ML20084M353

AO 3-73-1:on 730106,RCS Loop B Bypass Loop Flow Transmitter Began Leaking.Cause Undetermined.Transmitter Replaced

ML20084M353
Person / Time
Site:	Turkey Point
Issue date:	01/15/1973
From:	Schmidt A FLORIDA POWER & LIGHT CO.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084M354	List: ML20084M353
References
AO-3-73-1, NUDOCS 8306020114
Download: ML20084M353 (2)

Text

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.lYS N 7-1 Turkey Point Plant ik %{U$1h-4 he, Januarf 15, 1973

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r3 7g Mr. John F. O' Leary, Director Division of Reactor Licensing U. S. Atomic Energy Comission Washington, D. C. 20545

'IURKEY POINT UNIT NO. 3 DOCKET NOS. 50-250 AND 50-251 ABSORMAL OCCURRENCE NO. 3-73-1

Dear Mr. O' Leary:

H7 This report is submitted in accordance with Technical Specification 6.6.2 a and supplements Mr. J. K. Ilays' telephone notification to

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Mr. R. C. Lewis, Region II, Directorate of Regulatory Operations at 6 8:15 PM, January 6, 1973.

N At approximately 1:46 #!, January 6, 1973, while Unit 3 was at ap-75 proximately 30% (200 MKe) power, the Loop B Reactor Coolant System gd.' RTD Bypass Loop ficw transmitter, FSAR Figure 4.2-1, FT-3-491, (ITT Barton Model '290A Differential Transmitter, 0-600 inch 1120 range,

\fh serial 290A 1041) began leaking at.a rate of approximately 12 gpm.

The redundant leak detection systems functioned as designed to alert the operators to the condition. Immediate corrective action was taken and the transmitter was isolated at 2:23 AM, and then replaced.

The health and safety of the public was not affected in any way by the leakage because all contamination was confined within Unit 3 Containment. The maximum contamination measured in the vicinity of-2 the Icakage was 200,000dpm/1g0cm. Airborne particulate activity increased to a maximum of 10- PCi/cc. Gaseous activity did not change during the Icak. The Reactor Coolant System gross B-y activity during the leak was about 3.5 X 10-2 pCi/cc. No equipment was damaged by the leaking reactor coolant water or the resultant steam and the maximum personnel exposure was 150 mrem.

After finding the leaking Loop B RTD bypass loop flow transmitter, the Loop A and Loop C RTD bypass loop flow transmitters were checked.

It was found that Loop C bypass loop flow transmitter was Icaking around the flange screws. The transmitter was isolateu and rep] aced.

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Mr. John F. O' Leary Page 2 January 15, 1973 The cause of the failure has not been determined at this writing.

Westinghouse and the instnzment vendor are actively investigating the failure. _

We will advise you as soon as the investigation has been completed, and corrective action is determined.

A. D. Schmidt -

Director of Power Resources ADS:Dh'J/vy cc: Mr. John Davis, Director Region II, Directorate of Regulatory Operation U. S. Atomic Energy Commission

. Suite 218, 230 Peachtree Street, N. W.

Atlanta, Georgia Dr. James Coughlin J. R. Bensen W. H. Rogers , Jr.

Documentary Files G. E. Liebler J. K. Hays C. E. Branning D. W. Jones J. W. Williams, Jr.

Plant Nuclear Safety Committee J. B. Olmstead S. G. Brain Plant Supervisors 4