ML20215H362

Special Rept 87-02:on 870214,turbine Trip & Reactor Scram Occurred.Caused by Loose Wire Causing Loss of Feedwater Flow Signal.Following Reduction in Reactor Pressure All Electromatic Relief Valves Reseated Properly

ML20215H362
Person / Time
Site:	Oyster Creek
Issue date:	04/09/1987
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
87-02, 87-2, NUDOCS 8704200290
Download: ML20215H362 (2)

Text

8 l GPU Nuclear Corporation NUhIQf Post Office Box 388 Route 9 South Forked River,New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

April 9,1987 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Special Report No. 87-02 Enclosed is Special Report No. 87-02 which is submitted in accordance with Technical Specification 6.9.3.

If any questions or comments should arise, please contact Mr. George Busch, Oyster Creek Licensing Engineer at (609) 971-4909.

Very truly yours, Petef B. Fiedler Vice President and Director Oyster Creek PBF:GWB:at Enclosures cc: NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 8704200290 870409 PDR ADOCK 05000219 S PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g

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0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New ~ Jersey 08731 Special Report 87-02 Report Date April 9,1987

~ Date of Occurrence The event occurred on February 14, 1987, at approximately 1301 hours0.0151 days <br />0.361 hours <br />0.00215 weeks <br />4.950305e-4 months <br />.

Identification-of Occurrance On February 14, 1987, a Turbine Trip and Reactor Scram occurred due to a loose wire causing a loss of feedwater flow signal. This event was reported in LER 87-011 dated March 20, 1987. During this event, the Electromatic Relief Valves (EMRV's) lifted to control reactor pressure. This constitutes a challenge of the relief valves as defined in the Oyster Creek Operating License and Technical Specifications, section 6.9.3.m.

Description of Occurrence The event described in LER 87-11 included a closure of the turbine stop valves due to high reactor water level. The EMRV's actuated to reduce reactor pressure due to the rapid closure of these valves. It is estimated that reactor pressure reached 1100 psig. It is assumed that all five EMRV's actuated during this event since two EMRV's are actuated at 1060 psig and the -

remaining three EMRV's are actuated at 1080 psig. The exact maximum reactor

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pressure reached during the transient could not be determined; however, the

! actions of the EMRV's, isolation condensers, and the curbine bypass valves .

indicated 1100 psig as the best estimate. This estimate is reasonable based on review of the FSAR transient analysis for a turbine trip from high reactor t water level with turbine bypass valves available. Based on the estimated

, pressure of 1100 psig, all five EMRV's would have actuated. In any event, it is known that a minimum of two EMRV's did actuate. Following the reduction in reactor pressure all EMRV's reseated properly and reactor pressure control was P established using the turbine bypass valves.

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