ML043090491

Steam Generator Tube Inservice Inspection Report

ML043090491
Person / Time
Site:	Cook
Issue date:	10/28/2004
From:	Jensen J Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:4445
Download: ML043090491 (3)

Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER October 28,2004 AEP:NRC:4445 Docket No: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT Pursuant to the requirements of the Donald C. Cook Nuclear Plant (CNP) Unit 2 Technical Specification 4.4.5.5.a, Indiana Michigan Power Company is submitting this letter to notify the Nuclear Regulatory Commission of the number of tubes plugged during the Unit 2 Cycle 15 steam generator inspection.

Eddy current inspections were conducted on each of the four Unit 2 steam generators during the CNP Unit 2 Cycle 15 refueling outage. No defective tubes were identified during these examinations. However, one tube was classified as degraded due to loose part wear, and was conservatively plugged. The attachment to this letter provides additional details.

This letter contains no new commitments. Should you have any questions, please contact Mr. John- A. Zwolinski, Safety Assurance Director, at (269) 466-2428.

kensen cePresident Attachment RV/rdw

U. S. Nuclear Regulatory Commission AEP:NRC:4445 Page 2 c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King - MPSC C. F. Lyon - NRC Washington, DC MDEQ - WHMD/HWRPS NRC Resident Inspector

ATTACHMENT TO AEP:NRC:4445 EDDY CURRENT FINDINGS AND REPAIRS DURING THE UNIT 2 CYCLE 15 REFUELING OUTAGE Eddy current inspections were conducted on each of the four Unit 2 steam generators during the CNP Unit 2 Cycle 15 refueling outage. The inspection consisted of a full-length examination of 25 percent of the tubes using a bobbin coil probe. This inspection was supplemented by rotating coil examinations of select areas in two steam generators and additional rotating coil inspection of a sample of indications of the bobbin coil data from all four steam generators for enhanced characterization. No defective tubes were identified during these examinations. However, one tube was classified as degraded and was conservatively plugged. The tube in location row 46/column 37 of steam generator 22 was plugged due to wear from a foreign object.

The following table presents the repair status of the Unit 2 steam generators.

Steam Generator Number of Number of Overall Tubes/Steam Plugged Tubes Plugging Generator Percentage SG 21 3592 1 0.028 SG 22 3592 5 0.139 SG 23 3592 6 0.167 SG 24 3592 4 0.111