05000206/LER-1982-010, Forwards LER 82-010/99X-0.Detailed Event Analysis Submitted

Forwards LER 82-010/99X-0.Detailed Event Analysis Submitted

ML20028D932
Person / Time
Site:	San Onofre
Issue date:	12/29/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20028D934	List: 05000206/LER-1982-010, Forwards LER 82-010/99X-0.Detailed Event Analysis Submitted 05000206/LER-1982-010-99, /99X-0:on 820317,three Tubes on Inlet Side of Steam Generator C Found Leaking.Caused by Intergranular Attack at Top of Tubesheet on Tube Portion of tube-sleeve Assembly.Leaking Tubes Removed from Svc by Plugging
References
82-445, NUDOCS 8301200097
Download: ML20028D932 (2)

LER-1982-010, Forwards LER 82-010/99X-0.Detailed Event Analysis Submitted

Event date:
Report date:
2061982010R00 - NRC Website

text

b f40 Southern California Eo'ison Company E

S AN ONOFRE NUCLE AR GENER ATING ST ATioN f

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P.o. s o m 12 e S A N C LEME NT E. C A LIFOR NI A 92672

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December 29, 1982

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U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention:

Mr. R. H. Engelken, Regional Administrator

Dear Sir:

Subject:

Docket No. 50-206 Follow-Up Report Licensee Event Report No.82-010 San Onofre Nuclear Generating Station, Unit 1

References:

(1) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC),

dated March 18, 1982 (2) Letter, K.P. Baskin (SCE) to D.M. Crutchfield (NRC),

dated September 21, 1982 Reference (1), describing a reportable occurrence involving three steam generator tubes, was submitted in accordance with the reporting require-ments of Section 6.9.2 of Appendix A to Provisional Operating License DPR-13. At the time of its submittal, SCE comitted to supplying the NRC a summary report on the results of the steam generator tube inspet. tion program, together with a Licensee Event Report, prior to the resumption of power operation at Unit 1.

The sumary report, containing a detailed description of the methods employed and results obtained in the steam generator tube inspection program, has been supplied under separate cover in Reference (2). Thus, with the submittal of the attached LER 82-010, SCE has now satisfied its comitments in this area.

In connection with the steam generator inspection prugram a primary-secondary differantial pressure test followed by a secondary side leakage test was conducted. The secondary side leakage test revealed a total of three (3) leaking tubes, all in the hot leg side of Steam Generator C.

At a secondary side pressure of about 800 psi, the tubes were observed to leak at the rate of two (2) drops per minute, or less. All three are previously sleeved tubes with mechanical expansion or braze-converted leak limiting seals.

8301200097 0

1em 62: 445

Mr. R. H. Eng21 ken D:cemb:r 29,1982 The leakage observed for each tube was within design specification.

However, as a conservative measure all three tubes have been plugged.

There was no effect on public health or safety as a result of this occurrence.

Please contact me should you require any additional infonnation.

Sincerely,

/ Ad b

Enclosures: 1) LER 82-010

2) " Steam Generator Inspection Program Return to Power Report, SONGS 1, Sept.1982" cc:

L. F. Miller (USNRC Resident Inspector, San Onofre Unit 1)

(w/o enclosure #2)

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement (w/o enclosure #2)

U. S. Nuclear Regulatory Commission Office of Management Information & Program Control (w/o enclosure #2)

Institute of Nuclear Power Operations (w/o enclosure #2) l l