05000366/LER-1981-029-03, /03L-0:on 810408,during 100% Power,Rcic Inboard Steam Supply Isolation Valve Could Not Be Reopened After Closing on Isolation Signal.Caused by Excessive Activation & Tripped Breaker.Breaker Reset & Valve Tested

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/03L-0:on 810408,during 100% Power,Rcic Inboard Steam Supply Isolation Valve Could Not Be Reopened After Closing on Isolation Signal.Caused by Excessive Activation & Tripped Breaker.Breaker Reset & Valve Tested
ML20008F971
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/05/1981
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20008F965 List:
References
LER-81-029-03L, LER-81-29-3L, NUDOCS 8105120412
Download: ML20008F971 (2)


LER-1981-029, /03L-0:on 810408,during 100% Power,Rcic Inboard Steam Supply Isolation Valve Could Not Be Reopened After Closing on Isolation Signal.Caused by Excessive Activation & Tripped Breaker.Breaker Reset & Valve Tested
Event date:
Report date:
3661981029R03 - NRC Website

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o.i loisilis r e p_ ort _a b l e u n d e r T e c h S p e c s 6. 9.1. 9. B.

As per Tech Spe_cs 3/4.7.3.2 i

O c lHPcl system was operable. and no__significant event occurred.

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50-366/1981-029 Licensen:

Georgia Power Company Facility Namc:

.Edwin I. llatch Docket #:

50-366

Narrative

Report for LER 50-366/1981-029 On 4-8-81, at 13:00 and with Unit 2 at 100% thermal power the monthly test (functional test part) of IlNP-2-3410, RCIC Steam Line Delta Pressure Instrument FTSC, was being performed.

.As per the procedure the RCIC inboard steam ' supply valve, 2E51-F007, was closed on an isolation trip signal.

The isolation trip signal was reset, and the valve control switch was actu-ated a number of times in rapid succession to open the valve.

This resulted in an apparent overcurrent situation for the M0V, and this tripped the breaker and overload blocks for the MOV.

The breaker and overload blocks were

reset, and the valve was successfully tested for operability.

RCIC was declared operable upon completion of the test.

' Operating personnel have been reminded that valves of this type are subject to failure if excessive duty cycles are imposed.

As per Tech Specs 3/4.7.3.2 HPCI was operabic with current surveillance requirements complete and satisfactory during this period of RCIC inoperability.

No significant event occurred.

The unit is now in full compliance with the requirements of Tech Specs, and no further renorting is required.

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