ML20090D853

AO-50-219/74-18:on 741108,common Indicator for Isolation Valves V-28-5 & 6 Did Not Indicate Closed.Caused by Rust Accumulations on Piston Lands & Cylinder Walls of V-28-6. Rust Removed

ML20090D853
Person / Time
Site:	Oyster Creek
Issue date:	11/18/1974
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
References
AO-50-219-74-58, NUDOCS 8303030265
Download: ML20090D853 (3)

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.ersey Centra Power & Lig7t Company F y j

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• MORRISTOWN, N.J. 07960

• 201-509-6111 NEMMt R OF THE General Public Utilities Corporation -

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' "" .. l id &h Mr. A. Giambusso Deputy Director for Reactor Projects i ",' ,

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Directorate of Licensing United States Atomic Energy Commission Washington, D. C. 20545

Subject:

Oyster Creek Station Docket No. 50-219 Abnormal Occurrence Report No. 50-219/74-58 The pu! pose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the Technical Speci-ficati ons .

. Enclosed are forty copies of this submittal.

Very truly yours,

1. dif.xLbl:'

Donald A. Ross

'cGU' Manag,cr, Generating Stations-Nuclear pk Enclosures e

cc: Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region 1 11256 8303030265 741118 PDR ADOCK 05000219 S PDR

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.ersey Centra Power & Lig7t Company v

MADISON AVENUQ AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6111 NEmmtM ff THE General yjj]*, Public Utilities Corporation Sr$7E tr OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/74-58

" Report Date November 18, 1974 Occurrence Date November 8, 1974 Identification of Occurrence Violation of the Technical Specifications, paragraph 3.5.B.1, failure o maintain secondary containment integrity -(as defined in paragraph 1.14 of the Technical Specifications) with the reactor operating at power. This event is considered to be an abnormal occurrence as defined in the Technical Specifications,(paragraph 1.15B. ,.

Conditions Prior to Occurrence The plant was at steady state power with major parameters as follows:

i'ower: Reactor, 1907.51 FMt Electric, 655 FMc 4

Flow: Recirculation, 15.6 x 10 gpm Feedwater, 7.12 x 10 lb/hr 6 Reactor Pressure: 1019 psig Stack Gas: 30,525 pCi/sec*

• Standby gas treatment system in operation.

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y Abnormal Occurrence Report O ~

No.

50-219/74-58 o ' Page 2 1

Lescription of Occurrence 9

At approximately 1630 on November 8,1974, while performing secondary containment leak rate testing .it was noted that the common indicator for isolation valves V-28-5 and V-28-6 did not indicate , closed following isolation of the reactor building ventilation system. Investigation revealed that V.28-6 was not in the fully closed position. The redundant valve, V-28-5, was found to be in the fully closed position. Note that the test results were acceptable even with V-28-6 partially opeu.

Apparent Cause of Occurrence , ' ,

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! Rust accumulations were found on the piston lands and cylinder walls of the j valve operator for V-28-6. These accumulations caused binding which prevented

the valve from closing fully. It is believed that condensation on the valve i operator components caused the rust accumulations.

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J Analysis of Occurrence v .

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The safety significance of this event 'is the -loss of isolation valve redundancy.

Although V-28-6 did not fully close, the redundant isolation valve, V-28-5, I functioned normally and closed fully. ,

Corrective Action a

The valve operator for V-28-6 was disassembled by the maintenance departmen.t and _ ,

small rust accumulations were found on the piston lands and . cylinder walls as mentioned above. These rust accumulations caused the parts to bind, and this i prevented the valve from closing fully. The rust was removed and the cperator s reassembled. V-28-6 was satisfactorily tested and returned to service on 0400 on November 9,1974. All operators on air operated ventilation isolation valves in the reactor building will be inspected. Die operators will be cicaned if the inspection indicates it is necessary. In addition, a surveillance pYogram l on the instrument air system will be developed and implemented in order to -

! ascertain problem areas, if any, in that system.

Failure Data j Manufacturer - Rockwtil  !

I Type - 14" Butterfly Valve (air operated) i i

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