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Implementation of SAMG and Integration with Emergency Response in Canada

Abstract of the technical presentation presented at:
IAEA Technical Meeting on Implementation and Integration of Accident Management Guidelines and Interface with Emergency Preparedness and Response
September 27–29, 2017

Prepared by:
Peter Devitt
Canadian Nuclear Safety Commission


In Canada, the generic severe accident management guidelines (SAMG) were developed in 2006, taking into account Canada Deuterium Uranium (CANDU) reactor design features and related characteristics of severe accident progression and phenomenology. Critical parameters were identified for reactor operators to determine when to switch from an accident-specific procedure response to a symptom-based approach. These symptom-based SAMG enable nuclear power plant (NPP) personnel to identify suitable actions to mitigate a severe accident and bring the NPP to a stable and controlled state.

The Fukushima Daiichi accident demonstrated the importance of having robust SAMG. Soon after the events at Fukushima, all Canadian NPPs implemented their SAMG.

As the SAMG were being implemented, the Canadian Nuclear Safety Commission (CNSC) carried out several regulatory activities to ensure that actions under the SAMG aligned with other operating procedures and that the onsite staff had been trained in the use of SAMG. These activities included document review, interviews with site staff and observation of safety drills. Furthermore, the CNSC has participated jointly with the NPPs in national emergency exercises. These exercises provide an understanding of the ways in which the licensee SAMG integrate with the emergency response of other organizations. The presentation given at this IAEA Technical Meeting describes the objectives, scope, processes and major activities carried out by CNSC staff to assess the implementation and integration of the plant-specific SAMG.

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