05000321/LER-1979-008-03, /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure

/03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure

ML19261B338
Person / Time
Site:	Hatch
Issue date:	02/07/1979
From:	Baxley S GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19261B335	List: 05000321/LER-1979-008, Forwards LER 79-008/03L-0 05000321/LER-1979-008-03, /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure
References
LER-79-008-03L-01, LER-79-8-3L-1, NUDOCS 7902150343
Download: ML19261B338 (2)

LER-1979-008, /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure

Event date:
Report date:
3211979008R03 - NRC Website

text

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60 61 DOCKET NuvaER Ld 69 EVENT DATE 14 25 REPOHT DATE 8J EVENT DESCHIPTION AND pro 9 ACLE CONSECUENCES h

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2 l Reactor maximum cooldown rate of 100 degrees F per hour was exceeded on Jan 21, 1979 i

ldue to injection of condensate feedwater into reactor vessel during cooldown. The 3

3 314ll moderator temperature was being reduced to bring recirc loop temperatures within 50 l

i egrees F limit for startup Idle recirc loop. Pressure was allowed to decrease below l l

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s condensate booster pump pressure and allowed condensate feedwater to be injected intc j i

l reactor vessel. This resulted in a cooldown rate of 103 degrees F Per hour in a one j

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i ois l hour period in the A recirc loop.

Condensate booster pump was tripped and (con't)

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4 Georgia Power Company Edwin I. Hatch Plant Baxley, Georgia 31513 Event Description and Probable Consequences (cen't) feedwater valves isolated to stop injection to vessel. Recirc icop A temperatures were back within limits within 15 minutes. There were no personnel injuried or overexposured or any release of radioactive materials te the environs as a result of this occurence.

Cause Description and Corrective Actions (con't) a system pressure that could inject cold feedwater into vessel during reactor cooldown and to observe pressure decrease and level increase ve.'y closely during this type pf operation.

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