ML19323J222
| ML19323J222 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/16/1980 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| References | |
| NUDOCS 8006190453 | |
| Download: ML19323J222 (2) | |
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m c a. f Jersey Central Power & Light Company
jif Madison Avenee at Punch Bowl Road Momstown, New Jersey 07960 (201)455-8200 June 16, 1980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Crer.k Nuclear Generating Station Docket No. 50-219 Transier'c of May 2,1979 Pursuant to section VI.B of your May 30, 1979 letter, the following information is provided.
The event on May 2, 1979 at the Oyster Creek Nuclear Generating Station occurred during routine surveillance testing of the isolation condenser initiation pressure switches when a gauge valve was opened to verify that an excess flow check valve in the instrument line was in the open position. The opening of the gange valve caused a pressure transient in the instntment line which resulted in a reactor scram on a false high pressure signal.
A modification performed on the instrument line replaced the pressure gauge with a pressure transmitter which continuously monitors the line pressure. The excess flow check valve status can now be determined by observing normal reactor pressure fluctuations without the need for opening a gauge valve.
In addition, the appropriate surveillance procedures have been reviewed to ensure that determining the excess flow check valve status does not result in the generation of spurious signals. A listing of these procedures is enclosed as Attachment A.
J 1f there are any questions regarding this information, please contact Jim Knubel, Supervisor, NSGL, 201-455-8753.
Very truly yours, N
Ivan R. Fi roc, Jr.
Vice Presi ent 1r 8006190 f fj S
Jersey Central Power & Lght Company is a Member of the Generaf Pubhc Utitties Systern
o Attachment A The following Oyster Creek Nuclear Generating Station surveillance procedures were reviewed relative to the transient of May 2,1979.
Electromatic' Relief Valve Pressure Sensor Test Isolation Condenser Isolation Test Isolation Condenser Automatic Actuation Test Core Spray Header Differential Pressure Test and Calibration Core Spray System Instrument Channel Calibration and Ter.t Core Spray Isolation Valve Actuation Test High Flow in the Main Steam Line Test and Calibration Rx Triple Low Water Level Test and Calibration Reactor Low Level Test and Calibration Reactor High Pressure Scram Test and Calibration 1
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