05000366/LER-1980-035-03, /03L-0:on 800321,during Calibr Procedure HNP-2-5329,all But Six Accumulator Pressure Switches Found to Be Outside Tech Specs.Caused by Personnel Error & Component Failure.Pressure Switches Recalibr

/03L-0:on 800321,during Calibr Procedure HNP-2-5329,all But Six Accumulator Pressure Switches Found to Be Outside Tech Specs.Caused by Personnel Error & Component Failure.Pressure Switches Recalibr

ML19309E643
Person / Time
Site:	Hatch
Issue date:	04/17/1980
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19309E632	List: 05000366/LER-1980-035, Forwards LER 80-035/03L-0 05000366/LER-1980-035-03, /03L-0:on 800321,during Calibr Procedure HNP-2-5329,all But Six Accumulator Pressure Switches Found to Be Outside Tech Specs.Caused by Personnel Error & Component Failure.Pressure Switches Recalibr
References
LER-80-035-03L, LER-80-35-3L, NUDOCS 8004220735
Download: ML19309E643 (2)

LER-1980-035, /03L-0:on 800321,during Calibr Procedure HNP-2-5329,all But Six Accumulator Pressure Switches Found to Be Outside Tech Specs.Caused by Personnel Error & Component Failure.Pressure Switches Recalibr

Event date:
Report date:
3661980035R03 - NRC Website

text

UCENSEE EVENT REPORT 6

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60 61 DOCKET NUMBER 68 63 EVENT DATE 74 75 REPOR T DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10 121 l Durina the nerfdrmance of the CRD HCU Pressure Indicator and Switch Cali-1 o 3 l bration procedure, HNP-2-5329, all but six of the accumulator pressure I

l o 14 l l switches were found to be outside the Tech Spec limit of 955 ! 15 psig.

I lo Isl l In addition, two leak detector switches were found inoperative. There I

lo is I l was no effect upon the health and safety of the public.

This is a non-I 10171 l repetitive event.

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NARRATIVE

REPORT Georgia Power Comapny Plant E. I. Hatch

.Baxley, Georgia $1513 Reportable Occurrence Report No. 50-366/1980-035.

While performing the CR0 HCU. Pressure Indicator and Switch Calibration, it was discovered that all but six of the 137 accumulator pressure switches were outside the Tech Spec limit of 955 ! 15 psig.

In addition, two leak detector switches were found to be inoperative. The reactor was in the cold shutdown condition. The health and safety of the public was not affected.

The operation of the plant was not affected.

The cause of the event was attributed to procedu're inadequacy and component failure. The accumulator pressure switches were intially calibrated for the pre-op purposes with a water medium rather than nitrogen.

The water apparently trapped air or nitrogen in the pressure switch piping causing the calibration to be inenrrect. There was not a written procedure with initial calibration (proper way to calibrate these instruments during the instructions for the performed for pre-op pursposes).

Procedure HNP-2-5329 has been written since and does require the use of nitrogen as the calibration medium. The accumulator pressure switches were recalibrated and returned to service. The leak detection switches were replaced and successfully tested.

One pressure switch was found to acutate at 650 psig and three switches were found at 830 psig. The remainder of the 137 switches actuated anywhere from 860 to 960 psig. The control rods would have functioned properly for all reactor pressures due te the inherent design which allows reactor pressure to assist in the injection of the control rods into the core.

The reactor would have been shutdown safely from any reactor pressure.

A random sample of 14 accumulator pressure switches (10%) will be tested in three to six months to insure the switch setpoints are staying within the Tech Spec limit.

No generic problems have been discovered at this point.

This event is not repetitive.

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