Future Gaps: Difference between revisions

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Latest revision as of 20:07, 30 January 2026

Through the review of the current EPRI course offerings, a series of knowledge transfer gaps were identified. Additionally, the key skills of plant specific systems knowledge and plant indoctrination training are not included in EPRI PRA courses. The training on these topics is a utility responsibility and key for the success of PRA Engineers. The following topics are the identified knowledge transfer gaps without formal training provided by EPRI. Many of these topics may be part of a general orientation requirement developed by the industry or part of training developed by third party vendors or contractors. For some of the topics below, EPRI may have developed training for specific utilities that have not yet been published for broader availability. Also, there are scheduled software training opportunities that focus on particular products, such as MAAP, GOTHIC, and FTREX which are provided through the applicable software user group, but do not have links to the EPRI learning management system.

  • General Print Reading – this could be part of the orientation requirements for all nuclear workers
  • The interface of PRA with site organizations such as licensing, operation, systems engineering, and maintenance including communicating risk insights
  • PRA Configuration Control
  • Model Rollout with an emphasis on the most common applications required after a Model Update and how to communicate revised risk results with the site.
  • Low Power/Shutdown Model Development and Maintenance
  • Ethical responsibilities in PRA
  • Thermal Hydraulic Codes such as Gothic and MAAP
  • Features of FTREX
  • Applications such as how to develop a Phoenix model for RICT, insights into Outage Risk Assessment and models supporting that, and Risk-Informed Security with an emphasis on identifying target sets.
  • PRA for Advanced Reactors including source term and release categories
  • Detailed PRA practitioner support for PRA applications such as Risk-Informed Categorization and Treatment of SSCs for Nuclear Power Reactors (50.69) and development of a Surveillance Frequency Control Program (SFCP)