05000206/LER-1982-009, Forwards LER 82-009/01T-0.Detailed Event Analysis Submitted

Forwards LER 82-009/01T-0.Detailed Event Analysis Submitted

ML20054D083
Person / Time
Site:	San Onofre
Issue date:	04/16/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20054D084	List: 05000206/LER-1982-009, Forwards LER 82-009/01T-0.Detailed Event Analysis Submitted 05000206/LER-1982-009-01, /01T-0:on 820405,failed Attachment Welds on Four Feedwater Sys Pipe Supports Discovered During Scheduled Insp.Cause Undetermined.Metallurgical & Design Analysis in Progress.Failed Supports Being Replaced
References
NUDOCS 8204220322
Download: ML20054D083 (2)

LER-1982-009, Forwards LER 82-009/01T-0.Detailed Event Analysis Submitted

Event date:
Report date:
2061982009R00 - NRC Website

text

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Licensee Event Report 82-009 e6 San Onofre Nuclear Generating Station ne Attention:

Mr. R. H. Engelken, Regional Administrator

Dear Mr. Engelken:

Reference:

Letter, H. B. Ray (SCE) to R. H. Engelken (NRC), dated April 5, 1982.

The referenced letter provided prompt written notification to you of the attachment weld failures on two feedwrter system pipe supports (#1-KEG 391-1 & #1-KBG-393-1) in accordance with Technical Specification 6.9.2.a.(9).

These supports are located inside containment on feedwater lines 391-10"-EG and 393-10"-EG, respectively.

This letter is submitted as the required 14-day report.

In addition, a completed copy of Licensee Event Report No.82-009 is enclosed concerning the incicent.

As part of the initial investigation into this matter, the remaining integrally welded feedwater pipe supports inside containtrent were visually examined.

This expanded examination revealed two additional support failures.

These supports (#1-KBG-392-1 and #1-KEG-392-2) are located on feedwater line 392-10"-EG.

A seismic analysis was performed to the seismic design criteria identified in the FSAR.

Results indicated that despite the absence of the four failed supports, material yield stress in the line would not have been exceeded and structural integrity would have been maintained.

A continuing engineering evaluation has yet to confirm the exact cause of the problem.

Currently, Unit 1 is shutdown for modifications and seismic restraint of these lines is not required.

The following actions are being taken in regard to these deficiencies:

8204220322 820416

{DRADOCK 05000206 PDR y, 1E s

d R.H. Engelken 1.

A metallurgical analysis of all four supports is being performed to determine the mode of failure.

Long term action to prevent recurrence will be based on the results of this analysis.

2.

All failed supports are being replaced in accordance with ASME 8 & PV Code,Section XI, Article IWA 7000.

There was no adverse impact on Public Health or Safety as a result of these deficiencies. A final report of this matter will be forwarded by June 1, 1982.

Please contact me if additional information concerning this matter is required.

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Enclosure:

Licensee Event Report 82-009 cc:

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of Management Information & Program Control Institute of Nuclear Power Operations (INPO)

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