The experience of severe accidents shows that reliable determination of technological process parameters is necessary but not always sufficient to avoid catastrophic consequences. The accident measures should be considered in a broader context that includes the human factor, organization of the nuclear technology, external influences, and safety culture. The anticipated transient without scram (ATWS) events were not considered in the original water water energy reactor (WWER) (Russian pressurized water reactors (PWR)) design basis accidents (DBA). The design extension conditions (DEC) scenarios progress in a context which is very uncertain and highly stressful for the operators. If a specific scenario requires some operators' actions as measures to mitigate, delay, or distribute the accident consequences, then the dynamics of accident context seem of primary importance for “best estimate” evaluations and enhancing the plant's capability. The paper presents the capacities of the performance evaluation of teamwork (PET) procedure for enhancing plant's capability for DEC based on best estimate context evaluation of human performance in ATWS events. The PET procedure is based on a thorough description of symptoms of various timelines and their context quantification. It is exemplified for different ATWS scenarios of the nuclear power plant (NPP) with WWER-1000 based on thermal-hydraulic simulations with RELAP5/MOD3.2 code and models.
Skip Nav Destination
Article navigation
April 2018
Research-Article
Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
Gueorgui I. Petkov
Gueorgui I. Petkov
Search for other works by this author on:
Gueorgui I. Petkov
1Corresponding author.
Manuscript received September 30, 2016; final manuscript received December 22, 2017; published online March 5, 2018. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Apr 2018, 4(2): 020905 (11 pages)
Published Online: March 5, 2018
Article history
Received:
September 30, 2016
Revised:
December 22, 2017
Citation
Petkov, G. I. (March 5, 2018). "Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 020905. https://doi.org/10.1115/1.4039000
Download citation file:
Get Email Alerts
Cited By
Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
ASME J of Nuclear Rad Sci (April 2025)
Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Setup of the Supercritical CO 2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System
ASME J of Nuclear Rad Sci (July,2018)
Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
ASME J of Nuclear Rad Sci (April,2018)
Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
ASME J of Nuclear Rad Sci (April,2021)
Related Proceedings Papers
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
A PSA Update to Reflect Procedural Changes (PSAM-0217)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)