Can we quantify human reliability in Level 2 PSA?

PSAM 2014 - Probabilistic Safety Assessment and Management

Volumn , Issue , 2014, Pages

  Raganelli, Lavinia ^a,b   Kirwan, Barry ^c  

^a IMPERIAL COLLEGE LONDON   (United Kingdom)

^b Corporate Risk Associ ^*  (United Kingdom)

^c EUROCONTROL EXPERIMENTAL CENTRE   (France)

Author keywords

Human Factors; Level 2; PRA; Uncertainty

Indexed keywords

ACCIDENTS; HUMAN ENGINEERING;

ACCIDENT SCENARIOS; EMERGENCY OPERATING PROCEDURES; HUMAN RELIABILITY ASSESSMENTS; LEVEL 2; PRA; REGULATORY ORGANIZATIONS; SEVERE ACCIDENT MANAGEMENT GUIDELINES; UNCERTAINTY;

RELIABILITY ANALYSIS;

EID: 84925064275     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. IAEA (2010) Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants, Vienna, Austria
2. IAEA (2009) "Severe Accident Management Programmes for nuclear power plants", Vienna Austria
3. V. N. Dang, G. M. Schoen, B. Reer (2009) "Overview of the Modelling of Severe Accident Management in the Swiss Probabilistic Safety Analyses" ISAMM 2009, October 26-28, 2009 Böttstein, Switzerland
4. Bye, A., Lois, E., Dang, V., Parry, G., Forester, J., Massaiu, S., Boring, R, Braarud, P., Broberg, H., Julius, J., Männistö, I. and Nelson, P. (2012) "International HRA Empirical Study - Phase 2 Report Results from Comparing HRA Method Predictions to Simulator Data from SGTR Scenarios." NUREG IA-0216 Vol 2, USNRC, Washington DC 20555.
5. E. Raimond et al (2013) ASAMPSA2 "Best-Practices Guidelines For Level 2 PSA Development And Applications", April 2013
6. M. L. Ang, N. E. Buttery (1997), "An approach to the application of subjective probabilities in level 2 PSAs" Reliability Engineering & System Safety, Vol 58, pages 145-156, November 1997
7. Martin Richner (2006) "Modelling of SAMG operator actions in Level 2 PSA" PSAM-8, May 2006, New Orleans, USA
8. th November, Cape Canaveral: USA
9. "Manual for the DORRET technique" Vectra Report No. 1005-215-TD01. Revision 1. October 1997.
10. Kirwan, B., Gibson, H., Kennedy, R, Edmunds, J., Cooksley, G., and Umbers, I. (2004) "Nuclear Action Reliability Assessment (NARA): A data-based HRA tool. In Probabilistic Safety Assessment and Management" 2004, Spitzer, C, Schmocker, U., and Dang, V.N. (Eds.), London, Springer, pp. 1206-1211