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EPR risk-informed activities at IRSN



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Titre du congrès :PSA 2008 - International Topical Meeting on Probabilistic Safety Assessment and Analysis
Ville du congrès :Knoxville
Date du congrès :07/09/2008

Type de document > *Congrès/colloque

Mots clés > EPS, nouveaux réacteurs, risk-informed, RPE

Unité de recherche > IRSN/DSR/SESPRI/BEPS

Auteurs > CORENWINDER François, EVRARD Jean-Michel, GEORGESCU Gabriel

Date de publication > 11/09/2008


For EPR Reactor, the PSA was developed from the beginning of the design by the reactor designer (AREVA). This PSA was used for early design verification, several design improvement being defined based on these PSA insights and following the discussions with the French and German safety authorities. Now, in the frame of the construction and licensing of Flamanville 3 NPP (FLA3) the PSA is playing an important role for the EPR Project assessment by IRSN, as the French Safety Authority (ASN) technical support organization. In this context, both the plant operator (EDF) and IRSN are developing and using PSA and PSA applications. PSA is used firstly for the verification of the plant safety level, since the -Technical Guidelines- for EPR require that the probabilistic approach should be used in order to show the achievement of a significant reduction of the global core melt frequency comparing with the existing NPPs. The PSA is used to support the demonstration of -practical elimination- of the large early releases, equally requested by the -Technical Guidelines-. The PSA is involved in the verification of the completeness of the deterministic multiple failure situation (Risk Reduction Categories) features. Furthermore, PSA applications are used by IRSN for the design verification, mainly the I&C architecture and electrical power supply systems design, as well as in the frame of the verification of the plant Technical Specifications, in the frame of the verification of the planned preventive maintenance and it contributes to the verification of the accident procedures.