ML19269E401

LER 79-019/03L-0 on 790526:reactor High Pressure Isolation Condenser Initiation Switch RE-15A Tripped at 3 Psig Greater than Specified.Caused by Instrument repeatability.RE-158 Reset to Trip at 1,068 Psig

ML19269E401
Person / Time
Site:	Oyster Creek
Issue date:	06/21/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19269E397	List: ML19269E396 ML19269E401
References
LER-79-019-03L, LER-79-19-3L, NUDOCS 7906280122
Download: ML19269E401 (3)

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EVENT CESCRrPTION AND PRCD AELE CONSECUENCES h 0 IO l Cn'May 26, 1979, while performino the isolation condeme- nnen-*1c ac- 1 i3I l tuation test. reactor hiah pressure isolation condenser initiation switch ]

I, i4 (_ _ _ _ 'E-15A t ripped at a value three (3) psig greater than specified in 1 0 16a ! Tech Spec 2.3.5. The only safety significa ce of this event was the l Ir is  ! los's of redundancy in the pressure switch actuation at the prescribed ]

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, -i Instrument repeatability was the apparent cause of this eve.t. It i e : - t i should be noted that the instrument actuated within its design accuracy.

3 2 l The immediate corrective action was to reset RE-15A to trip at 1068 j i 3 l psig. No further action is contemplated. l 1 14 l l 7 E 9 80 F ACILITY A*ETHOD CF STATUS l:I* POWER OTH E R STATUS DISCoVE AY DISCOVEPY DES 0piPT.CN i 5 y @ l0l0l0l@l NA l lBl@l Surveillance Test l 7 8 9 10 12 11 44 45 46 ACTIVITY . CONTENT 80 P E tt A'. E C OF PE LE ASE AYOUNT CF ACTIVITY LOC ATIO*. C8 RELE ASE ...

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Momstown, New Jersey 07350 (201)455-8200 0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-19/3L-0 Recort?Date June 21, 1973 Occurrence Date May 26, 1979 m _._:ficcticn of Occurrence Reretor high pressure isolation condenser initiation pressure switch RE-15A tripped at a value greater than that specified in the Technical Specification, section 2.3.5 This event is considered to be a reportable occurrence as acf!ned in the Technical Specifications, paragraph 6.9.2.b.l.

_ di ions Prior to Occurrence "he plant was in a cold shutdt v.1 condition.

Reactor coolant temperature 144 1.

". ode switch in refuel.

Reactor water level 86".

All control rods at 00.

Source range monitor ~60 cps.

Description of Occurrence On Saturday, May 26, 1979, at approximately 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br />, while performing the

" isolation condenser automatic actuation test," the RE-15A trip point was found to be less conservative than that specified in the Technical Specifications.

Surveillance test on the high reactor pressure switches for the isolation ,,

condenser system revealed the following data:

Pressure Switch Desired Setpoint Desianation (Head Correction included) As Found As Left RE-15A 1063 1071 1068

E-ISB 1060 1068 1068 RE-15C 1066 1066 1066 RE-15D 1066 1066 1066 2170 115 u u m._

, Reportable Occurrence No. 50-219/79-19/3L-0 Page 2 June 21, 1979 Apparent Cause of Occurrence The cause of this event is attributed to instrume7t repeatability, it is noted that the instru.aent was operating within its design accuracy.

Analysis of Occurrence RE-15A pressure switch would have actuated, but at a pressure 3 psig greater than it 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.

Correctise Action Imuediate corrective action was to reset RE-15A to trip at 1068 psig. No further action is contemplated.

aiture Data Darksdale 5.. itch #B2T A12SS Proof 1800 psi Adjustable range 50-1200 psi 2170 116 ff

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