ML20084M145

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AO 4-73-3:on 730509,during Initial post-core Loading Heatup of Rcs,Rhr Pump 4A Began Leaking.Vendor Representative on Site to Assist in Determining Cause.Followup Rept to Be Submitted When Cause & Corrective Action Known
ML20084M145
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 05/18/1973
From: Schmidt A
FLORIDA POWER & LIGHT CO.
To: Oleary J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084M139 List:
References
AO-4-73-3, NUDOCS 8306020014
Download: ML20084M145 (2)


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P.O. BOX 3100 / MI AM1, FLGAIDA 33101

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%"b FLORIDA PC'AER '4 tlGHT CO'.?ANY Turkey Point Plant May 18, 1973

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Mr. John F. O' Leary, Director Directorate of Reactor' Licensing f;

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TURKEY POINT UNIT No. 4

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DOCKET No. 50-251

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M ABNOMIAL OCCURRENCE NO. 4-73-3 gg W' N

4A RHR PUMP LEAKAGE

Dear Mr. O' Leary:

This report is. submitted in accordance with Technical Specification 6.6.2(a) and in amplification of Mr. J. K. Hays' telephone notification to Mr. R. C. Lewis, Region II, Directorate of Regulacory Operations on May 10, 1973.

During initial post core loading heatup of the Reactor Coolant System at 2:50 PM, May 9, 1973, with RCS temperature about 440'F and RCS pressure about 800 psi, i

the 4A RHR pump began leaking reactor coolant along the pump shaft at a rate estimated visually at 5 gallons per minute and calculated later at 6 to 7 gallons t

per minute. At that time, the RHR System was isolated from the RCS System with only RUST head on the system and with neither RHR pump in operation.

i The immediate corrective action consisted of closing MOV-4-862B. This valve is one of two motor operated valves in series in the combined suction line for both RHR pumps. Attampts were then begun to close valve 4-752A, the manual isolation valve on the suction of the 4A PJIR pump, so MOV-4-862B could be reopened and an RHR flow path restored through the 4B RHR pr.mp.

However, valve 4-752A would close. This failure is Abnormal Occurrence No. 4-73-5 and is reported completely in a separate letter.

Af ter valve 4-752A was disassembled and reassenbled in the closed position, the RHR pump was removed, disassembled and inspected to determine the cause of the leak. A vendor representative is on site to assist in deternining the cause of the leak. A followup report will be submitted when the cause and corrective action is knosm.

The pump leakage is an Abnormal Occurrence, as an al$ normal degradation of a bound-ary designed to contain fission products. However, because the reactor had not yet been critical, no fission products were present in the RCS. This, was verified by sampling in accordance with Technical Specifications. Hence, no radioactivity

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,4 Mr. John F. O Leary, Director May 18, 1973 y,

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was released through the break.

If the RCS had contained fission products, they would have been contained in the radioactive drain system which would have been monitored and processed, prior to release to the environment, in accordance with plant procedures. The health and safety of the public was not affected by this occurrence.

Very truly yours, e

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I A. D. Schmidt Director of Power Resources ADS:DWJ:jw cc: Norman C. Moseley, Director Region II, Directorate of Regulatory Operation U. S. Atomic Energy Commission Suite 818, 230 Peachtree Street, N. W.

Atlanta, Georgia Mr. G. A. Olson Edison Elcetric Institute 90 Park Avenue New York, N. Y.

10016 D. W. Jones J. W. Williams, Jr.

J. B. Olmstead S. G. Brain Plant Supervisors Plant Nuclear Safety Committee Documentary Files Dr. James Coughlin J. R. Bensen W. H. Rogers, Jr.

G. E. Liebler J. K. Ilays C. E.. Branning w-4