ML20212B614
| ML20212B614 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/20/1987 |
| From: | Morgan H SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8703030600 | |
| Download: ML20212B614 (2) | |
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+**~cwD' Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92672 H.E. MORGAN TE LEPHONE s
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February 20, 1987 U. S. Nuclear Regulatory Commission Attention: : Document Control Desk Washington, D.C.
20555
Subject:
Docket No. 50-362 Special Report - Inservice Inspection of Steam Generator Tubes San Onofre Nuclear Generating Station, Unit 3
Reference:
Letter from Mr. M. O. Medford (SCE) to Mr. G. W. Knighton (USNRC) dated April 5, 1985 Pursuant to Surveillance Requirement 4.4.4.5(a) of Appendix A, Technical Specifications to Facility Operating License NPF-15, this report is being submitted to the Commission following the completion of inservice inspection of steam generator tubes at San Onofre Unit 3.
Eddy current inspection of the steam generator tubing was completed on February 6, 1987. A total of 1117 tubes (6% of the tubes in service) in two steam generators were inspected full length and 20 tubes were removed from service by mechanical plugging.
In steam generator E-088, 840 tubes were inspected. One tube found to be defective due to the wear mechanism previously described in the reference, was plugged. Additionally, eight tubes with indications below the plugging limit, that were due to the wear mechanism previously described in the reference, 4
were preventively plugged.
8703030600 070220
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Document Control Desk.In steam generator E-089, 277 tubes were inspected. One tube, which exhibited degradation during the previous inspection in October 1985, was found to be defective. This defective tube was plugged. A comparison of the eddy current results from the previous inspection and this inspection showed no growth of the flaw. Therefore, as provided for in Technical Specification 4.4.4.2, no program expansion was necessary. Additionally, ten tubes with indications below the plugging' limit, that were due to the wear mechanism previously described in the reference, were preventively plugged.
As required by Surveillance Requirement 4.4.4.5(b), complete results of the recently completed inservice inspection will be submitted to the Commission by February 5,1988.
If you require any additional information, please so advise.
Sincerely, Mbb cc:
J. B. Martin (Regional Administrator, USNRC Region V)
F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)
H. Rood (Project Manager, SONGS 2/3, USNRC, NRR)
Institute of Nuclear Power Operations (INPO) l 1
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