This paper discusses the calculation of the IAEA benchmark entitled In-core fuel management code package validation for WWERs (IAEA-TECDOC-847) with the Version5 code system (DRAGON and DONJON). Calculations were performed for VVER-1000 cores. Cell calculations are done with DRAGON. Core calculations are done with DONJON, using CLE-2000 procedures to determine the reactor state at each depletion step, taking into account the control rod insertion pattern, reactor power, coolant inlet temperature and coolant mass flow. A multi-variate cross-section database for the core calculations is made with DRAGON. Calculated results are the critical boron concentration at each depletion step, and axial and radial power profiles at a few depletion steps. The present work serves as a feasibility study for the application of DRAGON and DONJON to VVER cores, and results are generally acceptable. Suggestions are made to improve the quality of the simulations.