Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

Author:

Petkov Gueorgui I.1

Affiliation:

1. Independent Consultant, Volewijkshof 20, Amsterdam AH 1031, The Netherlands e-mail:

Abstract

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.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference17 articles.

1. Anticipated Transients Without Scram for WWER Reactors,1999

2. Model Validation for Units 5 & 6, Safety Analysis Capability Improvement of the Kozloduy NPP in the Field of Thermal Hydraulic Analysis,1999

3. Engineering Handbook, Safety Analysis Capability Improvement of KNPP (SACI of KNPP) in the Field of Thermal Hydraulic Analysis,2001

4. Petkov, G., and Furuta, K., 1998, “Application of PN-Based Method for Identification and Classification of Human Actions in NPP TLRS,” 4th International Conference on Probabilistic Safety Assessment and Management (PSAM 4), New York, Sept. 13–18, pp. 1136–1141.

5. Petkov, G., and Groudev, P., 1999, “Correlation Between Human and Material Shocks in Symptom-Based Emergency Procedures,” ASME-PVP Conference, Boston, MA, Aug. 1–5, pp. 25–35.

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