Nuclear power plants must have the ability to ensure that components relied on to safely shutdown the reactor, maintain it a safe shutdown condition and mitigate the consequences of an accident are operationally ready to perform their specified safety function(s). Regulatory agencies must also assure that these components are able to perform their specified safety function(s) when required by plant conditions. Compliance with the ASME “Operation and Maintenance for Nuclear Power Plants” Code (OM Code) is required by the US Nuclear Regulatory Commission of all operators of nuclear power plants to provide this regulatory assurance. This workshop describes the OM Code requirements that assure these components are operationally ready to perform their specified function(s) and the limitations and modifications placed on the use of the OM Code by the USNRC.
The scope of this workshop begins with an introduction in to the organization of the OM Code, a discussion on the distinction between a Code and a Standard and how they are used by the USNRC and review of the USNRC’s definition of “safety-related.” The workshop also provides insights into the purpose and use of ASME Code Cases by the USNRC and power reactor licensees. Included in the workshop is a detailed discussion of the OM Code requirements for the in-service and preservice testing that provides assurance that pumps, valves, and dynamic pipe restraints, are operationally ready to perform their specified function(s). The course also includes a discussion of the OM Code requirements that address the use of risk insights in the development of an in-service test program. The course concludes with a discussion of the limitations and modifications imposed by the USNRC on the use of the OM Code and how licensees comply with the USNRC requirement that they update their In-service Test Program at 10-year intervals.