ML19323C611

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LER 80-018/03L-0:on 800413,during Chemistry Surveillance, Discovered That RCS Chloride & Fluoride Concentrations Were 0.24 Ppm & 0.274 Ppm.Caused by Chloride & Fluoride Contamination on Walls & Floors of Fuel Transfer Canal
ML19323C611
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 05/05/1980
From: Lancaster K
FLORIDA POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19323C607 List:
References
LER-80-018-03L, LER-80-18-3L, NUDOCS 8005160390
Download: ML19323C611 (2)


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i o ,2 i 10n 13 April during routine chemistry surveillance, it was discovered that the ,

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lairl [ reported under this specification. Reference LER 79-23 and 67. [

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.a Nared-cf preparer: K. F. Lancaster , (904 795-6'.M (SEE ATTACED SUPPLE'.t:.2.i'D.E DIFO:cfATION S~ce.ZT) ,

SUPPLEMENTARY INFORMATION U Raport No.: 50-302/80-018/03L-0 Facility: Crystal River Unit #3 Report Date: 5 May 1980 Occurrence Date: 13 April 1980 Identification of Occurrence:

Reactor Coolant System chloride and fluoride concentrations exceeded the limits imposed by Technical Specification 3.4.7 Conditions Prior to Occurrence:

Mode 6 refueling.

Description of Occurrence:

At 0140, it was discovered that the fluoride concentration in the Reactor Coolant System was 0.274 ppm. This exceeded the Technical Specification steady state limit of .15 ppm. At 0745, it was discovered that the chloride concentration was .24 ppm which exceeded the Technical Specification steady state limit of

.15 ppm. The sampling frequency for both chloride and fluoride analysis was increased to a four (4) hour interval. RCS chloride concentration reached a maximum of .32 ppm. Reactor Coolant Sys-tem purification was initiated through "B" cation demineralizer.

Fluoride concentration returned to within specification at 1200

, on 14 April 1980. Chloride concentration returned to within specification at 1600 on 14 April 1980.

Designation of Apparent Cause:

The apparent cause of this event is attributed to the chloride and fluoride contamination on the walls and floor of the fuel transfer canal, occurring during refueling flooding operations.

Analysis of Occurrence:

There uas no hazard created for the plant or the general public as a result of this event.

Corrective Action:

An engineering evaluation will be conducted to determine the effects of this event on the structural integrity of the R3 actor Coolant System prior to entering Mode 4.

Failure Data:

This is the third occurrence of this type reported under this specification. Reference LER 79-23 and 67.  ;

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