05000265/LER-1980-016, Forwards LER 80-016/03L-0

Forwards LER 80-016/03L-0

ML19338C933
Person / Time
Site:	Quad Cities
Issue date:	08/11/1980
From:	Kalivianakis N COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19338C934	List: 05000265/LER-1980-016, Forwards LER 80-016/03L-0 05000265/LER-1980-016-03, /03L-0:on 800723,discovered That Pressure Switch PS-2-261-30C Would Trip at 841 Psig,Under Limit of 850 Psig. Caused by Instrument Drift.Pressure Switch Recalibr & Tested Satisfactorily
References
NJK-80-277, NUDOCS 8009080398
Download: ML19338C933 (2)

LER-1980-016, Forwards LER 80-016/03L-0

Event date:
Report date:
2651980016R00 - NRC Website

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Commonw;:lth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 NJ K-80-277 August 11, 1980 J. Keppler, Regional Di rector Office of Inspection and Enforcement Region 111 U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reference: Quad-Cities Nuclear Power Station Docket No. 50-265, DPR-30, Unit 2 Appendix A, Sections 2.1.H. and 6.6.B.2.b.

Enclosed please find Repor.able Occurrence Report Number R0 80-16/03L for Quad-Cities Nuclear Power Station.

This report is submitted to you in accordance with the requirements of Technical Speci ficatior 6.6.B.2.b., as a condition leading to operation in a degraded mode permitted by a limiting condition for operation.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEA POWER STATION

/ /

f N. J. Kalivianakis Station Superintendent NJK:JW/bb Enclosure cc R. F. Janecek i

8 d'

y4f, 6ij 8009080378 5

1.

LER NUMBER: LER/R0 80-16/03L ll, LICENSEE NAME: Commonwealth Edison Company quad-Cities Nuclear Power Station 111.

FACILITY NAME: Unit Two IV.

DOCKET NUMBER: 050-265 V.

EVENT DESCRIPTION

On July 23, 1980, while instrument technician was performing Main Steam Line Low Pressure isolation Surveillance Test, procedure QlS-20, pressure switch PS-2-261-30C was found to trip at 841 psig. Technical Specification 2.1.H. requires a limiting condition for operation not to be less than 850 psig. The as found trip point was below the Ilmit by 9 psi. The pressure switch was recalibrated and tested satisfactorily immediately after the occurrence.

.VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The Main Steam Line Low Pressure Isolation is arranged in a one-out-of-two-twice logic.

Since the redundant pressure switches did function properly in this incidence, the reactor would have isolated within limits should an isolation condition occur. The reactor was not endangered and the public safety was not threatened at any time in this occurrence.

Vll.

CAUSE

The cause of this occurrence is attributed to the Instrument drift.

Vill.

CORRECTIVE ACTION

The temediate corrective action was to recalibrate the pressure switch.

Another test was subsequently performed satisfactorily. The pressure switch is manufactured by Barksdale; the model number is B2T-Al2SS.

Last failure of this kind was on January 14, 1975