05000272/LER-1981-081, Forwards LER 81-081/03L-0.Detailed Event Analysis Encl

Forwards LER 81-081/03L-0.Detailed Event Analysis Encl

ML20049A838
Person / Time
Site:	Salem
Issue date:	09/23/1981
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20049A839	List: 05000272/LER-1981-081, Forwards LER 81-081/03L-0.Detailed Event Analysis Encl 05000272/LER-1981-081-03, /03L-0:on 810827,individual Rod Position Indicators for Control Rods 2A1,1SC1,1C2,1D4 & 2D2 Were in Disagreement W/Demand Position Indicators.Indicators Recalibr & 1SC1 Circuit Card Replaced
References
NUDOCS 8110020326
Download: ML20049A838 (3)

LER-1981-081, Forwards LER 81-081/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2721981081R00 - NRC Website

text

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O PSIEG Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 23, 1981 Mr.

R. C. Haynes i (h ;&

Director of USNRC

((' 0072 Office of Inspection and Enforcement u,

JgOIA *Sl Region 1 S

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631 Park Avenue King of Prussia, Pennsylvania 19406 O

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Dear Mr. Haynes:

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..F LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-81/03L Pursuant to the requirements of Salem Generating Station Unit No.

1, Technical Specifications, Section 6.9.1.9 b, we'are submitting Licensee Event Report for Reportable Occurrence 81-81/03L.

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

Sincerely yours, ll..5 y

H.

J. Midura Manager - Salem Generating Station s

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)

(I 8110020326 G10923 PDR ADOCK 05000272 S

PDR The Energy People 9s 2189 02.sw iiso

1 Report Number:-

81-81/03L Report Date:

9-23-81 j

Occurrence Date:

8-27-81, 9-3-81, 9-9-81, 9-15-81 and 9-18-81 Facility:

Salem Generating Station, Unit 1 Public Service Electric & Gas _ Company Hancocks' Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Individual Rod Position Indications - 2Al, 1SC1, 1C2, 1D4 and 2D2 - Inoperable.

This report was initiated by Incident Reports81-346, 81-361,81-370, 81-375 and 81-384.

CONDITIONS PRIOR TO OCCURRENCE:

8-27-81 Mode 1 - Rx Power 97% - Unit Load 1030 MWe 9-03-81 Mode 1 - Rx Power 96% - Unit Load 990 MWe 9-09-81 Mode 1 - Rx Power 96% - Unit Load 1000 MWe 9-15-81 Mode 1 - Rx Power 91% - Unit Load 1010 MWe 9-18-81 Mode 1 - Rx Power 86% - Unit Load 870 MWe DESCRIPTION OF OCCURRENCE:

On five separate occasions, August 27 and' September 3, 9, 15 and 18, 1981, 1

the control operator noticed that individual rod position indicators (IRPI) for control rods 2A1, 1SCl, 1C2, 1D4 and 2D2, respectively, were-in disagreement with the demand position indicators bf greater than 12 steps.

The IRPIs were declared inoperable at 1845, 0910,.

0730, 0907 and 2240 hcurs, respectively, and action statement 3.1.3.2.a was entered.

These ocenrrences constituted operation in a_ degraded mode in accordance j

with technical specification 6.9.1.9.b.

i DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

l The causes of the IRPIs being in disagreement with the demand position j

indicators by greater than 12 steps are as follows:

2Al and 1C2 - These rods were verified at 228 steps by a series of. flux traces even though the indi -

i cators indicated a lower position.

i 1SCl - A malfunction in tha P-250 computer was loading.

l down the signal co-

,ning module.

1 I

1D4 - The signal conditioning module'and IRPI had drifted out of calibration.

2D2 - The'IRPI had drifted out of calibration.

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ANALYSIS OF OCCURRENCE:

Technical specification 3.1.3.2.a requires:

With a maximum of one rod position indicator channel per group inoperable either:

1.

Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per eight hours and immediately after any motion of the non-indicating rod which exceeds 24 steps in ene direction since the last determination of the rod's position, or 2.

Reduce thermal power to < 50% of rated thermal power within eight hours.

CORRECTIVE ACTION

The corrective actions were as follows:

2Al and 1C2 - The signal conditioning module was recalibrated utilizing new input data to indicate 228 steps.

1SC1 - Circuit card serial No. 348 was replaced in.the P-250 computer.

1D4 - The signal conditioning module and IRPI were recalibrated.

2D2 - The IRPI was recalibrated.

The IRPIs and other affected units for all five control rods were tested satisfactorily and returned to service.

At 2240, 1115, 2000, 1150 and 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br /> on September 1, 3, 9, 15 and 18, 1981, respective to the occurrence dates, action statement 3.1.3.2.a was terminated.

FAILURE DATA:

Bailey Instrument Co., Inc.

Bailey Edgewise Indicator Model RY2 M&gnetics, Inc.

Signal Conditioning Module Type E2786 Westinghouse Electric Corporation P-250 Computer Circuit Card No. 348 Prepared By F.

Dickey

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- f.-

Managdr - Salem Generating Station SOPC Meeting No.

81-95