05000311/LER-1981-102, Forwards LER 81-102/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-102/03L-0.Detailed Event Analysis Encl
ML20031F782
Person / Time
Site: Salem 
Issue date: 10/07/1981
From: Midura H
Public Service Enterprise Group
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20031F783 List:
References
NUDOCS 8110200419
Download: ML20031F782 (3)
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LER-1981-102, Forwards LER 81-102/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3111981102R00 - NRC Website
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text

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O PSEG Putac ScMce Electric and Gas Ccmpany P O Box #168 Hancocks Bridge, New Jersey 08038 i

4 October 7, 1981

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Mr.

R. C.

Haynes

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s Director of USNRC Office of Inspection and Enforcement g7 00I] g I

OI * '2r Region 1 84 631 Park Avenue MID'**. 2/

King of Prussia, Pennsylvania 19406 t

Dear Mr. Haynes:

w LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-102/03L 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 81-102/03L.

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

Sincerely yours, l

f lif.

- s~

H. J. Midura General Manager -

Salem Operations CC:

R. A.

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

Director, Office of Management Information and Program Control 4

(3 copies)

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r Report Number:

81-102/03L Report Date:

10-7-81 Occurrence Date:

9-15-81 Facility:

Salem Generating Station, Unit 2 Public Service Electric & Cas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

No. 22 Reactor Coolant Pump Flow Channel 2 - Inoperable.

This report was initiated by incident report 81-376.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 94% - Unit Load 1040 MWe DESCRIPTION OF OCCURRENCE:

On September 15, 1981 the control room operator noticed a low reading on No. 22 Reactor Coolant Pump Flow Channel 2.

The channel was declared inoperable at 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br /> and action statement 3.3.1 action 7 was entered.

This occurrence constituted operation in a degraded mode in accordance with technical specification 6.9.1 9.b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The cause of the low flow indication was failure of the flow transmitter and equalizing valve assembly.

ANALYSIS OF OCCURRENCE:

Technical specification 3.3.1 action 7 requires:

With the. number of operable channels one less~than the total number of channels, startup and/or power:. operation may proc 2ed until performance of the next required channel functional 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 />.

C.RRECTIVE' ACTION:

The channel was 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 />.

The flow transmitter and equalizing valve assembly were replaced.

and calibrated satisfactorily.

The No. 22 Reactor Coolant Loop Flow Channel 2 was tested satisfactorily and declared operable.

At 1846 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.02403e-4 months <br />, September 16, 1981 action statement 3.3.1 action 7 was terminated.

i

e LER 81-102/03L

  • FAILURE DATA:

Fischer and Porter Co.

Differential Pressure Flow Transmitter Model 10B2496 Kerotest Manufacturing Corp.

Equalizing Valve Assembly Model 3/8 - X58M Prepared By F.

Dickey

/'

L

N Manager - Salem Generating Station SORC Meeting No.81-102 e

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