05000366/LER-1980-086-03, /03L-0:on 800523,during Power Increase,Psw Flow Was Throttled to Reduce Dilution Flow,Reducing Cooling Capacity.Dw Temp Exceeded Specs.Caused by Operator Throttling Svc Water Flow Through Plant

/03L-0:on 800523,during Power Increase,Psw Flow Was Throttled to Reduce Dilution Flow,Reducing Cooling Capacity.Dw Temp Exceeded Specs.Caused by Operator Throttling Svc Water Flow Through Plant

ML19324A077
Person / Time
Site:	Hatch
Issue date:	06/10/1980
From:	Baxley S GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19324A073	List: 05000366/LER-1980-086, Forwards LER 80-086/03L-0 05000366/LER-1980-086-03, /03L-0:on 800523,during Power Increase,Psw Flow Was Throttled to Reduce Dilution Flow,Reducing Cooling Capacity.Dw Temp Exceeded Specs.Caused by Operator Throttling Svc Water Flow Through Plant
References
LER-80-086-03L, LER-80-86-3L, NUDOCS 8006200444
Download: ML19324A077 (2)

LER-1980-086, /03L-0:on 800523,during Power Increase,Psw Flow Was Throttled to Reduce Dilution Flow,Reducing Cooling Capacity.Dw Temp Exceeded Specs.Caused by Operator Throttling Svc Water Flow Through Plant

Event date:
Report date:
3661980086R03 - NRC Website

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S 60 61 DOC r. E T N U'.'d E H 1A 63 EVENT DATE 74 7b REPOHT DATE 80 F. VENT DESCRIPTION AND PROBABLE CONSEGUENCES O'o g lDuring a power increase, at 1750 MWT, P.S.W.

flow was throttled to re-I g, duce dillution flow.

The Reactor Building Chiller tripped reducing the I g ; cooling capacity to the D.W. coolers.

The average D.W.

temp. exceeded I

g,145 degrees F. violating Tech. Specs.

3.6.1.7.

There were no effects I

g gupon public health and safety due to this event.

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NARRATIVE

REPORT Reportable Occurrence Report No. 50-366/1980-086 During a power increase, the P.S.W. plant outlet valves 2M71-E012 (make-up to the circulating water flume) and 2N71-F013 (direct dis-charge to the river) were being realigned to make-up to the flume after a previous alignment for Radwaste dillution flow discharge.

During the realignment to flume make-up, the two outlet valves were inadvertantly throttled partially closed simultaneously reducing the total P.S.W.

flow.

The Reactor Building chiller compressor head pressure increased to the point of a trip due to the lack of cooling.

Upon investigation of chiller operation, it was determined that there wasn't enough P.S.W.

flow to the eniller.

The flume make-up isolation was opened fully and the chiller was restarted and D.W. temperature was returned to < 145 F. within 15 minutes.

Operators have been instructed to insure that one of the outlet valves are full open before closing or adjusti'ng the opposite out-let valve.

This event is not a reoccurring problem and is not applicable to the other unit.

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