The release of cooling water from the divertor, first wall, or blanket cooling system into the vacuum chamber during plasma operation is a coolant ingress accident. Once inside the chamber, this coolant will enter the plasma, causing a density limit disruption. We have analyzed this accident for ITER with the DSTAR code. Two neutral transport treatments were used in studying this accident: a 1 1/2D diffusion approximation, and a 2D fluids solution; both gave comparable results. Our findings are that this event could increase the rate of plasma current decay during a disruption by two to three times that being proposed as an ITER reactor design guideline.