One-velocity treatments of thermal neutron transport have proved inadequate whereas multigroup methods may be so time consuming as to become impractical. The few thermal group calculations investigated here lie between these extremes. Few group calculations in typical power peaking and control rod worth studies are found to be both rapid and accurate, particularly when the rods are represented by boundary conditions. Boundary conditions for use with the P-3 and double P-1 approximations are derived and discussed.