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

Statement of responsibility on title page reads: Y. Huang, N. Siu, D. Lanning ,and J. Carroll"June 1990."Includes bibliographical references (leaf 11)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.Supported by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission NRC-04-89-35

Systems model for dynamic human error during accident sequences

Statement of responsibility on title page reads: Y. Huang, N. Siu, D. Lanning, J. Carroll, and V. Dang"December 1991."Includes bibliographical references (pages 153-155)Final report: "A systems model for dynamic human error during accident sequences"This report describes a systems-based operating crew model designed to simulate the behavior of an nuclear power plant control room crew during an accident scenario. This model can lead to an improved treatment of potential operator-induced multiple failures, since it deals directly with the causal factors underlying individual and group behavior. It is intended that the model, or more advanced developments of the model, will be used in the human reliability analysis portion of a probabilistic risk assessment study, where careful treatment of multiple, dependent failures is required. The model treats the members of the control room crew as separate, reasoning entities. These entities receive information from the plant and each other, process that information, perform actions that affect the plant, and provide information to the other crew members.The information retrieval, processing, and output activities are affected by the characteristics of the individual operator (e.g., his technical ability) and his relationship (measured in terms of "confidence level") with his fellow operators. Group behavior is modeled as the implicit result of individual operator behavior and the interactions between operators. The model is applied towards the analysis of steam generator tube rupture (SGTR) accidents at a non-U.S. pressurized water reactor, using the SIMSCRIPT 11.5 programming language. Benchmark runs, comparing the model predictions with videotaped observations of the performances of three different crews during SGTR training exercises, are performed to tune a small number of model parameters. The tuned model is then applied in a blind test analysis of a fourth crew. In both the benchmarking and blind test runs, the model performs quite well in predicting the occurrence, ordering, and timing of key events.The model is also employed in a number of sensitivity analyses that demonstrate the robustness of the model (it generates plausible results even when the model parameters are assigned values not representative of observed crews) and the model's usefulness in investigating key issues (e.g., the effect of stress buildup on crew performance). iSupported by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission: NRC-04-89-35

Improving negotiators' cognitions

Includes bibliographical references (p. 33-36).HD28 .M414 no.3116-, 90,

A cognitive-process analysis of taxpayer compliance

"Prepared for the Symposium on Taxpayer Compliance Research, National Academy of Sciences, South Padre Island, Texas, January, 1986."HD28 .M414 no.1739-, 85,

Organizational learning activities in high hazard industries : the logics underlying self-analysis

Cover title. "A version of this paper was presented under the title "Failures to Learn from Experience: An Analysis of Incident Reviews in Nuclear Power Plants and Chemical Process Plants" in the Symposium "High States Learning: Making Sense of Unusual, High-Hazard Events" at the Academy of Management meetings, Cincinnati, August, 1996."--p. 33.HD28 .M414 no.3936-97,

The organization and management of nuclear power plants

Includes bibliographical references (p. 36-44).HD28 .M414 no.3118-, 90,

Management research on outages and maintenance

HD28 .M414 no.3580-93,

The MIT International Program for Enhanced Nuclear Power Plant Safety : organization and management in the nuclear power industry

by John S. Carroll, Constance Perin, Alfred A. Marcus.HD28 .M414 no.3435-, 92,