ML19352A093
| ML19352A093 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/22/1977 |
| From: | Ross D JERSEY CENTRAL POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RO-50-219-77-5, NUDOCS 8103040384 | |
| Download: ML19352A093 (2) | |
Text
/7412 OYSTER CPIEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence *No. 50-219/77-5-3L
__ Report Date April 22, 1977 Occurrence Date March 23, 1977 Identification of Occurrence Core Spray System I parallel isolation valve V-20-15 became inoperabic in the open position when the cotor operator breaker tripped. Tnis event is considered to be a thirty-day reportabic occurrence as defined in the Technical Specifications, paragraph 6.9.2.B.2.
Conditions Prior to Occurrence The major plant paraceters at the time of the event were as follows:
Power:
Core,1410 Eft Electrical, 469 Mie Flow:
Feedwater, 5.15 x 106 lb/hr Recirculation, 14.4 x 104 gpm Stack Gas:
10,400 uci/sec Description of Occurrence On Wednesday, March 23, 1977 at approximately 1330, core spray system I parallel isolation valve became inoperab!c.
The condition occurred during performance of the routine surveillance test for core spray isolation valve actuation. Parallel isolation valve V-20-15 failed to close, after testing pressure switch RE17B, when the valve motor operator breaker tripped.
Subsequently, the valve operater motor and the breaker were checked and tested.
Following the checks and tests, parallel isolation valve V-20-15 was returned to an operabic condition.
Apparent Cause of Occurrence "Ihe valve operator motor was checked and tested and the associated circuit
. breaker was checked and bench tested. The tests and checks indicated that the motor operator and circuit breaker were functioning properly. No equip-ment failure has been indicated to date.
l 7/bsdo3T
/NM
.:e Reportable Occurrence No. 50-219/77-5-3L Page 2 April 22, 1977
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Analysis of Occurrence The safety significance of this failure is considered to be negligible. The parallel. isolation valves are designed for rated syste= flow and the alternate parallel valve was-demonstrated to be operable. !!ad the core spray systen been required at the time the valve was inoperable the system would have operated as intended.
Corrective Action The surveillance testing frequency of valve V-20-15 will be increased to weekly until the spring refueling outage at which time the valve will be included in a more extensive electrical and mechanical preventive maintenance program in an attempt to determine the actual enusc of failure.
Failure Data R0 No. 50-219/76-28-3L e
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