By RT Wood; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information
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Additional resources for Advanced Reactor Licensing : Experience with Digital I&C Technology in Evolutionary Plants
For SDS1, the trip computer design requirements and design description consisted of an English overview description and a corresponding mathematical functional description based on a box-structured method. The design description described the 25 interface requirements between hardware and software components. The required software functions contained in the design requirements and design were combined to form the "virtual" trip computer software requirement specifications. For SDS2, the software requirement specifications were written using function tables.
32 France The responsibility of nuclear safety in France is placed on the nuclear operator. The provisions taken by the nuclear operator to ensure nuclear safety are supervised by the Nuclear Safety Authority (Autorit de SOret6 Nucl6aire), which acts under the joint authority of the Ministry of Environment, the Ministry of Industry, and the Ministry of Health. The central organization within this independent authority is the General Directorate for Nuclear Safety and Radioprotection (DGSNR or Direction G6n6rale de la Soret6 Nucl6aire et de la Radioprotection).
The ANIS computerized procedure presentation system performs this comparison and advises the control room staff of the satisfaction/completeness of each procedure step. By doing so, the Beznau control room operators can address malfunctions much more quickly, thereby reducing the time the plant process is beyond design limits, thereby potentially limiting the severity of transients. This benefit was so important to the Beznau Operations Department that they devised an entirely new "method of operation" for plant operation and procedure use.