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The Nuclear Regulatory Commission (NRC) has developed draft guidance for power reactor licenses on acceptable methods for using probabilistic risk assessment (PRA) information and insights in support of plant-specific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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 31016553
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DATA PROCESSING; INSPECTION; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; REACTOR MAINTENANCE; REACTOR MATERIALS; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ENGINEERING; MAINTENANCE; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; PROCESSING; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- 2 refs.