Control room temperature survey at a pressurized water reactor nuclear power station

During preoperational testing at a near term operating license (NTOL) pressurized water reactor power facility, numerous printed circuit board failure and out of calibration instrument loops have been encountered. This, coupled with licensee event reports filed by other operating stations, I. and E. notices, etc., prompted the utility to conduct a survey of various control panels and logic racks in the control room to determine operating temperatures. The completion of all activities associated with this survey are expected to result in longer qualified life for components, less time expended on calibration activities, and more reliable instrument loop indication and operation. This paper discusses the testing methodology and preliminary work performed to give the best possible results