Control of liquid radioactive effluents from nuclear power plants in the Federal Republic of Germany

The early nuclear and water appropriation procedures for nuclear power plants provided release limits for liquid radioactive effluents expressed as total activity levels (without tritium) and tritium levels and/or concentration levels. This approach also determined the control methods to be applied. In the meantime, more detailed control methods and requirements were developed including a system of sampling of radioactive materials containing water, storing of the samples for providing evidence, performing total gammma and nuclide-specific measurements, and assessing the actual releases of radioactive materials in comparison with prescribed release limits. From this background, a safety guide on the liquid radioactive effluents was developed. It covers, in addition to radioactive waste water, plant service water, turbine building discharge and also the main cooling water. Within the framework of the guide, measurements for deciding on radioactive waste-water releases, the determination of the concentration of radioactive materials in releases, the nuclide-specific measurements and release assessments, the establishment of threshold values for initiating safety actions, and the quality assurance programme for the measuring equipment is discussed. The reporting system for liquid radioactive effluents is demonstrated by the example of an actual radioactive release report. Compliance with the guide requirements produces an integral control system for all liquid radioactive effluents of nuclear power plants. (author)