Assessment of human interactions credited in Canadian PSA using SPAR-H method

There is a wide variety of available methods to perform Human Reliability Analysis (HRA) in support of Probabilistic Safety Assessment (PSA). However, it is recognized that no strong consensus exists on the best methods to perform HRA. All methods have merits and limitations under the particular circumstances in which they are applied. In 2014, the Idaho National Laboratory (INL) and the Canadian Nuclear Safety Commission (CNSC) embarked upon a cooperative project to assess Human Interactions (HIs) credited in Level 1 and Level 2 PSA of a Canadian Nuclear Power Plant (NPP) using an alternate HRA method. The project also aimed at developing generic guidance for crediting Severe Accident Management Guidelines (SAMGs) including the use of Emergency Mitigation Equipment (EME) in Level 2 PSAs. This paper summarizes the outcome of this project that includes: 1) performance of an HRA confirmatory evaluation from a Canadian NPP PSA using an alternative HRA method; 2) alignment of HRA Performance Shaping Factors (PSFs) with the Safety and Control Areas (SCAs) defined in the Canadian regulatory framework; and 3) development of SAMGs and EME Guidelines in Level 2 PSA studies. (author)