05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift

/01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift

ML19296A731
Person / Time
Site:	Hatch
Issue date:	02/05/1980
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19296A721	List: 05000366/LER-1980-007, Forwards LER 80-007/01T-0 05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift
References
LER-80-007-01T, LER-80-7-1T, NUDOCS 8002150344
Download: ML19296A731 (3)

LER-1980-007, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift

Event date:
Report date:
3661980007R01 - NRC Website

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reached 2.08 psia. rhis is not a repetitive event, however instrument drift for (cont)l o

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i o j The cause of the f ailure of these instruments was attributed to instrument drift.

l The Instruments ucre recalibrated per IDIP-2-5240, Static-0-Ring Pressure Switch li ;i; [

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, l Calibration, and returned to service.

HNP-2-3002, High Drywell Pressure Instrument ;

ij3j l Functional Test and Calibration was again performed with satisfactory results.

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Event Description and Probable Consequences (cont) these irstruments was Jast reported on Reportabic Occurrence 2-79-108, dated September 26, 1979.

Public health and sofety was not ef fected by this event.

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e NARRATIVC REPORT Georgia Power Company Plant E.

I. Itacch Baxley, Georgia 31513 Reportabic Occurrence Report No. 50-366/1980-007.

l With the reactor mode suitch in run, and while performing IINP-2-3002, Iligh Drywell Pressure Instrument (Reactor Protection System) Fu:ictional Test and Calibration, technicians found that pressure switches 2C71-N002A, B, and D i

exceeded Tech. Spec. acceptance criteria. Logic channel "A" was still operabic j

below the 2 psig Tech. Spec. limit (2C71-N002C) but logic channel "B" could not have actuated until achieving a pressure of 2.08 psig.

Therefore a reactor scram would not have occurred until the pressure in the Drywell reached 2.08 psig.

The health and safety of the general public was not effected. Calibration

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procedure HNP-2-5240, Stetic-0-Ring Precsure Switch Calibration, was performed I

on the switches that were out of tolerance and HNP-2-3002 was performed again 4

with satisf actory results.

Instrument drift has occurred on these instruments

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before and was reported on Reportable Occurrence 2-79-108, dated September 26, 1979.

Unit I utili;:es the same type switches,- however the switches were tested per itNP-1--3002 and founc], acceptable on January 25, 1980.

IINP-1-3002 and liNP-2-3002, liigh Drywell Pressure Instrument (Reactor Protection System) Functional Test and Calibration, are performed monthly.

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