[en] The material property data on thermal annealing of reactor-pressure-vessel steels have been reviewed. The most-critical materials are high copper welds; the data indicate that close to full recovery of Charpy V-notch properties can be realized by annealing at 850⁰F for 1 week (168 hours). However, the variability and sparcity of annealing recovery data dictate appropriate surveillance and experimental test programs. Of particular concern are the actual fracture-toughness changes and the differences between test- and power-reactor conditions. A survey of pressurized-water-reactor vendors, architect engineers, and consultants has been performed to assess the feasibility of performing a thermal-annealing cycle to restore the beltline material properties to their original state. This survey also addressed the issue of whether or not an actual annealing demonstration should be performed. It is the consensus view of the industry that in-situ reactor-vessel annealing can be done, but several areas still need to be studied and the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code guidelines need to be defined