05000348/LER-1978-062-01, /01T-0 on 780922:during Inspec of Class I & II Pipe Restraints/Snubbers,Noted That Main Feedwater Line Lateral Seismic Restraint FW-R49 Was Not in Place.Reason or Date of Removal Not Determined;Unit Reinstalled

/01T-0 on 780922:during Inspec of Class I & II Pipe Restraints/Snubbers,Noted That Main Feedwater Line Lateral Seismic Restraint FW-R49 Was Not in Place.Reason or Date of Removal Not Determined;Unit Reinstalled

ML20147B363
Person / Time
Site:	Farley
Issue date:	10/02/1978
From:	Hairston W ALABAMA POWER CO.
To:
Shared Package
ML20147B361	List: 05000348/LER-1978-062-01, /01T-0 on 780922:during Inspec of Class I & II Pipe Restraints/Snubbers,Noted That Main Feedwater Line Lateral Seismic Restraint FW-R49 Was Not in Place.Reason or Date of Removal Not Determined;Unit Reinstalled
References
LER-78-062-01T, LER-78-62-1T, NUDOCS 7810100086
Download: ML20147B363 (3)

LER-1978-062, /01T-0 on 780922:during Inspec of Class I & II Pipe Restraints/Snubbers,Noted That Main Feedwater Line Lateral Seismic Restraint FW-R49 Was Not in Place.Reason or Date of Removal Not Determined;Unit Reinstalled

Event date:
Report date:
3481978062R01 - NRC Website

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Rep 6rt Number:

78-62/03L Report Date:

10/3/78 Occurrence Date:

9/13/78 Facility:

Salem Generating Ptation Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

No. 12 Reactor Coolant Flow Channel 2 Inoperable CONDITIONS PRIOR TO OCCURRENCE:

Operational Mode 1, Reactor Power 100%

DESCRIPTION OF OCCURRENCE:

At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the Control Room Operator observed a loss of indication on Channel 2 Reactor Coolant Flow.

A routinely scheduled channel functional test which does not check flow indication had been satis-factorily completed at 1027 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.907735e-4 months <br />.

Performance Department was notified and Action Statement No. 7 for Technical Specification 3.3.1.1.1 was implemented.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, repairs had been completed and the channel was returned to service.

The Action Statement was terminated.

All redundant channels were available during this occurrence.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The cause of this occurrence was loss of output from the signal isolator which supplies flow indication.

The cause of the signal isolator failure is under investigation and is being followed on o.I. 752.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.3.1.1.1 Action Statement No. 7 states that with the number of operational channels one less than the total number of channels, startup and/or power operation may proceed until perform-ance of the next required channel functional test provided the operational channel is placed in the tripped condition within one hour.

No. 12 RC Flow Channel 2 was placed in the tripped condition and re-mained tripped until the channel was declared operational.

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CORRECTIVE ACTION

The failed signal isolator was replaced with a unit taken from spares.

The spare isolator was bench tested prior to installation into the protective system.

Flow indication was compared with other channels and found satisfactory.

The failed signal isolator is under investigation.

FAILURE DATA:

Signal Isolator Model 110 Manufacturer:

Westinghouse Electric Corporation Hagan/ Computer System Division Prepared by A. W.

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iosail No. 12 Reactor Coolant Flow Channel 2 was not indicating.

T/S 3.3.1.1.1; loIAllAction Statement 7 was implemented.

Performance Department placed the j t o i s ; I channel in the tripped condition and repaired.

All redundant channels 1 1o te l l were operational.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, #12 RC Flow Ch 2 was declared opera-l lo67ll tional and the Action Statement was terminated.

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