ML20248G251

Part 21 Rept Re Defect in Two Safety Relief Valves for Core Spray Sys Supplied by Lonergan.Relief Valves Ordered & Received for Installation & Two Valves Lifted Prematurely Removed from Sys & Sent to Offsite Test Facility

ML20248G251
Person / Time
Site:	Oyster Creek
Issue date:	04/04/1989
From:	Phyllis Clark GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-89-060-000 PT21-89-060-000, PT21-89-60, NUDOCS 8904130351
Download: ML20248G251 (4)

Text

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GPU Nuclear Corporation arsippany, Ne Je sey 07054 201-316-7000 TELEX 136-482-Writer's Direct Dial Number:

April a,1989 Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Notification under 10 CFR 21 l Pursuant to 10 CFR 21.21(b)(1), GPU Nuclear is submitting this letter to notify the USNRC that a basic component containing a defect was received at the Oyster Creek Nuclear Generating Station and subsequently installed in a safety-related system.

Attachment 1 to to this letter contains the information specified in 10 CFR 21.21(3). If any further information is required, please contact ,

Mr. John Rogers at (609) 971-4893.

Very truly yours, P. R. Clark President, G;U Nuclear 1

PRC/JJR/crb 0920A:20 Att.

8904130351 890404

{DR ADOCK 05000219 PDC

[N GPU Nuclear Corporation is a subs.J~" d na- ral Public Unities Corporation l a

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cc: Director, Office of Nuclear Reactor Regulation (2 additional copies)

Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/II Washington, DC 20555 Mr. William T. Russell, Administrator Reaion I U.'S . Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 1 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 Lonergan, Valve Division P.O. Box 2360 Fort Wayne, Indiana 46801-2360 I

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ATTACHMENT I The following information is submitted under 10CFR21.21(3):

(i) Name and address of the individual or individuals informing the -

Commission.

Philip R. Clark, President GPU Nuclear Corporation 1 Upper Pond Road Parsippany, N.J. 07054 (11) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the '

United States which fails to comply or contains a defect.

Dyster Creek Nuclear Generating Station Docket No. 50-219 License No OPR-16 P.O. Box 388 forked River, N.J. 08721 .q 1

(iii) Identification of the firm constructing the facility or supplying-The basic component which fails to comply or contains a defect -l Lonergan, Valve Division P.O. Box 2360 Fort Wayne, Indiana 46801-2360 (iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply Two safety relief valves for the Core Spray system, procured under 10CFR50 Appendix B criteria, were received with a defect and installed in a safety-related system. The procurement specification stated the relief point to be 350 psig + 2%. During operability testing for acceptance, one valve relieve 3 at approximately -6.0% and the second at approximately -14.8%. The safety hazard is twofold. A premature relief valve lift decreases pump discharge pressure, thereby increasing the time until water will be injected into the core. Also, the volume of water being relieved is precluded from injection to the core, thereby

/ecreasing cooling capability.

(v) The date on which the information of such defect was or failure to comply was obtained As required by Corporate Procedure 1000-ADM-1290.01, "NRC Regulation 10-CFR-21 (Reporting of Defects and Noncompliance", the Responsible Officer of GPU Huclear was notified on April 4.19R9 .

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i (vi) In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part. j Two relief valves were ordered and received for installation in the '

Core Spray Systems, one each. The valve tag numbers are V-20-24 and V-20-25.

(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action. '

The two valves which had lif ted prematurely were removed from the systems and sent to an off-site test facility. As found data were recorded and the valves disassembled to determine root cause. The valves were then re-assembled and retested, satisfactorily. The valves were re-certified and returned to GPU Nuclear as warehouse spares. <

(viii) Any advice related to the defect or failure to comply about the facility activity or basic component that has been, is being, or will be given to purchasers or licensees.

The vendor has informed GPU Nuclear that the decrease in set point was a relaxation of residual spring stresses after the production setting of the valve. The vendor further states that this has not been a problem with this series of valves or springs in the past.

Any further advice would need to be supplied by the vendor.

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