05000321/LER-1979-098-01, /01T-0:on 791210,HPCI Sys Not Proven Inoperable as Required by Tech Specs.Caused by Failure of Personnel to Consider Reactor Core Isolation Cooling Sys Inoperable After Trip on High Turbine Exhaust Pressure

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/01T-0:on 791210,HPCI Sys Not Proven Inoperable as Required by Tech Specs.Caused by Failure of Personnel to Consider Reactor Core Isolation Cooling Sys Inoperable After Trip on High Turbine Exhaust Pressure
ML19256G125
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/19/1979
From: Baxley S
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19256G121 List:
References
LER-79-098-01T, LER-79-98-1T, NUDOCS 7912270489
Download: ML19256G125 (3)


LER-1979-098, /01T-0:on 791210,HPCI Sys Not Proven Inoperable as Required by Tech Specs.Caused by Failure of Personnel to Consider Reactor Core Isolation Cooling Sys Inoperable After Trip on High Turbine Exhaust Pressure
Event date:
Report date:
3211979098R01 - NRC Website

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LICENSEE EVENT REPORT COmROt stoCu i I

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8 60 61 DOCK ET NuvaER tA 6J EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h IFailure to consider RCIC system inoperable af ter a trip on high turbine exhaust pres-j O

2 [sure on 12-8-79.

Therefore, the HPCI system was not proven operable as required by

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l Tech Specs 4.5.E.2.

Also, Tech Specs section 3.5.E.3 was not complied with.

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grevious event of this nature was reported on LER 50-321/1979-066.

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40 48 42 4J 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1The cause of the event was due to an oversight by operating personnel on shif t to dec-;

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_ li li l 1lare RCIC system inoperable when the system tripped on high turbine exhaust pressure.

l i 121, l The personnel involved in the occurrence were administratively relieved of their

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Georgia Power Company Plant E. I. Hatch Baxley, Georgia 31513 Cause Description and Corrective Actionscompletion of their evaluation.

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1644 329

LER #:

50-321/1979-098 Licensee:

Georgia Power Company Facility Name:

Edwin I.

Hatch Docket Number 50-321

Narrative

Report On 12-8-79, at 0940 RCIC system tripped on high turbine exhaust pressure.

The RCIC system was being used to maintain RPV water level during startup until the reactor feed pump was placed in service.

When the RCIC system tripped the RFP was placed in service and startup continued.

The licensed personnel on shift did not declare RCIC inoperable, only resct RCIC and placed in standby conditions on 12-9-79, at 1015 the RCIC system was started to demonstrate operability as required by normal surveillance as indicated by Tech Specs.

The RCIC system again tripped on high turbine exhaust pressure.

The system was declared inoperable and all requirements of Tech Specs performed.

The

cause

of the RCIC system trip was investigated and found that the manual stop check

valve, E51-F001 was closed.

The lock had broken and chain then came off handwheel, and valve vibrated closed.

The E51-F001 valve was immediately opened and the chain installed with a new lock.

Engineering is evaluating a

different type looking device for valves of this type.

The exhaust valve on HPCI Units 1 and 2 and also the exhaust valve of Unit 2 RCIC was checked to ensure they were locked in the open position.

Better type locks have been ordered and will be replacing the type Yale lock that was used on the E51-F001 valve The personnel involved in the occurrence were administratively relieved of their licensed duties and were evaluated at the completion of a training and self-study program.

They were returned to licensed duties based on their successful completion of their evaluation.

The training and self-study program included the following:

1.

Tech Specs review for LCOs 2.

Tech Specs Surveillance Requirements 3

Procedure HNP-425 4.

Procedure HNP-17 5.

Tech Specs Sections on ECCS systems 1644 330