Calculation of Instrument Loop Errors in Special Safety Systems of CANDU Reactors: A Statistical Approach
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Abstract
Allowances made in Nuclear Safety Analysis for CANDU reactors Special Safety Systems consider expected instrument loop errors. As utilities accumulate more operational experience and more insight on the behaviour of instrumentation in the specific stations environmental conditions, station staff are able to validate allowances used in the Safety Analysis. This paper describes a statistical method for drift data analysis of the different types of errors attributed to instrumentation and the approach used to determine total instrument loop errors in safety systems at Bruce A and B NGS. While the exercise is still in progress, this paper provides a summary of findings to date, together with recommendations on issues to be considered in the events where a need to reduce errors was identified.
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