The purpose of this paper is to identify the Neutral Beam Injection (NBI) parameters for a system on a Next Step reactor, optimised for ignition and burn control, rather than current drive. As a main model we use the ITER-EDA concept in its 1993 version (R0 = 7.75m, Ip = 25MA, BT = 6T, a = 2.8m, k = 1.6). The dependence of the 'minimum power to ignite ITER-EDA' on beam energy, beam geometry and beam isotope species is investigated for a plasma, which conforms to Rebut LaBia-Watkins transport in time dependent simulations. It is found that deuterium beams with an energy of 400keV or above in a geometry with tangency radius (RT) approximately half the major radius, are sufficient for efficient ignition. The beam simulation results are compared with simulations using an idealised heating scheme. Sensitivity of the results to variations in plasma behaviour are investigated. Impurities, particle confinement, energy confinement and the H-mode threshold are factors which influence the power required for ignition significantly, but have little effect on the choice of beam energy and geometry. Considerations with respect to loss of fast particles led us to adopt a beam geometry with RT ~ 1/2R0 (very similar to that of JET), rather than perpendicular injection. Finally it will be shown that burn control using NBI is possible on ITER-EDA in sub-ignited regimes.