ML19261A802

LER 79-005/01T-0 on 790123:facility Notified That During Accidents Such as double-ended Pipe Rupture,Rockwell Mfg Co Main Steam Isolation Valve May Not Close in Specified Time of 5-s Due to Forces on Valve Disc

ML19261A802
Person / Time
Site:	Crystal River
Issue date:	01/30/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19261A803	List: ML19261A802 ML19261A805
References
LER-79-005-01T, LER-79-5-1T, NUDOCS 7902080186
Download: ML19261A802 (2)

Text

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NRC FORM ;66 U. 5 NUCLE A A A EGULATORY COM*AIS34CN

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(PLEASE PRINT OR TyFE ALL RECutRED INFORMATICN)

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SUPPLEMENTARY INF0FMATION Report No.: 50-302/ 79-005 /0lT-0 Facility: Crystal River Unit #3 Report Date: 30 January 1979 Occurrence Date: 23 January 1979 Identification of Occurrence:

Indeterminate response time for Main Steam Isolation Valves during accident conditions reported under the provisions of Technical Specification 6.9.1.8.1.

Conditions Prior to Occurrence:

Mode 1 power operation (100%)

Description of Occurrence:

At 1500, CR-3 was notified that Rockwell Manufacturing Co. advised Florida Power Corporation that the four Main Steam Isolation Valves MSIV-411, 412, 413, and 414, during accident conditions and especial-ly a double ended pipe rupture, may not close within the design specified time frame of five (5) seconds at specified design cceditions. It is Rockwell's belief, however, that the valves will function within customer specifications during normal opera *tng conditions.

Designation of Apparent Cause:

Functional tests performed by Rockwell Manufacturing Co, since the initial purchase by Florida Power Corporation, revealed the presence of additional forces on the valve disc not previously analyzed or considered. Rockwell believes that these forces may prevent valve closure within the five (5) second time specifica-tion.

Analysis of Occurrence:

No hazard to the health and safety of the plant or general public as the use of Main Steam Isolation Valves was not considered in the Steam Line Failure analysis of the Final Safety Analysis Report.

Corrective Action:

Corrective actions are presently being formulated. Upon final determination of corrective actions, a revision to this report will be submitted.

Failure Data:

Four occurrences previously reported. First occurrence of an event of thi type.

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