ML20116D878

Interim Deficiency Rept Re Performance of Ruskin Mfg Co Spring Closure Fire Dampers.Initially Reported on 841224. Specific sys/damper-related Fixes Will Be Developed.Next Rept Will Be Submitted by 850701

ML20116D878
Person / Time
Site:	Hope Creek
Issue date:	04/01/1985
From:	Martin T Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8504300084
Download: ML20116D878 (2)

Text

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w 4 m Public Service Electric and Gas Company Thomas J. Martin 80 Park Plata, Newark, NJ 07101 201-430-8316 Mailing Address: P.O. Box 570, Newark, NJ 07101 Wm Praident Er:gineering and Construction April 1, 1985 Dr. Thomas E.-Murley, Administrator ,

U. S. Nuclear Regulatory Commission 4 Office of Inspection and Enforcement Region I 631 Park Avenue

- King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

SIGNIFICANT CONSTRUCTION DEFICIENCY RUSKIN FIRE DAMPERS MODEL 1BD-23 HOPE CREEK GENERATING STATION On December 24, 1984, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. H.

Kister, advising of a potentially significant construction deficiency concerning the performance of spring closure fire dampers supplied by Ruskin Manufacturing Company. On January 25, 1985, an interim report was sent to your office.

The following interim report is provided in accordance with 10CFR50.55(e).

Our Architect / Engineer and Constructor, Bechtel has evaluated a total of 694 fire dampers for applicability of the subject concern. These dampers were purchased variously as Q (for seismic. considerations), non-Q or F listed. Of these, some 221 dampers will require further analysis / potential rework.

Two (2) solutions that are presently qualified for use by test data are heavier springs and modified latching mechanisms.

Other solutions that suggest themselves will' require qualification testing. .

To assist us in our evaluation, Ruskin is developing a formula suitable for interpolating known tent results into a matrix format that will provide acceptance criteria for the Hope Creek damper sizes and configurations. When this information becomes available, we will" develop specific system / damper related fixes.

M h h 354-PDR l

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Dr. T. E. Murley 2 4/1/85 We anticipate providing you with an update report of our progress in the resolution of this problem by July 1, 1985.

Very truly yours, ,

t 3

C Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C. 20555 NRC Resident Inspector - Hope Creek P. O. Box 241 IIancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, GA 30339 i 1 I