached at (301) 415-2934 or Boom a.Venkataraman@nrc.gov.

Docket No. 50-334 cc:

Distribution via Listserv Sincerely, Booma Venkataraman, Project Manager Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO. 1 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR REFUELING OUTAGE 24 (CAC NO. MF9272; EPID L-2017-LR0-0004) DATED DECEMBER 12, 2017 DISTRIBUTION:

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