[en] As a continuation of the earlier presented work, an additional computational analysis of the WWER-1000 fuel rod behaviour under hypothetical large break LOCA conditions was carried out applying reasonably maximum conservative initial and boundary conditions. The same multi-stage approach was used, consisting of: (1) a four-year neutron-physical core simulation and selection of fuel rods, without Gd (FRs, no-Gd FRs) and with Gd burnable absorber (Gd-FRs) with the highest linear heat rate (LHR) and burnup achieved before the hypothetical accident start; (2) thermal-hydraulics simulation of the primary system large break LOCA accident and extraction / preparation of boundary conditions (LHR, coolant temperature and pressure, cladding surface temperature, etc., along the cooling channel) applying the RELAP5/MOD3.3 code, and (3) steady-state and accident thermal-mechanical analysis of the selected fuel rods using the extracted boundary conditions, by means of the TRANSURANUS code. Taking into account the new requirement for a reasonably maximum conservative analysis all selected fuel assemblies (FAs), fuel rods (FRs and Gd-FRs), LOCA simulations and boundary conditions generation were carefully prepared to fulfil this goal. Based on preliminary series of calculations, seven FRs and two Gd-FRs, with the highest LHR and burnup achieved in the course of two model four-year cycles, have been selected and analysed with the TRANSURANUS code. The calculated results were compared to the limiting values of the acceptance criteria for LOCA. The influence of some TRANSURANUS cladding mechanical parameter variation leading to more conservative results has been studied and a new more realistic RELAP5/MOD3.3 / TRANSURANUS boundary condition approach was applied and compared to the more conservative base variant. (authors)