In September 2006, the regulatory body of Japan, the Nuclear Industry and Safety Agency (NISA), issued an interim report entitled “The improvement of the inspection system for nuclear power plants” which had been reviewed by the Subcommittee of the Advisory Committee on Nuclear and Industrial Safety. The report addresses the potential use of risk information in order to identify the safety significant inspection scope, to select and evaluate performance indicators, to evaluate the safety significance of inspection findings, and to enhance the maintenance program. NISA has been preparing for the new inspection system in Fiscal Year 2008. Before the implementation, technical bases such as the detailed design of the new inspection system and the pilot application of major issues need to be developed. The technical support of this new inspection program is now in progress by the Japan Nuclear Energy Safety Organization (JNES) to develop methodology and technical bases for improvement of efficiency and transparency of regulatory inspection, application of risk information to develop maintenance program guidelines, selection of performance indicators, identification of the safety significance of inspection findings and comprehensive evaluation of individual plants. This paper shows the development and sample calculation of significance determination process (SDP) which is one part of the new inspection program. The SDP is applied to evaluate the significance of inspection findings. The inspection findings are categorized into four groups such as the safety function facet, the risk facet, the public and occupational radiation exposure facet and the safety importance (SI) of the inspection findings are evaluated with risk information. The sample calculation with this SDP indicated that the level of SI is the same level by the current deterministic evaluation process. At present, the SDP models have been developed into the eight types of typical Japanese nuclear power plants for Boiling Water Reactor (BWR), BWR-3, BWR-4, BWR-5, Advanced BWR, 2-Loop, 3-Loop, 4-Loop Dry Containment Pressurized Water Reactor (PWR) and 4-Loop Ice-Condenser PWR.
- Nuclear Engineering Division
Development of Significance Determination Process in Japan
Kasagawa, Y, Sugawara, M, Uchida, T, Ogura, K, & Yamashita, M. "Development of Significance Determination Process in Japan." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 231-239. ASME. https://doi.org/10.1115/ICONE16-48676
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