ML20084J276
| ML20084J276 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/15/1973 |
| From: | Ross D JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8305120379 | |
| Download: ML20084J276 (2) | |
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M ADISoN AVENUE AT PUNCH BOWL Ro AD e MoRRISToWN. N.J. 07960 e 539 6111 May 15, 1975
$1 Mr. A. Giariousso N,/
Deputy Director for Reactor Projects MD
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P Washington, D. C. 20545 MAY l U 197-P C l
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Dear Mr. Giambusso:
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Subject:
Oyster Creek Station 7,
Docket No. 50-219 Nv i Failure of Torus to Reactor Building Vacuum Relief Valve V-26-18 This event is considered to be an abnormal occurrence as j
Q defined in the Technical Specifications, Paragraph 1.15.F.
Notifica.
i tion of tinis event, as required by the Technical Specifications, Para-
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graph 6.6.B, was made to AEC Region I, Directorate of Regulatory Opera-
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y tions, on Friday, May 4, 1973.
i While performing local leak rate testing, it was found that l
one of the torus to reactor building vacuum breaker lines would not d]'
hold pressure between the isolation valves (V-26-17 6 18). The lack of j
air Icakage through check valve (V-26-17) indicated that the Icakage was f
through the butterfly valve (V-26-18).
l Details of the valve are as follows:
Air Operated Butterfly, Rockwell E
Size - 20" Rating - 150 psi Operator - Conoflow Corp.
Inspection of V-26-18 showed that the valve was 0.010 inches
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off the seat, indicating that the linkage on the valve arm required adj usttrent.
The valve was inspected and the boot seat and butterfly disc I
were found in good ~ condition. The valve was found to be 0.010 inches off the seat. The boot seat and butterfly disc were cleaned and the valve
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, i linka,ge was adjusted to position the zalve disc properly on the seat.
"The adjustment consisted of increasing the stroke in the close direction.
i The line between the isolation valves was then pressurized and the
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1eakage was calculated to be 0.492 SCFH well within the technical specifi-
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cation limit. The cause of the change in linkage adjustment has not been determined, t
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There was no safaty significance associated with this occurrence since the redundant component (check valve V-26-17) was shown to be Icakage tight. This is implied by the fact that the check valve was not j
moved during the testing period, so that the maximum possible Icakage through the check valve was 0.492 SCFH.
r To prevent a reoccurrence of this type problem, indicating marks were placed on the disc shaft.
Several operating tests will be perfonned prior to plant startup to verify repeatability of linkage and valve I
position based on these markings.
Also, additional leak rate measurements will be performed prior to plant startup to verify the adequacy of re-
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lying on these new markings to ensure the valve has closed properly i
following future operability surveillmice tests.
Very truly yours, i
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Donald A. Ross Manager, Nuclear Generatir.g Stations cs Enclosures (40) 6 f
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Mr. J. P. O'Reilly, Director
.j Directorate of Regulatory Op rations, Region 1 t
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