05000321/LER-1980-069-01, /01T-0:on 800626,after Reactor Scram,Hpci Failed to Inject to Reactor Pressure Vessel Per Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Turbine Controls Being Out of Dynamic Calibr

/01T-0:on 800626,after Reactor Scram,Hpci Failed to Inject to Reactor Pressure Vessel Per Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Turbine Controls Being Out of Dynamic Calibr

ML19320C587
Person / Time
Site:	Hatch
Issue date:	07/10/1980
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19320C582	List:
References
LER-80-069-01T, LER-80-69-1T, NUDOCS 8007170419
Download: ML19320C587 (2)

LER-1980-069, /01T-0:on 800626,after Reactor Scram,Hpci Failed to Inject to Reactor Pressure Vessel Per Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Turbine Controls Being Out of Dynamic Calibr

Event date:
Report date:
3211980069R01 - NRC Website

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EVENT DESCRIPTION AND PRC9AULE CONSEQUENCES h a l2l l Following a reactor scram on June 26, 1980, IIPCI failed to inicct to the l

l RPV after receiving an auto initiation signal due to isolating on steam 013 l l l

0141 l line high dP, reportable per Tech Spec 6.9.1.8.a. The isolation was reset There were no l

and !!PCI auto initiated and controlled RPV water 1cvel.

o 151 l ADS, Core Spray l

cf fccts upon public health and safety due to this event.

o ls l l RCIC was inoperable. There was no impact on Unit l

ol7]l and LPCI were operable.

II. This is a repetitivo event, reference LER 50 -321/1980-o49.

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CAUSE

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!!PCI isolated on high steam line dP due to poor turbine speed control l

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caused *by turbine controls out of dynamic calibration. The system was l1 li l l Procedures are being l

calibrated to yield satisfactory dynamic response.

g, l ;, l l Cold quickstarts of IIPCI and l

lil3l l revised to assure proper system response.

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RCIC are scheduled.

An update report will be submitted l

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NAME OF PRFPAREll U

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NARRATIVE

REPORT Georgia Power Company.

Plant E.

I. Hatch Baxley, Georgia 31513 Reportable Occurrence Report No. 50-321/1980-0G9.

On June 26, 1980, Plant Hatch Unit I reactor scrammed from a main turbine stop valve fast closure following a turbine trip.

The llPCI 'ystem received an auto initiation signal on low reactor water level but failed to inject to the RPV_due to isolating on a steam line high dP isolation signal.

This is a failure of a system subject to limiting safety system settings to complete

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the required protective function, _ reportable per Technical Specifications 6.9.1.8.a.

The isolation was reset and when the inboard isolation valve was opened, the outboard isolation valve received another steam line high dP isolation cignal. The isolation was reset, the isolation valves opened and.HPCI auto started and injected to the RPV and was used to control water level.

ADS, Core Sptay and LPCI systems were operable.

The RCIC system was inoperable. There were no effects upon public health and safety due to this event. There was no impact on Unit II.

This is a repetitive occurrence as last reported on Reportable Occurrence Report No. 50-321/1980-049.

She isolation, due to steam line high dP, was determined to be caused by poor turbine speed control due to the turbine control system being out of dynamic calibration.

System calibration was affected over a period of time by the replacement of control system components which were statically calibrated.

System operability tests to verify pump rated flow and discharge pressure and quickstarts to verify time to rated flow did not adequately monitor the llPCI system dynamic response to auto start transients.

Following extensive testing, including manual starts and quickstarts of the HPCI system and recalibration of the llPCI turbine control sytems, the !!PCI system demonstrated satisfactory performance during hot quickstarts.

Cglibration, surveillance and operability procedures are being revised to [nclude quickstart test for both Unit I and Unit II IIPCI and RCIC systems.

In addition, performance testing procedures to monitor IIPCI and RCIC system performance are being developed and will be utilized to assure continued satisfactory system dynamic response.

Cold quickstarts of the Unit I IIPCI and RCIC systems are scheduled to be performed prior to placing the generator back on line.

An update report will be submitted following these tests.

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