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Data analysis : operating crew characteristics and interactions during steam generator tube rupture simulation

Author(s)
Huang, Y. (Yuhao); Siu, N. O. (Nathan O.); Lanning, David D.; Carroll, John S., 1948-
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Massachusetts Institute of Technology. Department of Nuclear Engineering
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
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Abstract
This report provides an analysis of the data collected during a one-month visit to a 2-unit, non-U.S. PWR. The data consist of results from interviews (largely with plant operators and former shift engineers) and from reviews of videotapes covering crew responses to steam generator tube rupture training exercises. The interviews were aimed at indicating perceptions of individual and group skills. The analysis shows that the interview results are fairly consistent, that the time required to perform key actions does not generally correlate very well with the team quality ratings obtained from the interviews, and that the team quality ratings obtained from interviews correlate reasonably with ratings of the team performances (during the exercises) developed using the 7-dimension scale described in PNL-7250.
Description
Statement of responsibility on title page reads: Y. Huang, N. Siu, D. Lanning ,and J. Carroll
 
"June 1990."
 
Includes bibliographical references (leaf 11)
 
Date issued
1990
URI
http://hdl.handle.net/1721.1/90349
Publisher
Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1990
Series/Report no.
MITNE ; 290

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