ML20107B031

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Preliminary AO Rept 73-23:on 730924,failure of Differential Pressure Switch DPS 66A to Trip & Thereby Actuate Reactor Building to Torus Vacuum Breaker Block values,V-26-16-18
ML20107B031
Person / Time
Site: Oyster Creek
Issue date: 09/25/1973
From: Carroll J, Reeves D
JERSEY CENTRAL POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 AO-73-23, NUDOCS 9604150301
Download: ML20107B031 (3)


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,y Operations James P, O'ReillyDirectorate of Hagulatory 00:-

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  1. 50-219 Company Docket Jersey Central Power 6 Lightting Station Dyster Creek Nuclear Genera 08731 w Jersey Front Forked River, Ne i

73-23 nce Report No.

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submitted in Preliminary #snormal occurrea prelim i

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Subject:

The following is with the Technical Spec 3

comp 11ance 6.6.2.

Prelialnary Approval:

[r9/25/73 l

/a Date J. T. Carroll, Jr Mr. A. Gianbusso cc:

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Time: 2:40 p.m.

Preliminary Abnormal Occurrence Report No. 73-23 SulkiELT:

Failure of Differential Pressure Switch 0P3 66A to trip add j

i thereby actuate the reactor building to torus vacuum breaker block valves, Y-26-16 and 18 j

This event is considered to be an abnormal occurrence as de.

fined in the Technical Specifications, pai; graph 1.150.

Notification of this event a$ nquired by the Technical Spec-ifications, paragraph 6,6,2,a, was made to AEC Region I, Directorate of Regulatory Operations by telephone on Monday, September 24,1973, at 6:00 p.m., 'and by telecopier on Tuesday, j

1 September 25, 1973, et 3:00 p.m.

i SITUATION:

While performing routine surveillance testing as required by l

the Technical specifications, paragraph 4.5.1.5, Rifferential Pressure Switch DPS 66A failed to trip.

j CAUS!!:

Excess friction in the leakage pivots.

i REWiDIAL ACf10N:

The switch was removed, disassembled and cleaned. After re-assembly and installation, the unit was natisfactorily trip tested twenty (20) times and returned to service.

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Abnormal Occurrence

.I Septcaber 22, 1973 Report No. 73 23 SAFRTY _ SIGNIFICANCE:

As noted in the Technical specifications, "ihe shsorption cham.

bcr-reactor building vacuum relief system assures that the prl-mary containment is not operated at a negative pressure relative to Its surroundings... The vacuum relief system is a redun-dant system and full capacity is available through either velve."

Further, the differential pressure switches are themselves redundant in that either pressure switch will actuate both block valves.

In this case, since one of the switches was operabic, full relief capacity would have been provided through either valve since both would have been availabic. The significance of t.his event then is tho ioss of redundancy of the actuating switches.

Prepared by:

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