PNO-III-87-052, on 870408,licensee Reported That Channel Check of Containment High Pressure Instrumentation Not Performed Once Per Shift.Caused by Incorrect Designation of Instrument or Omission in Surveillance Procedure

PNO-III-87-052:on 870408,licensee Reported That Channel Check of Containment High Pressure Instrumentation Not Performed Once Per Shift.Caused by Incorrect Designation of Instrument or Omission in Surveillance Procedure

ML20206P531
Person / Time
Site:	Clinton
Issue date:	04/10/1987
From:	Knop R, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
References
PNO-III-87-052, PNO-III-87-52, NUDOCS 8704210210
Download: ML20206P531 (1)

PRELIMINARY NOTIFICATION' 0F EVENT OR UNUSUAL OCCURRENCE--PNO-III-87-52 Date April 10, 1987 ONb This prelizinary notification constitutes EARLY notice of events of POSSIBLE safety cr public interest significance. The information is as initially received without verification or cvaluation, and is basically all that is known by the Region !!! staff on this date.

Facility: Illinois Power Company Licensee Emergency Classification:

Clinton Nuclear Plant Notification of an Unusual Event Clinton, IL 61727

• Alert Site Area Emergency Docket No. 50-461 General Emergency X Not Applicable

Subject:

FAILURE TO PERFORM CERTAIN PERIODIC INSTRUMENT CHANNEL CHECKS On April 8, 1987, the licensee reported that the channel check of containment high pressure instrumentation was not being performed on a once-per-shif t frequency as required in the unit's surveillance procedure. Further reviews by the licensee identified three other instruments or circuits which were not being checked each shift as required. These three were one of the low-1m reactor water level indicator circuits; a Residual Heat Removal permissive circuit; and temperature indication circuits for equipment areas.

All the failures were associated with the incorrect designation of an instrument or an omission in the same surveillance procedure. Each of these checks is required to be performed every l 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by the Technical Specifications and every shift, according to the licensee's procedure.

The aissed checks have been occurring since the plant began operation.

Wh:n the problem was identified, the licensee checked all affected instruments and circuits and found them to be performing properly. A channel check is the least extensive of three tests whicQ ara performed on the instrument circuits. The other tests -- a functional test and a calibration i

check -- are performed at longer intervals and were not affected by the deficient shift channel check procedure.

l

! The licensee has reviewed each of the more than 1100 instruments and circuits involved which are required to be checked under the Technical Specifications to assure that all are covered by the surveillance procedures. A separate review of the instruments used to perform the Technical Sp;cification channel checks is in progress. The licensee is preparing a report of its findings for submission to Region III on April 10, 1987. The review identified an additional omission l - a high reactor water level circuit. It is not required to be checked in the current reactor mode.

! Region III (Chicago) has inspectors on site reviewing the licensee's activities. This PN is being issued because of the pending consideration of a Full Power Operating License.

l Th2 State of Illinois will be notified. IN PND-III-97-OS2 PDR R:gion III received initial notification of this problem on April 8, 1987. Further information was received from the licensee and NRC personnel at the site on April 9-10. This information is current as of 11 a.m. (CDT), April 10, 1987.

cR.gKnop fr$' ITS M 11E .r CONTACT: ( 388-5547) R. Warnidk (FTS 388-5575)

DISTRIBUTION:

H. St. EDO NRR E/W Willste Mail: ADM:DMB Chairman Zech PA IE NMSS DOT:Trans only Com. Roberts ELD OIA RES Comm. Asselstine AEOD NRC Ops Ctr /J.'.2/

Com. Bernthal Comm. Carr SP M//d Regional Offices ACRS SECY INPO /,.2% NSAC /.Ul7 CA RIII Resident Office l PDR Licensee:

/J7 .9 f (Corp. Office - Reactor Ei- Lic. Only) N