The stainless steel first wall of the Fusion Experimental Reactor (FER) needs protection against melting from the intensive heat load released during a plasma disruption. The guard limiter is proposed as an innovative first wall protection concept. The guard limiter is located slightly inside the plasma chamber beyond the first wall surface and it covers part of the first wall. It is modularized and each module is equipped with its own structural support and cooling system so that the replacement of a module is easy and reliable.The guard limiter of the FER consists of 12 inboard and 12 upper modules corresponding to the number of torus sectors. The upper modules can also be used as a ramp-up limiter. Both inboard and upper guard limiters can be replaced with straight motion through the interval between the TF coils. The coverage of the inboard limiter is only about 20% because its toroidal width is restricted by the narrow distance between TF coils, while a larger coverage is possible for the upper limiters. Replacement with vacuum-tight operation is possible for the inboard limiter by using a vacuum flask design.