Initial quantification of human error associated with specific instrumentation and control system components in licensed nuclear power plants

This report provides a methodology for the initial quantification of specific categories of human errors made in conjunction with several instrumentation and control (I and C) system components operated, maintained, and tested in licensed nuclear power plants. The resultant human error rates (HER) provide the first real systems bases of comparison for the existing derived and/or best judgement equivalent set of such rates or probabilities. These calculated error rates also provide the first real indication of human performance as it relates directly to specific tasks in nuclear plants. This work of developing specific HERs is both an extension of and an outgrowth of the generic HERs developed for safety system pumpc and valves as reported in NUREG/CR-1880.