HUMAN RELIABILITY ANALYSIS FOR COMPUTERIZED PROCEDURES

Conference · Thu Sep 01 00:00:00 EDT 2011

OSTI ID:1027908

Boring, Ronald L; Gertman, David I; Blanc, Katya Le

This paper provides a characterization of human reliability analysis (HRA) issues for computerized procedures in nuclear power plant control rooms. It is beyond the scope of this paper to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper provides a review of HRA as applied to traditional paper-based procedures, followed by a discussion of what specific factors should additionally be considered in HRAs for computerized procedures. Performance shaping factors and failure modes unique to computerized procedures are highlighted. Since there is no definitive guide to HRA for paper-based procedures, this paper also serves to clarify the existing guidance on paper-based procedures before delving into the unique aspects of computerized procedures.

• Research Organization: Idaho National Laboratory (INL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1027908
• Report Number(s): INL/CON-11-22469
• Conference Information: Annual Meeting of the Human Factors and Ergonomics Society,Las Vegas, NV,09/19/2011,09/23/2011
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS
computerized procedures
control room
CONTROL ROOMS
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
human reliability analysis
nuclear power plant
NUCLEAR POWER PLANTS
PERFORMANCE
RELIABILITY