05000219/LER-1979-002-03, /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset

/03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset

ML19270F657
Person / Time
Site:	Oyster Creek
Issue date:	02/27/1979
From:	JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19270F654	List: 05000219/LER-1979-002, Forwards LER 79-002/03L-0 05000219/LER-1979-002-03, /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset
References
LER-79-002-03L, LER-79-2-3L, NUDOCS 7903070333
Download: ML19270F657 (3)

LER-1979-002, /03L-0 on 790206:while Performing Isolation Condenser Automatic Actuation Test & calibr,RE-15B Trip Point Was Less Conservative than Tech Spec Std.Caused by RE-15B Switch Not Set at 1068 Psig valve.RE-15B Reset

Event date:
Report date:
2191979002R03 - NRC Website

text

U.S. NUCLEAR REGULATORY COMMISSION RC FORM 366 77) f*

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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 7b REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h

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O 2 1 During normal operation, while performing the isolation condenser auto-l matic actuation test and calibration, the RE-15B trip point was found to l

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s Jersey Central Power & Ught Company Madison Avenue at Punch Bowl Road Morristown New Jersey 07963 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-2/3L-0 Report Date February 27, 1979 Occurrence Date February 6,1979 Identification of Occurrence Violation of the Technical Specifications, paragraph 2.3.5, reactor high pressure isolation condenser initiation pressure switch RE-15B tripped at a value greater than that specified in the Technical Specifications. This event is considered to be a reportable occurrence as defined in the Technical Specifi-cations, paragraph 6.9.2.b.l.

Conditions Prior to Occurrence Plant parameters at the time of the occurrence were:

Power:

Reactor, 1918.16 MWt Generator, 647 MWe 6

Flow:

Feedwater, 7.177 x 10 lb/hr 4

Recirculation, 15.4 x 10 gpm 4

Stack Gas:

5.4 x 10 pci/sec Description of Occurrence On Tuesday, February 6,1979, at approximately 0944 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.59192e-4 months <br />, while performing the " Isolation condenser automatic actuation test and calibration", the RE-15B trip point was found to be less conservative than that specified in the Technical Specifications.

Surveillance tests on the high reactor pressure switches for the isolation condenser systems revealed the following data:

Pressure Switch Desired Setpoint Designation (Head Correction Inc.)

As Found As left RE-15A 1068 1068 1068 RE-ISB 1068 1070 1068 RE-15C 1066 1065 1065 RE-15D 1066 1066 1066

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Reportable Occurrence No. 50-219/79-2/3L-0 Page 2 Feb rua ry 27, 1979 Apparent Cause of Occurrence instrument repeatability.

Analysis of Occurrence RE-ISB pressure switch would have actuated but at a pressure 2 psig greater than its prescribed value of 1068 psig. -The only safety significance of this event was the loss of redundancy in the pressure switch actuation at the prescribed setpoint.

Corrective Action

immediate corrective action was to reset RE-15B to trip at 1068 psig.

No further action is contemplated.

Failure Data Barksdale Switch #B2T-A12SS Proof 1800 psi Adjustable range 50-1200 psi t