Neutron shielding calculations for a 70- to 250-MeV proton cancer therapy facility have been carried out using the High Energy Transport Code and the one-dimensional discrete ordinates code ANISN. Calculations were performed for iron and water targets with incident proton energies of 150, 200, and 250 MeV. The angular dependence of the neutron spectrum was taken into account by averaging and reporting the spectrum in angular bins of 0 to 15, 15 to 30, 30 to 45, 45 to 60, 60 to 90, and 90 to 180 deg relative to the forward direction of the protons. Each of these various spectra was used as the source spectrum for an individual ANISN run in which the source was placed at the center of a sphere of typical concrete (i.e., density of 2.3 g/cm3) and the dose equivalent per proton was calculated as a function of radius. These calculations differ from previous work primarily in the method used to calculate the neutron spectrum due to the interaction of the protons with the target and the transport cross sections used in the ANISN calculations.