Quantitative measurement and identification of reactor coolant system leakage shall be covered.
The purpose of this committee is to standardize criteria, methods and procedures for assuring the design and operational adequacy of reactor coolant pressure boundary leak detection systems used in nuclear power plants. A further objective is to encourage design improvements yielding increased utility and reliability of reactor coolant leakage detection systems. A diversity of leakage detection methods is necessary to provide improved confidence in specific leakage indications.
To prepare guidelines, conduct symposia, and otherwise extend knowledge and use of this discipline.
For more information, please contact
ISA Standards Administrator