ML19317G270

LER 78-007/01T-1:on 780204,feedwater Isolation Valve FWV-15 Stroke Time Exceeded 34-s During Engineered Safety Features Actuation Sys Sensor Response Time Test SP-136.Cause Under Investigation

ML19317G270
Person / Time
Site:	Crystal River
Issue date:	02/15/1978
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19317G267	List: ML19317G266 ML19317G270
References
LER-78-007-01T, LER-78-7-1T, NUDOCS 8002280894
Download: ML19317G270 (2)

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"" EXHIBIT A LICENSEE EVENT REPORT

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, ,,,,,, as there have been no occasions requiring feedwater isolation. and redundanj i,,ii feedwater isolation valve NV-30 was verified operab la. First occurrences g o , ,, , Valve operatou renewed with operator having stroke ti:na of 27.5 seconds.

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SUPPLEMENTARY INFCFlfATION b.dport :M. 50-302/78-007/0lT-L -

2. Facility: Crystal River Unic #3 .

3. Repert Date.- 15 February 1978 I

4. Occurrence Date: 4 February 1973

5. Deternination of Cause and Corrective Action:

This event is currently undergoing careful study to deter =ine what caused the situation in which the valve operator for NV-15 was not changed as requirad by the upgrading of the steam rupture matriz. Participating in this research ara plant staff personnel, Production Engineer 1ag, the Architect Engineer, and members of the original Generation Testing team. l Inherent in the above research program is an evaminacien of the Engineering Change Notice program which was imposed during the time of the steam ruptura matrix upgrading to determine if this was an isolated case or if the program itself provided a =echanism ,

which permitted this problem. '

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In addition to the above,. the tes: program review process will be scrutinired to da-termine if the failure to identify incorrect stroke time was a result of an isolated lapse or if a programatic problem existed.

outcome of the above actions will determine whether further studies are warranted to empass other changes resultant from the upgrading of the steam rupture matrix or other fications to the plant during the test progran phase af the project.

Co=pletion of the above is anticipated by 1 May 1978.

The recent successful completion of SP-136 ES FAS sensor response ti=a test assures us that the steam ruptura matrix vill perform as required, should it be necessary.