Application of a Software tool for Evaluating Human Factors in Accident Sequences
Creators
- 1. Department of Energy Systems of the Polytechnic University of Madrid (DSE-UPM) c/ Rios Rosas 21. 28003 Madrid (Spain)
- 2. Departamento de Optica, Escuela Universitaria de Optica, Universidad Complutense de Madrid, C/ Arcos de Jalon s/n, 28037 Madrid (Spain)
- 3. Spanish Regulatory Commission (CSN), C/ Justo Dorado, 11 28040 Madrid (Spain)
- 4. OECD Halden Reactor Project (HRP), PO Box 173, N-1751 Halden (Norway)
Description
The Probabilistic Safety Assessment (PSA) includes the actions of the operator like elements in the set of the considered protection performances during accident sequences. Nevertheless, its impact throughout a sequence is not analyzed in a dynamic way. In this sense, it is convenient to make more detailed studies about its importance in the dynamics of the sequences, letting make studies of sensitivity respect to the human reliability and the response times. For this reason, the CSN is involved in several activities oriented to develop a new safety analysis methodology, the Integrated Safety Assessment (ISA), which must be able to incorporate operator actions in conventional thermo-hydraulic (TH) simulations. One of them is the collaboration project between CSN, HRP and the DSE-UPM that started in 2003. In the framework of this project, a software tool has been developed to incorporate operator actions in TH simulations. As a part of the ISA, this tool permits to quantify human error probabilities (HEP) and to evaluate its impact in the final state of the plant. Independently, it can be used for evaluating the impact of the execution by operators of procedures and guidelines in the final state of the plant and the evaluation of the allowable response times for the manual actions of the operator. The results obtained in the first pilot case are included in this paper. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-698-5
- Imprint Title
- Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
- Imprint Pagination
- 2734 p.
- Journal Page Range
- p. 950-959
Conference
- Title
- 2006 International congress on advances in nuclear power plants - ICAPP'06
- Dates
- 4-8 Jun 2006
- Place
- Reno - Nevada (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39042855
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; COMPUTER CODES; ERRORS; EVALUATION; HUMAN FACTORS; LICENSES; MANUALS; PERFORMANCE; PROBABILISTIC ESTIMATION; PROBABILITY; RECOMMENDATIONS; RELIABILITY; RISK ASSESSMENT; SAFETY; SAFETY ANALYSIS; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; DOCUMENT TYPES
Optional Information
- Notes
- 18 refs.