Guidelines for the verification and validation of expert system software and conventional software: Volume 4, Evaluation of knowledge base certification methods. Final report

Technical Report · Mon May 01 04:00:00 EDT 1995

OSTI ID:80896

Miller, L A; Hayes, J E; Mirsky, S M ^[1]

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1. Science Applications International Corp., McLean, VA (United States)

Objective is the formulation of guidelines for the V&V of expert systems for use in nuclear power applications. This activity is concerned with the development and testing of various methods for assuring the quality of knowledge bases. The testing procedure used was that of behavioral experiment, the first known such evaluation of any of V&V activity; the value lies in the capability to provide empirical evidence for or against the effectiveness of plausible methods in helping people find problems in knowledge bases. The three-day experiment included 20 participants from three nuclear utilities, the Nuclear Regulatory Commission`s Technical training Center, University of Maryland, EG&G Idaho, and SAIC. The study used two real nuclear expert systems: a boiling water reactor emergency operating procedures tracking system and a pressurized water reactor safety assessment systems. Ten participants were assigned to each of the expert systems. All participants were trained in and then used a sequence of four different V&V methods selected as being the best and most appropriate. These methods either involved the analysis and tracing of requirements to elements in the knowledge base or direct inspection of the knowledge base for various kinds of errors. Half of the subjects within each system group used the best annual variant of the V&V methods (the control group), while the other half were supported by the results of applying real or simulated automated tools to the knowledge bases (the experimental group). The four groups of participants were similar in nuclear engineering and software experience characteristics. It is concluded that the use of tools in static knowledge base certification results in significant improvement in detecting all types of defects, avoiding false alarms, and completing the effort in less time. The simulated knowledge-checking tool, based on supplemental engineering information about the systems, was the most effective.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Science Applications International Corp., McLean, VA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States); Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 80896
• Report Number(s): EPRI-TR--103331-V4
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
CERTIFICATION
EXPERT SYSTEMS
KNOWLEDGE BASE
NUCLEAR ENGINEERING
NUCLEAR INDUSTRY
QUALITY ASSURANCE