ML19345C409

Part 21 Rept Re S&W Installation of Synthetic Insulated Switchboard Cable Inside Containment W/O Proper Documentation,Possibly Affecting Pressurizer Power Operated Relief Valves.Originally Reported on 790817

ML19345C409
Person / Time
Site:	Beaver Valley
Issue date:	11/24/1980
From:	Wild P STONE & WEBSTER, INC.
To:	Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
REF-PT21-80-312-000 NUDOCS 8012040645
Download: ML19345C409 (4)

Text

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Mr. Victor Stello November 24, 1980 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stello:

NOTIFICATION OF DEFECT BEAVER VALLEY POWER STATION - UNIT NO. 1 DUQUESNE LIGHT COMPANY Stone & Webster Engineering Corporation (S&W), pursuant to the provisions of 10CFR21, hereby provides notification of a " defect" concerning the Beaver Valley Nuclear Power Station, Unit No. 1, owned by Dugr. cane Light Company, and for which S&W provided both engineering and construction services.

In accordance with the reporting requirements of Section 21.21(b)(3),

the following information is submitted:

1. Name and address of the individual informing the Commission:

Mr. P. A. Wild Director of Engineering Stone & Webster Engineering

• Corporation P.O. Box 2325 Boston, MA 02107

2. Identification of the facility, or the basic component supplied for such facility, which contains a defect:

Beaver Valley Nuclear Power Station - Unit No. 1

3. Identification of the firm conetructing facility or supplying basic component which contains a defect:

Stone & Webster Engineering Corporation l

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4. Nature of the defect and the safety hazard which could be created by such defect:

There exists a departure from the technical requirements of a procurement document since S&W purchased and had installed synthetic insulated switchboard (SIS) cable inside containment without requiring documentation showing environmental qualification.

The equipment affected, whereby a substantial safety hazard could be created, are the Pressurizer Power Operated Relief Valves.

The following is an analysis of the system safety implications following an~ accident and conservatively assuming failure of valves using the undocumented cable, and taking into account a single failure:

A substantial safety hazard could be created regarding the Pressurizer Power Operated Relief Valves considering failure in the open position and postulating a main steam line break because the result created would be a Loss of Coolant Accident in addition to the main steam line break. Dais constitutes degradation of the Reactor Coolant Pressure Boundary.

5. Date on which information of such defect was obtained: '

November 24, 1980

6. In the case of a basic component which contains a defect, the number and location of all such components in use at, supplied for, or being supplied for facili, ties subject to the regulation:

Beaver Valley Nuclear Power Station - Unit No. 1 Pressurizer Power Operated Relief Valves (PCV-RC-455C, 455D, and 456)

Our investigation to date has shown no defect exists on any other S&W plants. Should this status change this report will be supplemented.

7. Corrective action which has been taken; name of individual or organization responsible; and length of time to complete the action:

The undocumented cable on Beaver Valley Unit No. I has been zeplaced by DLC with qualified cable on the affected valves. l

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VS 3 S&W Electrical Guideline - XXXIII-9-2 provides assurance that acceptable, documented switchboard cable is purchased.

8. Advice related to the defect.that has been given to purchasers or licensees:

We have notified certain clients of this potential problem, where from our records it is not possible to determine whether or not qualified cable was used.

Identification of this defect and the filing of this report are results of a review of 10CFR50.55(e), Reports and Licensee Event Reports filed by S&W clients since January 6,1978. This review, committed to in our letter to the Nuclear Regulatory Co =nission (NRC) of September 6,1979, resulted from the NRC special investigation of May 1-4, 1979. NRC has been previously advised of this problem by Duquesne Light Company Licensee Event Report 79019/0lT-1 on August 17, 1979.

If you require any further information, please contact Mr. R. B. Bradbury at 617-973-0291.

Very truly yours, g- .. .

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4.b P. A. Wild Director of Engineering PAS:CT 1

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