Integrating human reliability analysis approaches in the EPRI HRA calculator

Proceedings of the 8th International Conference on Probabilistic Safety Assessment and Management, PSAM 2006

Volumn , Issue , 2006, Pages

  Julius, Jeffrey A ^a   Grobbelaar, Jan F ^a  

^a Scientech LLC   (United States)

Author keywords

Human reliability analysis; Psa pra applications; Reliability; Risk informed regulation; Software tool

Indexed keywords

ELECTRIC POWER RESEARCH INSTITUTE; HUMAN ERROR PROBABILITY; HUMAN RELIABILITY ANALYSIS; LARGE EARLY RELEASE FREQUENCIES; MAINTENANCE SCHEDULES; PROBABILISTIC RISK; REACTOR OVERSIGHT PROCESS; RISK-INFORMED REGULATION;

COMPUTER AIDED SOFTWARE ENGINEERING; ERRORS; MAINTENANCE; MATHEMATICAL INSTRUMENTS; RELIABILITY; RISK ASSESSMENT; RISK MANAGEMENT; SAFETY ENGINEERING; SOFTWARE RELIABILITY; TOOLS;

RELIABILITY ANALYSIS;

EID: 84892642296     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. American Society of Mechanical Engineers, 2002-2005, Standard For Probabilistic Risk Assessment For Nuclear Power Plant Applications, ASME RA-S-2002, 2002 supplemented by American Society of Mechanical Engineers, Addenda to Standard For Probabilistic Risk Assessment For Nuclear Power Plant Applications, ASME RA-Sa-2003, 2003, and American Society of Mechanical Engineers, Addenda to Standard For Probabilistic Risk Assessment For Nuclear Power Plant Applications, ASME RA-Sb-2005, 2005, New York, New York.
2. US Nuclear Regulatory Commission, Regulatory Guide 1.200, 2004 An Approach For Determining The Technical Adequacy Of Probabilistic Risk Assessment Results For Risk-Informed Activities, US Nuclear Regulatory Commission, Washington DC.
3. American Nuclear Society, 2003, American National Standard - External Events PRA Methodology, ANSI/ANS-58.21-2003, American Nuclear Society, La Grange Park, Illinois.
4. Hannaman, G.W., and Spurgin, A.J., 1984, Systematic Human Action Reliability Procedure (SHARP), EPRI NP-3583, Electric Power Research Institute, Palo Alto, California.
5. Wakefield, D.J., Parry, G.W., Hannaman, G.W., and Spurgin, A.J., 1990, Systematic Human Action Reliability Procedure (SHARP1), EPRI NP-7183-M, Electric Power Research Institute, Palo Alto, California.
6. Spurgin, A.J., Moieni, P., and Parry, G.W, 1989, A Human Reliability Analysis Approach using Measurements for Individual Plant Examination, EPRI NP-6560L, Electric Power Research Institute, Palo Alto, California.
7. Parry, G.W, Spurgin, A.J., et al, 1992, An Approach to the Analysis of Operator Actions in Probabilistic Risk Assessment, EPRI TR-100259, Electric Power Research Institute, Palo Alto, California.
8. Swain, A.D., and Guttmann, H.E., 1983, Handbook of Human Reliability Analysis With Emphasis on Nuclear Power Plant Application, NUREG/CR-1278, US Nuclear Regulatory Commission., Washington, DC.
9. Swain, A.D., 1987, Accident Sequence Evaluation Procedure (ASEP) Program, NUREG/CR-4772, US Nuclear Regulatory Commission, Washington, DC.
10. EPRI HRA Calculator® Version 3.01, 2005, Apollo ID 1012902, EPRI, Palo Alto, California.