ML19294C058

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LER 80-005/03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift
ML19294C058
Person / Time
Site: Oyster Creek
Issue date: 02/28/1980
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19294C057 List:
References
LER-80-005-03L, LER-80-5-3L, NUDOCS 8003060608
Download: ML19294C058 (3)


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75 REPORT Osit E0 g 63 61 00 0 A ET '.w'.'i E si 65 Cr E V E NT O AT E EVEf.T DEEORIPTION ANO PROS ABLE CONSECUENCES h j e I: !l On February 5, 1980, during weekly surveillance of the ;tandby gas treat-

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2. 34 cA' sE des:: HIPTICN AND COARE 'TIVE ACTIONS h lo l Personnel error and instrument drift are the causes for this occurrence. l

. ei l The instrument technician who performed a calibration on RN04A-1 a week l earlier misread the meter scale. The non-conservative setpoint on  ;

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Jersey Central Power & Light Company Mac son Avenue a: P.,':? BoM Road r) > Morr stown, New Jersey 0360 (201):55-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-5/3L s

Recort Date February 29, 1980 Cccurrence Date February 5, 1980 Icentification of Occurrence Exceeding a limiting condition for operation as per stated in the Technical Specifications, table 3.1.1.J.2.

This event is considered to be a reportable occurrence as defined in the Techni-cal Specifications, paragraph 6.9.2.b.1.

Conditions Prior to Occurrence The plant was shutdown for a refueling / maintenance outage.

The reactor mode switch was locked in refuel.

The reactor cavity was flooded and less than 212*F.

Description of Occurrence On February 5,1980, at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, during weekly surveillance of the standby gas treatment system, the area radiation monitors RN04A-1 and Rh sA-2, located at the reactor building vent manifold, were found to be less conservative than that specified in the Technical Specifications.

The instrument setpoints were observed to be as follows:

Power Required Supply ARM Designation Setpoint As Found As Left 0

RN37 RN04A-1 ~~ 13 + 2 35 13 RN37 RN04A-2 _. 13 _.7 -0 2

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Fe;3":a:le Occarrence No. 50-215/B0-5/3; Page 2 Fec r ua r y 29, 1930 Ascarec: Cause of Occurrence The failure of area radiation monitor (ARM) RN04A-1 to trip at the proper set-point is due to personnel error in that an instrument technician, who performed a calibration on the instrument a week earlier, misread the meter scale. The non-conservative setpoint on ARM RN04A-2 is attributed to instrument drift.

Analvsis of Occurrence s The reactor building ventilation moni soring system continuousiv measures, indi-cates, and records the radioactivity levels (gross gamma) in the reactor building ventila: ion syste - When radiation levels in the main ventilation system reach a level e:ual to the setcoint for automa:ic isolation c' the reactor building venti-lation system, the standby cas treatmen; system is energized. The setpoints for area radiation monitors RN04A-1 and RN0kA-2 were found to be less conservative than those specified in the Technical Snecifications; therefore, the standby gas treatment system would have energized an: performed its intended function but at a nigher release rate.

The safety significance of this event is considered minimal since the stack gas monitor was functioning properly, if an abnormally high stack gas reading had been observed, the control room operator would have determined the cause to be related to the reactor building ventile* ion system, thus he could have initiated the standby gas treatment system manually to filter the air prior to release to the stack.

Corrective Action The area radiation monitors RN04A-1 and RN04A-2 were reset to trip within the prescribed limits.

Failure Data Not Applicable.

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