05000333/LER-1980-031-03, /03L-0:on 800405,drywell to Torus Differential Pressure Did Not Meet 1.75 Psi Requirement of Tech Spec. Caused by Rapid Temp Decrease in Sys Cooling Drywell.Reactor Bldg Cooling Water Temp Restored

/03L-0:on 800405,drywell to Torus Differential Pressure Did Not Meet 1.75 Psi Requirement of Tech Spec. Caused by Rapid Temp Decrease in Sys Cooling Drywell.Reactor Bldg Cooling Water Temp Restored

ML19309H119
Person / Time
Site:	FitzPatrick
Issue date:	05/01/1980
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19309H113	List: 05000333/LER-1980-031, Forwards LER 80-031/03L-0 05000333/LER-1980-031-03, /03L-0:on 800405,drywell to Torus Differential Pressure Did Not Meet 1.75 Psi Requirement of Tech Spec. Caused by Rapid Temp Decrease in Sys Cooling Drywell.Reactor Bldg Cooling Water Temp Restored
References
LER-80-031-03L, LER-80-31-3L, NUDOCS 8005080458
Download: ML19309H119 (2)

LER-1980-031, /03L-0:on 800405,drywell to Torus Differential Pressure Did Not Meet 1.75 Psi Requirement of Tech Spec. Caused by Rapid Temp Decrease in Sys Cooling Drywell.Reactor Bldg Cooling Water Temp Restored

Event date:
Report date:
3331980031R03 - NRC Website

text

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8 60 61 DOCKET NUMBER EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES h 1012l lDrywell to torus differential pressure did not meet the 1.7 psi recuirement of l

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a POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FlTZPATRICK NUCLEAR POWER PLANT DOCKET NO.50-333 ATTACHMENT TO LER 80-031/03L-0 Page 1 of I

During normal operation, the Drywell to Torus Differential Pressure was less than the requirements of Technical Specifications paragraph 3.7.A.7 This resulted in operation in a degraded mode allowed by paragraph 3 7.A.7.A.3 for a period of approximately 35 minutes.

The differential pressure was out of specification approximately 0.04 psid due to a rapid drop in the reactor building cooling system temperature. An operator initiated trip of the reactor water cleanup system (due to a valve packing failure) resulted in a sudden decrease in the heat load on the reactor building cooling system which in turn resulted in a rapid decrease in the temperature of the reactor building cooling system. This temperature decrease resulted in a drywell pressure decrease (due to cooling).

Immediate restoration of the Reactor Building Cooling Water temperature to its normal range restored the drywell to torus differential pressure to within technical specification limits.

'To provide the operator with early warning that drywell to torus differential pressure is approaching the limit, the low differential pressure alarm has been raised to 1.75 psid.

In addition, the reactor building cooling system temperature alarm setpoint will be changed during the 1980 refeeling l

outage to provide the operator with early warning of decreasing temperature.

No further action will be required to reduce the probability of recurrence. The event did not represent a significant hazard to the public health and safety.

NOTE:

LER 80-017 is a related event.