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Bowman & Smith on NRC security programs
Greg Bowman and George Smith work for the Nuclear Regulatory Commission in implementing programs that deal with risk, whether to nuclear power plants or from nuclear materials, such as radiological sabotage and theft or diversion of materials. Bowman is the director of the NRC’s Division of Physical and Cybersecurity Policy in the Office of Nuclear Security and Incident Response. Smith is the senior project manager for security in the Source Management & Protection Branch of the Division of Materials Safety, Security, State, and Tribal Programs in the Office of Nuclear Material Safety and Safeguards.
The three initiatives Bowman and Smith discussed with Nuclear News editor-in-chief Rick Michal are the Insider Threat Program, the Cybersecurity Program, and the Domestic Safeguards Program.
Jinkyun Park, Wondea Jung, Jaewhan Kim, Jaejoo Ha
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 290-308
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT03-A3418
Articles are hosted by Taylor and Francis Online.
In complex systems, such as nuclear power plants (NPPs) or airplane control systems, human error has been regarded as the primary cause of many events. Therefore, to ensure system safety, extensive effort has been made to identify the significant factors that can cause human error. According to related studies, written manuals or operating procedures are revealed as one of the important factors, and the understandability is pointed out as one of the major reasons for procedure-related human errors.Many qualitative checklists have been suggested to evaluate emergency operating procedures (EOPs) of NPPs so as to minimize procedure-related human errors. However, since qualitative evaluations using checklists have some drawbacks, a quantitative measure that can quantify the complexity of EOPs is indispensable.From this necessity, Park et al. suggested the step complexity (SC) measure to quantify the complexity of procedural steps included in EOPs. To verify the appropriateness of the SC measure, averaged step performance time data obtained from emergency training records of the loss-of-coolant accident (LOCA) and the excess steam demand event were compared with estimated SC scores. However, although averaged step performance time data and estimated SC scores show meaningful correlation, some important issues such as determining proper weighting factors have to be clarified to ensure the appropriateness of the SC measure. These were not properly dealt with due to a lack of backup data.In this paper, to resolve one of the important issues, emergency training records are additionally collected and analyzed in order to determine proper weighting factors. The total number of collected records is 66, and the training scenarios cover five emergency conditions including the LOCA, the steam generator tube rupture, the loss of all feedwater, the loss of off-site power, and the station blackout. From these records, average step performance time data are retrieved, and new weighting factors are determined by using a nonlinear regression analysis. The results show that the SC scores quantified by the new weighting factors show statistically meaningful correlation with averaged step performance time data. Thus, it can be concluded that the SC measure can represent the complexity of procedural steps included in EOPs.