05000311/LER-1981-077, Forwards LER 81-077/03L-0.Detailed Event Analysis Encl

Forwards LER 81-077/03L-0.Detailed Event Analysis Encl

ML20010E187
Person / Time
Site:	Salem
Issue date:	08/24/1981
From:	Midura H Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010E188	List: 05000311/LER-1981-077, Forwards LER 81-077/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-077-03, /03L-0:on 810729,Number 22 Reactor Coolant Flow Channel 2 Noted Reading Higher than Other Two Channels. Caused by Failure of Flow Transmitter 2FT-425.Transmitter Replaced & Returned to Svc
References
NUDOCS 8109030182
Download: ML20010E187 (3)

LER-1981-077, Forwards LER 81-077/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111981077R00 - NRC Website

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Mr. Boyce 11. Grier

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Dear Mr. Grier:

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LICENSE NO. DPR-75

/D DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-77/03L Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 81-77/03L.

This report is required within thirty (30) days of the occurrence.

Sincerely yours,

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11.

J.

Midura Manager -

Salem Generating Station CC:

R.

A.

Uderitz General Manager - Nuclear Production Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies)

sif, 8109030182 810824 PDR ADOCK 05000311 S

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I Report Number:

81-77/03L Report Date:

8-24-81 Occurrence Date:

7-29-81 Facility:

Salen Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 l

IDENTIFICATION OF OCCURRENCE:

Reactor Trip System Instrumentation No. 22 Reactor Coolant Flow Channel 2 - Inoperable

.l This report was initiated by Incident Report 81-295.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 65% - Unit Load 640 MWe j

DESCRIPTION OF OCCURRENCE:

On July 29, 1981, during routine channel checks the operator noticed that No. 22 reactor coolant flow channel 2 was reading higher taan the other two channels.

The channel was declared inoperable and the channel bistable was placed in the tripped condition within one hour.

Limiting condition for operation (L.C.O.)

3.3.1, table 3.3-1, action 7 was entered at 1833 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.974565e-4 months <br /> on July 29, 1981.

This occurrence constituted operation in a degraded mode in accordance with technical specification 6.9.1.9.b.

i DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Equipment failure - flow transmitter 2FT-425 had failed.

j ANALYSIS OF OCCURRENCE:

L.C.O.

3.3.1, table 3.3-1, action 7 states:

With the number of operable channels one less than the total number of channels, power operation may proceed until performance of the next required channel func-tional test provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

CORRECTIVE ACTION

Flow transmitter 2FT-425 was replaced, the channel was tested satisfac-torily and the channel was declared operable.

L.C.O.

3.3.1, table 3.3-1, action 7 was terminated at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br /> on July 30, 1981.

LER 81-77/03L.

FAILURE r;ATA:

Fisher and Porter Transmitter Model No. 10B2496PBNS lb ) d*

Prepared By J.

Varga Manager - Sa'lem Generating Station SORC Meeting No.

81-81 I