05000366/LER-1979-130-03, /03L-0:on 791205,during Reactor Water Level Instrument Functional Test & Calibr,Switch 2B21-NO42A Found Out of Tech Spec Limit.Caused by Instrument Drift. Instrument Calibr & Tested

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/03L-0:on 791205,during Reactor Water Level Instrument Functional Test & Calibr,Switch 2B21-NO42A Found Out of Tech Spec Limit.Caused by Instrument Drift. Instrument Calibr & Tested
ML19256G569
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/26/1979
From: Nix R
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19256G563 List:
References
LER-79-130-03L, LER-79-130-3L, NUDOCS 7912310468
Download: ML19256G569 (2)


LER-1979-130, /03L-0:on 791205,during Reactor Water Level Instrument Functional Test & Calibr,Switch 2B21-NO42A Found Out of Tech Spec Limit.Caused by Instrument Drift. Instrument Calibr & Tested
Event date:
Report date:
3661979130R03 - NRC Website

text

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7 77)

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8 60 61 DOCKET NUYBER 68 69 EVENT DATE le 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h 10121 l While performing Reactor Water Level (ADS) Instrument Functional Test and Calibration,l lo l3l l HNP-2-3251, 2B21-N042A was found to be out of Tech Specs limit. The switch actuated l

l o 14 l l at 10.2" H90 reactor level; Tech Specs limit is 312.5" H90. The switch, 2B21'-N042B, l

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There was no e f fect on l lo is l l the environs. This is a non-repetitive event for this instrument.

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The instrument l i o li li l was calibrated and a functional test was performed satisfactorily.

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NARRATIVE

REPORT Ceorgia Power Company Plant E.

I. Hatch Baxley, Georgia 31513 Reportable Occurrence Report No. 50-366/1979-130 While performing Reactor Water Level (ADS) Instrument Functional Test, 2B21-N042A level switch was found to be out of Tech Specs limit.

The switch, 2B21-N042A, actuated at 10.2" H,0 reactor level; Tech Specs limit is 212.5" H O reactor level. The switch, 2B21-N042B, in the redundant channel 4

2 was operable and within tolerance. The reactor was at 100% steady state power. The operation of the plant was not effected. There was no effect on the environs.

This was a non-repetitive event. The cause of the occurrence has been attributed to instrument drift. The instrument was calibrated and functionally tested satisfactorily.

Unit I and Unit II utilize this type of instrument, Yarway.Model 4418C, in the ADS, LPCI Permissive, Recirc Pump Trip Logic and Nuclear Steam Supply Shutoff System. These instruments do not have a generic drif t problem.

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