Human Performance Characterization in theReactor Oversight Process (NUREG/CR-6775, INEEL/EXT-01-01167)
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Publication Information
Manuscript Completed: September 2001
Date Published: September 2002
Prepared by:
David I. Gertman, Bruce P. Hallbert, David A. Prawdzik
Idaho National Engineering and Environmental Laboratory
P.O. Box 1625
Idaho Falls, Idaho 83415-3129
Eugene A. Trager, NRC Program Manager
J. Kramer, NRC Technical Monitor
Prepared for:
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code E8238
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Abstract
A review of the Reactor Oversight Process (ROP) and its characterization of human performance was performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to describe the means by which the Nuclear Regulatory Commission (NRC) monitors, analyzes and feeds back information on human performance. Review of detailed human performance findings and trends observed in 37 operating events identified through the Accident Sequence Precursor (ASP) program served as the sample of operating experience. All events reviewed had a conditional core damage probability of 1.0E-5 or greater and indicated the influence of human performance. Reviews also considered Individual Plant Examinations (IPEs) and Augmented Inspection Team (AIT) reports. These reviews were then compared to ROP source materials. The ROP source materials included SECY-99-007/007A, SECY-00-0049, NRC manual chapters and inspection procedures, inspection and supplementary inspection reports, plant issues matrices (PIMs) risk-informed inspection notebooks, and the Significance Determination Process (SDP) for Operator Requalification. Insights regarding the characterization of human performance in the ROP are presented.
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