05000219/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl

Forwards LER 82-007/03L-0.Detailed Event Analysis Encl

ML20041D796
Person / Time
Site:	Oyster Creek
Issue date:	02/25/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20041D797	List: 05000219/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl 05000219/LER-1982-007-03, /03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered
References
NUDOCS 8203090221
Download: ML20041D796 (1)

LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191982007R00 - NRC Website

text

,

GPU Nuclear h

y gg P.O. Box 388 Forked River. New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

February 25, 1982 d"aI 9 n

Mr. Ibnald C. Ilaynes, A%instrator Ikxjion I

(

gs United States Nuclear Regulatory Cmmission RECEWED 631 Park Avenue fg D

King of Prussia, Pennsylvania 19406

Dear Mr. !aynes:

9 th 7

SUIUDCT: Oyster Creek Nuclear Generating Sta W

Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/82-07/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/82-07/3L in cm pliance with paragraph 6.9.2.b.1 of the Technical Specifications.

Very truly yours,

)-

Ie r B. Fied Vice President - Director Oyster Creek PBF:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforement United States Nuclear Regulatory Cmmission Washington, D.C.

20555 Director (3)

Office of Management Information and Program Control United States Nuclear Regulatory Ccarission Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

8203090221 820225 PDR ADOCK 05000219 S

PDR GPU Nuclear is a part of the General Pubhc Utihties System ptt-

7 OYSTER CREEK NIX 1 EAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Rei. ort Reportable Occurrence No. 50-219/82-07/3L Report Date February 25, 1982 Occurrence Date January 26, 1982 Identification of Occurrence During surveillance testing, the Main Steam Line high flow sensor RE-22H tripped at a value greater than the value given in the Technical Specifications, Table 3.1.1, Itam B.3.

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

Conditions Prior to occurrence lant was in the refuel mode with reactor coolant terperature less than Description of Occurren On Tuesday, January 26, during surveillance testing, high flow sensor RE-22H tripped at a value greater than the Technical Specification limit of <97.5 psid. The testing yielded the following data:

4 Sensor Designation Desired Set}y2nt (psid) As Found (psid) sAs Inft (psid)

=

RE-22A

<97.5 94.5 88 RE-22B 797.5 93 88

}

RE~22C 797.5 94 87 l

RE-22D 797.5 90.5 88.5 RE-22E 797.5 92 87 RE-22F 797.5 89 87.5 RE-22G 797.5 89 88.5

~ 7.5 100 88.5 9

RE-22H Apparent Cause of Occurrence The cause is attributed to instrument repeatability. The total design accuracy is 9.0 psid which is based on the results of the engineering study performed to investigate the repeatability probles associated with this type of sensor.

Sensor RE-22H was last set at 92.5 psid and tripped at 100 psid; therefore, it was operating within design accuracy of the instrument.

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Reportable Occurrence Page 2 Report No. 50-219/82-07/3L Analysis of Occurrence Either of the Main Steam Lines will isolate due to a line break as sensed by either a high tmperature or a high flow condition. Each steam line contains 4 high flow sensors (two in each logic trip systs). Actuation of one sensor from each trip syst s will initiate a N IV closure. 'Iherefore, operation with RE-22H sensor setpoint at a value higher than the Technical Specification limit would not have prevented closure of the MSIV's in a timely manner. As a result the safety significance of this occurrence is considered minimal.

Corrective Action

The sensor was reset to trip within the Technical Specification limit. The setpoint has been lowered from 92.5 psid to R7.5 ocid with a setthe band of

+1.0 psid (note the "As Left" values in the Description of Occurrence) in order to account for instrument drift. FurthenTore, an enginew.ng study to investi-gate the proble of repeatability with this type of sensor has recum.erdal the replacment of the sensors with qualified sensors of irtproved accuracy. 'Ihe replacment is planned for the 1984 refueling outage.

Failure Data Manufacturer: ITT Barton Mxlel:

1. 288A Pressure Indicating Switch Range:

0-200 psig