ML20087A905
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g UNITED STATES ATOMIC ENERGY COMMISSION
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W ASHINGTON, D.C.
20545 a
October 19, 1970 N
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-1 R. T. Carlson, Senior Reactor Inspector i
Region I, Division of Compliance 1
ASSIST INSPECTION - OYSTER CREEK TURBI!E CONTROL SYSTEM MAIEUNCTION DOCKET No. 50-219 Enclosed is a report of an assist inspection conducted at the subject facility by W. S. Farmer to obtain information on the performance of the turbine inlet and bypass valve control systems.
The results of recent scrams and cyclic behavior of the turbine inlet valve were reviewed with representatives of G-E and Jersey Central.
The licensee concluded that dirt in the hydraulic system and an incor-rect turbine inlet valve cam profile were the main causes for the turbine j
inlet valve control difficulties.
l There have been several recent incidents of transients in boiling water reactors. Many of these are related to difficulties in either the turbine control system or feedwater control system. Problems such as those above at Oyster Creek can lead, if uncorrected, to similar inci-dents. Since the same type of turbine and bypass valve control system used at Oyster Creek is also used by G-E on the Nine Mile Point, Mill-stone, Monticello, Vermont Yankee, and Boston Edison plants, the experience at Oyster Creek has genaric significance.
It was our understanding from the meeting at Oyster Creek with the G-E personnel that corrective action had been taken by installing additional filters in the hydraulic system and the later supply of new cams. They stated that they are also providing new turbine inlet valve cams for the Niagara Mohawk plant and are reviewing others in the generic list' above. The hydraulic oil filter installation was stated not to be identical at these various plants.
Based on the number of problems and span of time during which Jersey Central has experienced troubles with the Oyster Creek 1 turbine inlet valve control system, we recommend continued close surveillance by Compliance. Since the epr has displayed unstable behavior at higher powers, we would suggest that performance on any future extended power increases be especially noted.
9508070217 950227 PDR FOIA D.EKOK95-36 PDR
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.6 R. T. Carlson October 19, 1970 During the course of this inspection the failure of a link in the bypass valve mechanical actuation system was discussed. Additional information is to be made available in the future by G-E after further evaluation.
We would like to obtain as much information as possible on their findings, since this failure would lead to one of the limiting transients covered l
in the FSAR and would also have generic implications.-
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. Denton, C f.'
Technical Suppo t Branch Division of Compliance Enclosure :
JC Assist Inspection Rpt cc w/ enc 1:
A. Giambusso L. Kornblith R. H. Engelken J. P. O'Reilly 6
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