Published February 2000 | Version v1
Journal article

Risk-informed inservice inspection program

  • 1. Smirt, Lyon (France)
  • 2. Nuclear Regulatory Commission, Washington, DC (United States). Electrical Mater. and Mech. Eng.

Description

The Nuclear Regulatory Commission (NRC) has developed draft guidance for power reactor licenses on acceptable methods for using probabilistic risk assessment (PRA) information and insights in support of plant-specific applications to change the current licensing basis (CLB) for inservice inspection (ISI) of piping. This process is also known as risk-informed inservice inspection programs (RI-ISI). The risk-informed inservice inspection process for operating nuclear power plants provides an alternative method for selecting and categorizing piping components that are inspected for the purposes of meeting the requirements of ASME section XI. A RI-ISI approach will incorporate probabilistic techniques to help define the scope, type and frequency of inservice inspection. The risk-informed process may support a decrease in the number of inspection and inspection intervals but will also identify areas where increased resources should be allocated to enhance safety. The approach discussed in this paper follows the method developed by NRC staff. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
195
Journal Issue
2
Journal Page Range
p. 211-215
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
2 refs.