Implementation of a dynamic PRA approach for the prediction of operator errors during abnormal nuclear power plant events

9th International Conference on Probabilistic Safety Assessment and Management 2008, PSAM 2008

Volumn 2, Issue , 2008, Pages 1006-1014

  Coyne, Kevin ^a   Mosleh, Ali ^a  

^a UNIVERSITY OF MARYLAND   (United States)

Author keywords

Dynamic PRA; IDAC; Information perception; Performance influencing factors

Indexed keywords

DISCRETE DYNAMIC EVENT TREES; IDAC; INFORMATION PERCEPTION; MAN-MACHINE INTERACTION; PERFORMANCE INFLUENCING FACTORS; PROBABILISTIC RISK ASSESSMENT; STATIC AND DYNAMIC PERFORMANCE; THERMAL-HYDRAULIC MODEL;

APPLICATION PROGRAMS; BEHAVIORAL RESEARCH; DECELERATION; FORECASTING; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; RISK ASSESSMENT; SAFETY ENGINEERING;

ERRORS;

EID: 84876484070     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (7)

1. NUREG, "A Technical Basis and Implementation Guidelines for a Technique for Human Event Analysis (NUREG-1624)," U.S. Nuclear Regulatory Commission, Washington, DC NUREG-1624, 2000.
2. Y. H. Chang and A. Mosleh, "Cognitive modeling and dynamic probabilistic simulation of operating crew response to complex system accidents - Part 1: Overview of the IDAC Model," Reliability Engineering & System Safety, vol. 92, pp. 997-1013, 2007.
3. A. Mosleh and Y. H. Chang, "Model-based human reliability analysis: prospects and requirements," Reliability Engineering and System Safety, vol. 83, pp. 241-253, 2004.
4. "RELAP5/MOD3 CODE MANUAL," U.S. Nuclear Regulatory Commission NUREG/CR-5535 (INEL-95/0174), 1995.
5. Y. H. Chang, K. Coyne, and A. Mosleh, "A Nuclear Plant Accident Diagnosis Method to Support Prediction of Errors of Commission," presented at American Nuclear Society Nuclear Plant Instrumentation, Control and Human-Machine Interface Technology Conference (NPIC & HMIT 2006), Albuquerque, New Mexico, 2006.
6. Y. H. Chang and A. Mosleh, "Cognitive modeling and dynamic probabilistic simulation of operating crew response to complex system accidents - Part 2: IDAC performance influencing factors model," Reliability Engineering & System Safety, vol. 92, pp. 1014-1040, 2007.
7. NRC, "Task Action Plan item I.D.2 - Safety Parameter Display System," US Nuclear Regulatory Commission Generic Letter 89-06, 1989.