05000219/LER-1981-019, Forwards LER 81-019/03L-0

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Forwards LER 81-019/03L-0
ML20003H300
Person / Time
Site: Oyster Creek
Issue date: 04/27/1981
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20003H301 List:
References
NUDOCS 8105050505
Download: ML20003H300 (3)


LER-1981-019, Forwards LER 81-019/03L-0
Event date:
Report date:
2191981019R00 - NRC Website

text

.

OYSTER CREEK NUCLEAR GENERATING STATION

.EnDMu Annn N"e%7,%'57]

(609)693-6000 P.O. BOX 388

  • 08731 wnes s,vem April 27, 1981 gg e

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Mr. Boyce H. Grier, Director

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Office of Inspection and Enforcenent 8_;

N g' S Region I H

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United States Nuclear Regulatory Ccmnission 631 Park Avenue

'g King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Gerarating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-19/3L This letter forwards three copies of a Licensee Event Report to rep rt Reportable Occurrence No. 50-219/81-19/3L in ccr:pliance with paragraph 6.9.2.b.3 of the Technical Specifications.

Very truly yours,

?.j FA-l van R. Finf Jr.

I ice President JCP&L l

Director - Oyster Creek IRF:dh Enclosures cc: Director (.40 copies)

Office of Inspection and Enforcenent United States Nuclear Regulatory Ccmnission Washington, D.C.

20555 Director (3)

Office of Management Infouration and Program Control United States Nuclear Regulatory Ccanission Washington, D. C. 20555 i

NRC Resident Inspector (1)

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

81050505o5 6

s OXSTER CREEK NUCLEAR GENERATING STATICN Forked River, New Jersey 08731 Lic e see Event Report Reportable Occurrence No. 50-219/81-19/3L Report cate April 27, 1981 Occurrence Date March 28, 1981 Identification of Occurrence Failure to perform a survaillance test as required by 'Ibchnical Specifications, paragraph 4.1 Table 4.1.1.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.3.

Conditions Prior to Occurrence Routine Shutdown Description of Occurrence On March 28, the plant was progressing towards cold shutdown to correct an increasing leak rate in the Primary Containment. During the normal shutdown sequence, the IBM ('alihration was not performed as required. When the IRM's were inserted sufficiently for the calibration, pcwer level was too low for the calibration to be performed. The correlation used to calenlate reactor power is inaccurate below 10% power.

Apparent Cause of Occurrence i

Procedure - Procedure 203.2 did not adequately specify the power level at which to perform the calibration.

Analysis of Occurrence j

The purpose of the IBM Systs is to provide a means of monitoring reactor power level between the APRM and SRM ranges, and to provide SCRAM protection in the event of a reactivity excursion.

The systs was not rendered inoperable, but was possibly out of calibration.

During a shutdown, the contribution to the heat balance by decay heat makes the ralibration less accurate than during a startup. Due to this consideration and the continuing process of shutdown at the time of occurrence, the safety signifi-cance of this event is considered to be minimal.

- w+,

m 7-,

Reportable Occurrence Page 2 Report No. 50-219/81-19/3L

Corrective Action

'Ihe calibration was perfonned during the startup on Marcti 31, 1981.

Both the IIM ralibration procedure and the Plant @l% fran Hot Stanoby to cold Shutdown procedure will be revised prior to startup to specify the power

- level at which to perform the IIM ralihration.

Failure Data Not Applicable.

t I

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