05000219/LER-1980-043, Forwards LER 80-043/03L-0

Forwards LER 80-043/03L-0

ML19344B564
Person / Time
Site:	Oyster Creek
Issue date:	10/14/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19344B565	List: 05000219/LER-1980-043, Forwards LER 80-043/03L-0 05000219/LER-1980-043-03, /03L-0:on 800925,during Routine Surveillance, Reactor Triple Low Water Level Sensor RE18D Tripped at Level Less Conservative than Tech Specs.Caused by Sensor Repeatability.Sensor Reset
References
NUDOCS 8010210493
Download: ML19344B564 (3)

LER-1980-043, Forwards LER 80-043/03L-0

Event date:
Report date:
2191980043R00 - NRC Website

text

o OYSTER CREEK NUCLEAR GENERATING STATION JCP&L~

GPU y g'"7 (609) 693-1951 P.O. BOX 388

• FORKED RIVER

• NEW JERSEY e o8731 c

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October 14, 1980 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Comission 641 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/80-43/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/80-43/3L in compliance with paragraph 6.9.2.b.1 of the Technical Specifications.

Very truly yours, hN ll[

Ivan R. Fin oc Jr.

Vice Presi ent eneration IRF:dh Enclosures cc: Mr. John G. Davis, Acting Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D.C.

20555 Mr. William G. Mcdonald, Director (3 copies)

Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 i

8010210<M N

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0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 License Event Report Reportable Occurrence No. 50-219/80-43/3L Report Date October 3, 1980 Occurrence Date September 25, 1980 Identification of Occurrence Exceeding a limiting condition for operation as per Technical Specifications, Section 3.1, Table 3.1.1, Function G.2, when reactor triple low water level sensor RE18D exceeded its required setpoint during surveillance testing.

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 Steady State Power Power:

- Reactor 1913 MWt Generator 635 MWe Flow:

Racirculation 15.4 x 104 gm Feedwater 7.1 x 106 lb/hr Description of Occurrence:

On Thursday, September 25, 1980, at approximately 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, while performing routine surveillance testing of the reactor triple low water level sensors,

~ RE180 tripped at a level which was less conservative than that specified in the Technical specifications.

Tests on all level sensors yielded the following data:

Pressure Switch Desired Manometer As Found As Left D_eshnation Reading at Trio Point ("H20).

("H20)

("H20) e System I RE18A

<126 124.5 122.1 RE18C

<126 123.5 122.5 System II RE18B 7126 125.8 122.0 RE18D 1126 128.0 121.5 The "As Found" value of 128.0" Hg0 corresponds to a water level 54" abcve the active fuel. The Technical Specification limit is 56".

l

1 Reportable Occurrence

- Page 2 Report No. 50-219/80-43/3L Apparent Cause of Occurrence Sensor Repeatability Analysis of Occurrence Failure of pressure switch RE18D to actuate at its prescribed setpoint would have delayed-initiation of reactor triple low water level indications. However, due to the existing logic configuration, the redundant switch, RE188, would have actuated to initiate the required functions at the required Technical Specification limit. The safety significance of this event is considered to be minimal since sensor RE18D's non-conservatism resulted only in a temporary loss of redundancy in the system.

Corrective Action

Reactor triple low level sensor RE18D was reset to trip within its prescribed limits.

4 An engineering study is in progress regarding the feasibility of replacing the existing sensors with a solid state system. Additionally, an evaluation will be performed by the manufacturer (ITT Barton) on the drift problem experienced with the snap-action switches.

Failure Data ITT Barton Differential Pressure Indicating Switch Switch Model #288A Adjustable Range 0-150 inches H 0 2

J 4

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