ML20128G463

Submits Outline of Findings of Visual Insp of Drywell Cables & Equipment to Be Performed 9 Months After Restart, in Response to Insp Repts 50-373/83-50 & 50-374/83-53.No Heat Damage Found

ML20128G463
Person / Time
Site:	LaSalle
Issue date:	01/09/1985
From:	John Marshall COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
9596N, NUDOCS 8507090197
Download: ML20128G463 (2)

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[\ Commonwealth Edison

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Chicago, Illinois 60690 January 9, 1985 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

LaSalle County Station Unit 1 Report on Nine Month Cable Inspection on Drywell Temperatures NRC Docket No. 50-373 Referen letter to Co e'ed

" - t c-4. 'la n u a ry 13, 1984, Re_s M o Ins n Report Nos. 30-373/83-50 and 50-374/83- .

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Dear Mr. Keppler:

The reference listed above requested that a report be submitted outlining the findings of the visual inspection of the Unit 1 drywell cables and equipment which was to be performed approximately nine months after the Unit 1 restart in January 1984.

The purpose of this letter is to fulfill that request per the following:

A. Basis for Drywell Cable Inspections The basis of the nine month inspection was to examine those cables and equipment which had been deemed affected by high temperatures in the Unit 1 Drywell prior to November 1983.

The visual inspection for the cables therefore examined most of the cables which had been replaced prior to Unit 1 restart in January of 1984.

Those cables which were replaced were inspected only at available locations above the 777 foot elevation.

The inspection of the drywell snubbers was performed under the requirements of the Technical Specification surveillance program.

8507090197 85010933 DR ADOCK 050 f 6dl

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JAN 111985

,7 f' J. G. Keppler January 9, 1985 B. Findings of Visual Inspection:

All Safety Related cables inspected above the 777 foot elevation were examined in at least two different locations and showed no visible degradation of the cable insulation.

From the sampling of non-safety related cables no cables showed evidence of heat induced degradation of the insulation.

All the snubbers which were listed in the December 22, 1983 letter to the Region III Headquarters as being replaced, were visually inspected and found to be in a satisfactory condition.

C. Conclusion The snubbers, Safety Related and Non-Safety Related cables inspected do not show heat damage. The drywell temperature data continues to show good results of substantially reducted upper level drywell temperatures indicating the interim HVAC modifica-tion is effective.

Very truly yours,

)$ 'WI J. G. Marshall Nuclear Licensing Administrator 1m cc: NRC Resident Inspector - LSCS A. Bournia - NRR 9596N