ML20084J675
| ML20084J675 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/24/1973 |
| From: | Ross D JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8305180649 | |
| Download: ML20084J675 (5) | |
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Subject:
Oyster Creek Station
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,J Docket No. 50-219
- s Isolation Condenser Valve Failurc This event is considered to be an abnormal occurrence as defined in k h/0) the Technical Specification, Paragraph 1.15.F.
g-During the weekly surveillance test of the "B" isolation condenser motor operated condensate return valvo V-14-35, a " breakaway from closed" O
motor current of 75 amps was observed. The high current continued for about 5 seconds whereupon the breaker was manually tripped. The reactor was in the cold shutdown cendition at the time of this test.
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Investigation is still in progress in an effort to determine the cause of this fcilure.
Ikwever, as was the case upon the previous failure on
. -7 December 29, 1972, the valvo disc was finally freed from its seat only upon
,d s applying considerabic torque to the operater handuhccl.
Once frec, the valvo' k
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was stroked with the motor operator to the fully opened, and then fully closed
-position several times without any difficulty. This valve had previously been b#
stroked successfully on sixtcon separato occasions' during the weekly survoillance
'T tests.
In all but one case, the reactor was operating at pressure and temper-U atures associated with full power operation.
In addition, during this period, the "B" isolation. condensor was actuated on one occasion to assist in maintain-ing plant pressure during a shutdown. The valve and operator data are as follows:
Valve Manufacturer: Anchor Size:
10" h' edge Gate i
Rating: 600 pounds Operator Manufacturer: Philadelphia Gear Company / Peerless lilectric-Operator Type: SNV Sizo 2 Motor Rating:
4.3 h.p. G 1900 rpm,125 volts DC, 35 amps f
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f ~.lll 27 %
$$Pi!88fo k g
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Mr. Giambusso April 24,1973 The requirements for at least one of the isolation condensers to act as a means of heat removal it detailed in Amendment 67 to the Oyster Creek FDSAR.
Since the "II" isolation condenser would not have been able to fulfill this requirc:.:ent, the significance of this event is that the isolation condenser systen would not have had its desi ;ned redundancy.
Both the va]ve nanufacturer and the associated operator nanufacturer have been contacted to aid in our investi;ation of this failure during our t
present outage.
Additional informatien will be forwarded to your office as soon as it becomes available.
Enclosed are forty (40) copies of this report.
Very truly yours,
O.+ L (It~f u l j'i~ &Li_
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Donald A. 11oss Manager, Nuclear Generating Stations DAR:cs linclosures (40) cc:
Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, llegion I I