ML20215B780
| ML20215B780 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/10/1987 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706170448 | |
| Download: ML20215B780 (2) | |
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Portland General Electric COuipeniy David W. Cockfield Vice President, Nuclear June 10, 1987 Trojan Nuclear Plant Docket 50-344 Licenso NPF-1 U.S. Nuclear Regulatory Commission ATTN:. Document Control Desk Washington DC 20555
Dear Sir:
Steam Generator Tube Plugning Report During the 1987 refueling outage, an inservice inspection of the "B"
and "C" steam generator tubes was conducted.
In accordance with Tech-nical Specification 4.4.5.5.a. attached is a listing of the number of tubes plugged and the reason for the plugging.
Sincerely, l
Attachment c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant Mr. David Kish, Director State of Oregon Department of Energy I
l gb 8706170440 870610 PDR ADOCK 05000344 g
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di 121 S.W Salmon Steet Portland. Oregon 97204
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"E Trojan ~ Nuclear. Plant Document Control Desk.
11 Docket 50-344
' June 10, 1987
. License'NPF Attachment Page 1 of 1 l
STEAM GENERATOR TUBE PLUGGING
~During the 1987 refueling' outage..an inservice. inspection of.the "B" and "C" steam generator tubes was conducted. The inspection encompassed
'over 20 percent'of the tubes in each steam generator. Included in the inspection were'all unplugged Row 2 and 3 tubes (examined in the U-bend region) and all tubes with previous-indications.- One tube was plugged ~
'following the= inspection. The tube.is in Row 2 of the "C" steam generator and was plugged due to an indication in the U-bend region.
Prior to.the inspection, it had been anticipated that indications _.would
.be observed in the hard-rolled region of the tubes on the hot-leg side of the "B" steam generator.' Many of these tubes had to'be repaired as
'a result of damage by: loose' parts in 1984.
In subsequent years, indi-'
cations had been observed using the bobbin-coil eddy: current' probe..
In 19874;a bobbin-coil probe was used and the indications were again
' observed.
In characterizing the indications using a rotating eddy current probe, fit ~ was determined there is no tube degradation.
LThe followingLtable lists the number of tubes inspected and plugged in
~
.1987 and the total number'of-tubes plugged;in each steam generator.-
B C
_D.
No. of Tubes Inspected in 1987 0
696 680 0-No. of Tubes Plugged inL1987 0
0' 1
0
- No, of Tubes Plugged Total 125 95 113 125 SAB/kal' 1784W.687