The manganese sulphate bath is standardly used for primary standardization of dosimetry quantities of neutron radiation. To achieve results at the metrology level it is necessary to have the overall uncertainty of this method properly determine and possibly the contributing uncertainties minimized. Several parameters, which have impact on the overall uncertainty, were discussed and characterized in previous publications. Analysis presented in the paper is focused on the characterization of uncertainties induced by cross-section data, which contribute through the correction factor. Advances in computational methods and computational power shifted the calculation of correction factors among the standard steps of the manganese bath method what decrease an interest about this part of the method. Anyway, with the development of computational tools, the cross-section data were also improved, and new cross-section libraries include more information about the cross-section data uncertainties. Therefore, the propagation of uncertainties in neutron cross-section can be carried out within standard transport calculation of the manganese sulphate bath model. In this paper, the super-sequence SAMPLER module that implements stochastic techniques is used to assess the uncertainty in computed results. Reaction rates on all nuclides of the solution are computed in more than 200 cases with uncertain parameters and the results are evaluated by an auxiliary tool.