ML19331D056
| ML19331D056 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/23/1980 |
| From: | Wild P STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| References | |
| REF-PT21-80-258-002 NUDOCS 8008270190 | |
| Download: ML19331D056 (3) | |
Text
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STONE TJ YlEBSTER ENGINEERING CORPORATION 245 SuMutn SrREET. B O STON. MASSACHUSETTS AD DRE S S ALL CORRE S POND EN CE TO P.O. B OX 2.325. BOSTON. M A SS. 02107
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Mr. Victor Stello, Director July 23, 1980 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
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Dear Mr. Stello:
NOTIFICATION OF DEFECT, 10CFR21 SHOREHAM NUCLEAR POWER STATION - UNIT I LONG ISLAND LIGHTING COMPAST Stone & Webster Engineering Corporation (S&W), pursuant to the provisions of 10CFR21, hereby provides notification of a " defect" concerning the Shoreham Nuclear Power Station, Unit 1, owned by Long Island Lighting Company (LILCO) and for which S&W provided both engineering and construc-tion services.
In accordance with 'the requirements of Section 21.21(b)(3), the followini; information is submitted:
1.
Name and address of the individual informing the Commission:
Mr. P. A. Wild, Director of Engineering Stone & Vebster Engineering Corporation Post Office Box 2325 Doston, MA 02107 2.
Identification the facility, or the basic component supplied for such facilia, which contains a defect:
j Shoreham Nuclear Power Station, Unit 1 General Electric Company (GE) 4 kV switchgear circuit breaker - Snap Rings 3.
Identification of firm constructing facility or supplying basic component which contains a defect:
Basic Component supplied by GE 8008270/fd
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July 23, l930 4
Nature o_f the defect and the safety harard which could be created by such defect:
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There exists a depa *"-
-' * -' # al require ents of a procure =ent docu=ent in that breakers could have failed to cperate as specified.
The defective circuit breakers are basic cc:pe:ents in GE metal-clad switchgear (4 kV) and the switchgear has been delivered to a purchaser.
As a result of loose breaker =ain output cracks, other links in the breaker =echanis eved cut of alig=:ent and i=pacted ' the prep pin snap ring. The effect of these i= pacts def =:ed the snap ring sufficiently to allcw it to fall off the prep pin. This could result in the failure of the-breaker to operate properly.
The breakers are required tader design basis events to assure the capability to shut down the reactor and
=aintain it in a safe shutd:w cceditice. Degradatics of such essential safety-related equipment rep' resents a
=ajor reductic: in the degree cf protection provided to the public health and safety and results in a substantial safety harard.
5.
Date on dhich infor:stic of such defect was obtained:
July 23, 1930 6.
In the case of a basic co:ponent which ccatsics a defect, the number and location of all such ce=penents in use at, supplied for, or being supplied for facilities subject to the regulatica:
Shoreham Nuclear Power Statics 4 kV sdithgear circuit breakers of which 29 are used in safe'ty-related applicacica.
7.
The corrective action which has been, is being, or will be taken; name of individual or crganization respensible; and length of time taken to co=plete the action:
All 65 breakers at the Shoreham site were returned to GE for corrective work. Corrective actie censisted of cc:plete disasse=bly of.each breaker =echanis: for inspectics with replace =ent of parts as necessary.
GE factory engineering and Quality Assurance grcups have l
been apprised of this preble: to prevent recurrence.
The ide=tified corrective actica has been c epleted.
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July 23, 1980 8.
Advice related to the defect that has been given to purchasers or, liceitsees :
- p-No other actica apart frem that specified under the previous section.
Identification of this defect and the filing of this report are results of a review of 10CFR50.55(e) Reports and Licensee Event Report,s filed by S&W clients since January 6, 1978. This review, committed to.in our letter to NRC of September 6, 1979, resulted from the NRC special inspection of May 1-4, 1979. NRC has been previously advised of this problem by LILCO n:tification on November 17, 1978, in accordance with 10CFR50.55(e).
If you require any further infor=ation, please contact S. B. Jacobs at 617-973-5264.
Very truly yours, e
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~.y P. A. Wild Director of Engineering PAS:mra
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