Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power plant

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A practical approach to develop a more realistic fault-tree model with a consideration of various conditions endured by a human operator is proposed. In safety-critical systems, the generation failure of an actuation signal is caused by the concurrent failures of the automated systems and an operator action. These two sources of safety signals are complicatedly correlated. The failures of sensors or automated systems will cause a lack of necessary information for a human operator and result in error-forcing contexts such as the loss of corresponding alarms and indications. It is well known that the error-forcing contexts largely affect the operator's performance. An automated system which consists of multiple processing channels and complex components is also affected by the availability of the sensors. This paper proposes a condition-based human reliability assessment (CBHRA) method in order to address these complicated conditions in a practical way. We apply the CBHRA method to the manual actuation of the safety features such as a reactor trip and auxiliary feedwater actuation in Korean Standard Nuclear Power Plants. Even the human error probability of each given condition is simply assumed, the application results prove that the CBHRA effectively accommodates the complicated error-forcing contexts into the fault trees. (c) 2005 Elsevier Ltd. All rights reserved.
Publisher
ELSEVIER SCI LTD
Issue Date
2006-06
Language
English
Article Type
Article
Citation

RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.6, pp.627 - 633

ISSN
0951-8320
DOI
10.1016/j.ress.2005.04.007
URI
http://hdl.handle.net/10203/92746
Appears in Collection
NE-Journal Papers(저널논문)
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