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In response to the Fukushima accident the Research Centre Rez plans to simulate accident scenarios of NPP Temelin and NPP Dukovany analyzed in the stress tests ordered by the European Commission to all European NPPs. While in a number of safety analysis of various accident scenarios it is sufficient to use one point reactor kinetics there are selected types of accidents in which it is useful to model the space (3D) behaviour of neutron kinetics, in particular control rod ejections, boron dilution scenarios, including transitions from design basis to beyond design basis accidents. For example in order to analyse control rod ejections, boron dilution scenarios and local changes of moderator temperature one has to see the local changes (3D) of reactivity and power. In this paper the current model of VVER1000/V320 reactor created in PARCS 3.2 is benchmarked with MCNP6 code and some reference data from NPP Temelin. The geometry of fuel in the core used for the analyses comes from fuel assemblies of NPP Temelin (hexagonal shape). This benchmark may serve as one of validation tests of the PARCS code for VVER1000/V320.

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