05000219/LER-1981-068, Forwards LER 81-068/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-068/03L-0.Detailed Event Analysis Encl
ML20040C650
Person / Time
Site: Oyster Creek
Issue date: 01/18/1982
From: Carroll J
GENERAL PUBLIC UTILITIES CORP.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20040C651 List:
References
NUDOCS 8201290122
Download: ML20040C650 (3)


LER-1981-068, Forwards LER 81-068/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2191981068R00 - NRC Website

text

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g7 P.O. Box 388 Forked River New Jersey 08731 609-693-6000 Writer's Direct Dial Number January 18, 1982 Mr. Ronald Haynes, Director

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Office of Inspection and Enforcement

'l-Region I Ol FEEJF.D United States Nuclear Regulatory Comnission JAN 2719825 f 3 631 Park Avenue King of Prussia, Pennsylvania 19406 S e met i.m1tra C g.,

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Dear Mr. Haynes:

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i SUBJECT: Oyster Creek Nuclear Generating Sta ' II d' Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-68/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-68/3L in empliance with paragraph 6.9.2.b.1 of the Technical Specifications.

Very truly yours, l

0

. T. Carroll, J.

,!ActingDirectorLOysterCreek JIC:dh y

Enclosures cc: Director (40 copies)

Office of Inspection and Enforcernent United States Nuclear Regulatory Comnission i

l Washington, D.C.

20555 Director (3)

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

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

f*((129EER*O!!ggy di pk GPU Nucie.

the General Pubhc Utikties System

c OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licel.aoe Event Report Reportable Occurrence No. 50-219/81-68 p rt Date January 18, 1982:

O_ccurrence Date Decmber 18, 1981 Identifi_ cation of Occurrence buring surveillance testing, the reactor triple low water' level indicator switch RE-18A tripped at a value greater than the desired setpoint as given in the Technical Specifications, Table 3.1.1, Itan G.2 This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2,b.l.

Conditions Prior to Occurrence The plant was in the refuel node with reactor teuperature less than 2120F and the reactor vented.

Description of Occurrence On January 15 during performance of the " Reactor Triple Im Water Iavel Test and Calibration" (Procedure 619.3.006), level indicator switch RE-18A tripped at a value greater than the 'Ibchnical Specification setpoint of < 126" H20. (56" above top of active fuel). The As Found value was 130.0" H2O which corresponds to a level of 53" above the_ top of active fuel.

Apparent Cause of Occurrence The cause of the occurrence was due to instrument drift.

Analysis of Occurrence The failure of switch RE-18A to actuate at the desired setpoint would not have delayed the initiation of triple low water level protection functions since RE18C, redundant to RE18A would have initiated the required actions within the Technical Specification limit.

o Reportable Occurrence Page 2.

Report No. 50-219/81-68

Corrective Action

The triple low water level sensor RE-18A was reset at 120" H20. Further testing, l

on sensors RE188, RE18C, and REl8D was halted to revise the procedure for more.

conservative As Ieft values of 115" H2O to 119" H20. Furthermore, an engineering study of this type of sensor has recomnended the replacement with qualified sensors of inproved accuracy. The replacment is planned for a future refueling outage.

Failure Data Manufacturer:

ITT Barton Model:

288A Indicating Pressure Switch Range:

0-150" H2O