ML021560396
| ML021560396 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/03/2002 |
| From: | Greenlee S Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:2455-01 | |
| Download: ML021560396 (3) | |
Text
Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bndgman, MI 49106 616465-501%
INDIANA MICHIGAN POWER June 3, 2002 AEP:NRC:2455-01 Docket No:
50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT Pursuant to the requirements of the Donald C. Cook Nuclear Plant Unit 1 Technical Specification 4.4.5.5.a, Indiana Michigan Power Company is submitting this letter to notify the Nuclear Regulatory Commission of the results the Unit 1 Cycle 18 steam generator inspection.
Eddy current inspections were conducted on all four Unit 1 steam generators.
No defective or degraded tubes were identified; however, four tubes were administratively plugged as a result of changes in signal response from the original baseline examinations.
The attachment to this letter provides the inspection findings, indication dispositions and the steam generator repair action taken during the Unit 1 Cycle 18 refueling outage.
There are no new commitments in this submittal.
Should you have any questions, please contact Mr. Gordon P. Arent, Manager of Regulatory Affairs, at (616) 697-5553.
Sincerely, S. A. Greenlee Director of Nuclear Technical Services TW/dmb AEP.- A.merica' ý nergi' Parimper,
AEP:NRC:2455-01 U. S. Nuclear Regulatory Commission Page 2 c:
K. D. Curry J. E. Dyer MDEQ - DW & RPD NRC Resident Inspector R. Whale
ATTACHMENT TO AEP:NRC:2455-01 EDDY CURRENT FINDINGS AND REPAIRS DURING THE UNIT 1 CYCLE 18 REFUELING OUTAGE Eddy current inspections were conducted on all four Unit 1 steam generators during the Donald C. Cook Nuclear Plant Unit 1 Cycle 18 outage (U1C 18).
The inspection included a 100 % full-length examination using a bobbin coil probe. In addition, select rotating coil inspections were conducted on a sample of the bobbin data for enhanced characterization. No defective or degraded tubes were identified; however, four tubes were administratively plugged as a result of changes in signal response from the original baseline examination.
The tube locations and indication information is noted below:
Steam Plugged Tube Indication Indication Location Generator Location SG 11 Row 13/Column 85 MBI*
Tubesheet Cold + 14.97" SG 11 Row 16/Column 40 MBI 6h Cold Leg Support +
MBI 34.48" 5t' Cold Leg Support +
37.06" SG 13 Row 19/Column 61 MBI 6e Cold Leg Support +
19.45" SG 14 Row 69/Column 45 MBI l' Cold Leg Support +
12.06"
- Manufacturing Burnish Mark Indication The following table presents the repair status of the Unit 1 steam generators.
Steam Number of Number of Overall Generator Tubes/SG Plugged Tubes Plugging Percentage SG 11 3496 2
0.06 %
SG 12 3496 0
0.0 %
SG 13 3496 1
0.03 %
SG 14 3496 1
0.03 %