Abstract
Abstract This note presents a calculation and discussion of the probability of operator failure to inject boron with the standby liquid control (SLC) system during an anticipated transient without scram (ATWS) at a boiling water reactor (BWR). Calculated results are compared to the value used in some past risk assessments, as well as with the estimated SLC hardware unavailability, to determine if the assertion that the SLC hardware unavailability dominates the human error probability is reasonable. The sensitivity of this calculation to the value used for the suppression pool heat capacity temperature limit is also examined.
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