05000219/LER-1980-038, Forwards LER 80-038/03L-0

Forwards LER 80-038/03L-0

ML19347A951
Person / Time
Site:	Oyster Creek
Issue date:	09/25/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347A952	List: 05000219/LER-1980-038, Forwards LER 80-038/03L-0 05000219/LER-1980-038-03, /03L-0:on 800826,during Surveillance Testing of Reactor Triple Low Water Level sensors,RE18B Tripped at Level Less Conservative than Tech Spec Limits.Caused by Sensor Repeatability.Sensor Reset within Prescribed Limits
References
NUDOCS 8009300564
Download: ML19347A951 (3)

LER-1980-038, Forwards LER 80-038/03L-0

Event date:
Report date:
2191980038R00 - NRC Website

text

.

o OYSTER CREEK NUCLEAR GENERATING STATION Q

",n".*, L, fM.aMC""'., uom som, (609) 693-1951 P.O. BOX 388

• FORKED RIVER

• NEW JERSEY

• o8731 c".

September 25, 1980 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Commission 641 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: 0yster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/80-38/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/80-38/3L in compliance with paragraph 6.9.2.b.1 of the Technical Specifications.

Very truly yours, Ivan R.

infr k,

Vice President Generation i

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 Proc 3m Control United States Nuclear Regulatory Commission Washington, D.C.

20555 O

8009800 66Y 3

4 0YSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 License Event Report Reportable Occurrence No. 50-219/80-38/3L Report Date September 25, 1980 Occurrence Date August 26, 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 RE18B 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.1.

Conditions Prior to Occurrence Steady State Power Power:

Reactor 1568 MWt Generator 491 MWe 12.1x10fgpm Flow:

Recirculation Feedwater 5.76 x 10 lb/hr Description of Occurrence:

On Tuesday, August 26, 1980, at approximately 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, while performing routine surveillance testing of the reactor triple low water level sensors, RE18B tripped at a level which was less conservative than that specified in the Technical specifications.

Tests on all level sensors yielded the following data:

1 Pressure-Switch Desired Manometer As Found As Left Designation Reading at Trio Point ("Hp0)

("H90)

("Hp0)

System I RE18A

<126 123 123 RE18C 7126 123 123 System II RE18B 7126 128 123 RE18D 1126 126 123 The "As Found" value of 128" H O corresponds to a water level 54" above the 2

active fuel. The Technical Specification limit is 56".

l

a Reportable Occurrence

- Page 2 Report No. 50-219/80-38/3L Apparent Cause of Occurrence Sensor Repeatability Analysis of Occurrence Failure of pressure switch RE18B to actuate at its prescribed setpoint would have delayed initiation of reactor triple low water level indications.

Ho' wever, due to the existing logic configuration, the redundant switch, RE180, would have actuated to initiate the required functions at the required Technical Specification limit. The safety significance of this event is conridered to be minimal since sensor RE18B's non-conservatism resulted only in a temporary loss of redundancy in the system.

Corrective Action

Reactor triple low level sensor RE18B was reset to trip with its prescribed limits.

An engineering study is in progress regarding the feasibility of replacing the existing sensors with a solid state system.

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

I

=