IEEE IEC 63260-2020 pdf download – Guide for incorporating human reliability analysis into probabilistic risk assessments for nuclear power generating stations and other nuclear facilities.
fault tree: A graphical representation of an analytical technique whereby an undesired state of a system is specifed and the patterns leading to that state can be evaluated to determine how the undesirable system failure can occur. human action: The observable result (often a bodily movement) of a person’s intention. human error: Failure of human task performance to meet specifed criteria of accuracy, completeness, correctness, appropriateness, or timeliness. human error probability (HEP): The quantitative estimation of the likelihood of a human error. human failure event (HFE): A basic event that pertains to a human error. human interaction: A human action or set of actions that afects equipment, response of systems, or other human actions. human reliability analysis (HRA): Any number of formal approaches and methods used to identify sources of human error and quantify their accompanying human error probabilities. initiating event: An event either internal or external to the plant that perturbs the steady state operation of the plant by challenging plant control and safety systems whose failure could potentially lead to core damage or release of airborne fssion products. operating crew: Plant personnel working on shift to operate the plant. They include control room personnel and those support personnel who directly support the control room personnel in operating the plant. performance shaping factor (PSF): A factor that infuences human reliability through its efects on performance. These include factors such as environmental conditions, human-system interface design, procedures, training, and supervision.
3. Overview of an integrated HRA 3.1 General 3.1.1 Importance of human reliability In assessing the risk associated with a nuclear power plant, the analyst should consider not only the reliability of plant hardware systems but also the reliability of people’s interactions with other plant or support personnel and with the plant’s equipment and systems. The scope of interactions with plant equipment and systems should include those in the control room and at local control stations and with both manually controlled and automated systems. 3.1.2 Importance of integrated HRA and PRA An HRA should be an integral part of a PRA. In PRAs, the quality of the analysis (e.g., quantifcation of human error) is dependent upon the analyst’s ability to identify scenarios and the expected human actions. This guide provides a specifc approach that, if applied, will standardize the integration of HRA into the PRA process. The breakdown and order of the steps presented are not so important; all of the steps and their activities, however, should be found within any HRA.