ML19317G263

LER 78-007/01T-0:on 780204,feedwater Isolation Valve FWV-15 Stroke Time Exceeded 34-s During Testing.Caused by Valve Operator w/89-s Closure Time on FWV-15.Operator Renewed

ML19317G263
Person / Time
Site:	Crystal River
Issue date:	02/06/1978
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19317G252	List: ML19317G251 ML19317G263
References
LER-78-007-01T, LER-78-7-1T, NUDOCS 8002280888
Download: ML19317G263 (2)

Text

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- SUPPLD'ENTARY INFORMATION 1 ort No. 50-302/78-007/01T-0

2. ceility: Crystal River Unit #3

3. Report Date: 6 February 1978

4. Occurrence Date: 4 February 1978

5. Identification of Occurrence:

The engineered safety feature response ti:ne for feedwater isolution valve WV-15 was greater than 34 seconds contrary to Technical Specification 3.3.2.1, Table 3.3-5.

6. Conditions Prior to Occurrence:

Mode 3 hot standby operation.

7. Description of Occurrence:

At 0400 during the perfor: nance of SP-136, engineered safeguards actuation systems -

sensor response ti:na test, it was de*:er:nined that feedwater isolation valve WV-15 1 stroke ti:na was greater than the required 34 seconds. The stroke time was 89 seconds. -

The valve was immediately closed (ES actuation position). The valve operator was renewed with the correct model operator under Work Request #0-6141 and verified operable, (with a 27.5 seconds stroke time) prior to removing the "B" feedwater train from isolation.

8.n Vsignation of Apparent Cause:

The cause of this event was the original installation of a valve operator with 89 second closure time on WV-15. Subsequent to original installation, the steam rupture matrix was incorporated into the ES actuation scheme with stroke time re-quirement of NV-14 and 15 changed to less than 34 seconds. The valve operator for NV-15 was not changed.

9. Analysis of Occurrence:

During plant operation to date, there has been no occasion requiring feedwater isolatic Therefore, isolationthe safet}0 valve was verified operableimplications of this occurrence were minimalas redundant feed NV-10 . Corrective Action:

The successful ecmpletion of testing of the complete Steam Rupture Matrix Surveillance Procedure assures that this occurrence was an isolated instance. Recurrence is therefere precluiad.

11. Failure Data:

This is the fiest cccurrence of this type of event.

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