A preliminary design integration study of the Electron Cyclotron Heating and Current Drive, and Neutral Beam heating systems with the outboard Multi-Module blanket Segments in DEMO, is being presented. Scope of the work is to provide a first assessment on requirement analysis, concept generation and evaluation of the remote maintenance for a DEMO fusion power plant, in order to maximize its availability. The work has been divided into three phases: firstly, assessments to define the required openings for Electron Cyclotron and Neutral Beam launchers have been made. For the former, a Remote Steering concept has been considered, while for the latter a properly rescaled-ITER-like system has been taken into account. Secondly, CAD model of a DEMO sector has been modified to contain the port openings and a coarse port plug. Thirdly, a preliminary structural and electro-magnetic analysis has been carried out, considering two blanket concepts: Helium Cooled Lithium Lead and Helium Cooled Pebble Bed.