ML20106J885
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To:
James P. 'O'Reilly Directorate of Regulatory Operations Region 1 631 Park Avenue f.ing of Pmssia, Pennsylvania 19406 From:
Jersey Central Power. 4 Light Company Oyster Creek Nuclear Generating Station Docket #50-219 Forkod River, New Jersey 05731 4
Subjectt Prolininary Ahnonnal Occurrence Report No. 75-34 The following is n preliminary report being sthuitted in compliance with the Technical Specifications, i-I, parseraph 6.6.2 i
Preliminary Approval 1-i b
12/28H3 m:u J.T.Carrod,.N.
Date cc; Mr. A. Giambusso 9604120045 960213 i
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l' Pro 11dnary w.g, 4 e
t Abnomal Occurrsnce Report N2, 73-34
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SUBJECT:
Violation of the Technical specifications, Table 3.1.1.B.6, which requires that the Main Steam Line High Radiation Mtmitors trip at a level of 10 times background.
This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15A.
Notification of this event, as svquired by the Technical Specifications, para-
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graph 6.6.2.a, was made to AEC Region I, DiMetorate of Reguistory Operations, by telephone on 1hursday, Deceder 27, 1973, at 1640, l
and by telecopior on Friday, Decedor 28, 1973, at 0940.
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S1TUATION:
During the normal surveillance testing of tho' Nain Steam Line l
High Radiation Monitors, it was observed that the RN05A Log Count l
Rate Monitor failed to trip at its normal setpoint of 1000 cps.
The Co" source used to introduce the test signal was moved closer to the detector, thereby increasing the test signal to approximately l
l 4000 cps in an unsuccessful attempt to determine the actual trip point,- The monitor would not trip regardless of the signal applied.
CAUSE:
The cause of this occurrence is presently under investigation.
REMEDI_AL _ ACTION:
The RN05A log Count Rate: Monitor assembly was replaced.
SAFETY SIGNIFICANCE:
The safety significance cannot, at this tim, he determined since the failure occurred on the first channel tested and the other
1 Abnormal occurrsnce
', December 27, 1973 Rep;rt No. 73-34 g,
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i throo channels (M058, C, and D) cannot be surveilled until the replacement unit is properly calibrated and a successful surveil-lance test condus ted. If this is the only unit to experience
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these difficulti st, the safety significanco is in the loss of system redundancy.
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