ML20084C435

AO 50-219/74-53:on 741015,stack Gas Sample Sys Discovered Not Functioning Properly While Reactor Not in Isolated Condition.Caused by Excessive Air Flow to Pump Thereby Reducing Vacuum of Filter.Loose Fitting Tightened

ML20084C435
Person / Time
Site:	Oyster Creek
Issue date:	10/24/1974
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084C439	List: ML20084C435 ML20084C478
References
AO-50-219-74-53, NUDOCS 8304080043
Download: ML20084C435 (3)

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M.iDISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6111 NEunROFikE General (('[ ', Public Utilities Corocration SYSTE M October 24, 1974 f hs-QNQ,'t GCs .,

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United States Atomic Energy Commission w Washington, D. C. 20545

Subject:

Oyster Creek Station Docket No. 50-219 Abnorma1 0ccurrence Report No. 50-219/74-53 The purpose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the Technical Specifications.

Enclosed are forty copies of this submittal.

Very truly yours, O l W Donald A. Ross -

Manager, Nuclear Generating Stations es Enclosures ,

cc: Mr. J. P. O'Reilly, Director i Directorate of Regulatory Operations, Region 1 Q- R 19

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.ersey Centra if Power & Lig7t Company J k<f MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6111 nFlarnes of TNE General jj[ Public Utihties Corporation SFS f3 er OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/74-53 Report Date October 23, 1974 Occurrence Date October 15, 1974 Identification of Occurrence Violation of the Technical Specifications, paragraph 3.6. A.3, improper function-ing of the stack gas sample system while the reactor was not in an isolated condition. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraphs 1.15B and D.

Conditions Prior to Occurrence A normal reactor startup was in progress with the reactor mode switch in the "STARTUP" position. Reactor water temperature was icss than 212*F.

Description of Occurrence.

On October 14, 1974, at 1230, the stack gas sampic pump was replaced, with the reactor in an isolated condition, as a preventive maintenance consideration.

At 1730 on October 14, 1974, the stack gas sampic system wass returned to service and appeared to operate properly. At 0033 on October 15, 1974, the main steam isolation valves were opened in the course of a reactor startup.

At 0100 on October 15, 1974, an equipment operator noted that the stack gas sampic pump appeared to be operating at a higher than normal temperature. At 0543 on October 15, 1974, the stack gas filter was replaced in an attempt to determine if the stack gas sampic system was operating properly.

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i l' Abnormal Occurrence Report No. 50-219/74-53 Page 2 i

i At approximately 0629 on October 15, 1974, further investigation of the stack

.{ gas sample system was conducted. Sample air flow indication was normal; how-

! ever, there was no indication of vacuum at the filter and the pump oil level j was low. The pump was refilled with oil and an indication of vacuum at the filter j was observed although air flow could not be regulated and pump oli 1cvel de-j creased rapidly. On the basis of these observations, the stack gas sample i

1 system was considered to be inoperative and at 0630 the reactor was isolated.

Apparent Cause of Occurrence i

s Examination of the pump revealed a loose fitting between the oil flow regulating .

. valve and the oil reservoir which feeds to the pump suction. The loose fitting j permitted excessive air flow to the pump suction through the oiling system and l so reduced or eliminated the vacuum at the filter.

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i Analysis of Occurrence 1

Since it is not possibic to determine the exact time at which the stack gas j sample system became inoperative, it must be assumed that the niant was operated j in violation of Technical Specifications, paragraph 3.6. A.3, daring the time j that the reactor was not isolated (from 0033 on October 15, 1974-to 0630 on October 15, 1974). The safety significance of this event is cansidered to be j minimal since the reactor was critical with reactor coolant less than 212 F and-

no releases were being made from the mechanical vacuum pumps, steam jet air 1 ejectors, or from the containment vessel.

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$ Corrrective Action The stack gas sample pump was examined and the loose fitting t'ightened. The j system was then returned to service and observed to operate normally.

t j Failure Data

! Not applicable.

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