Risk based ASME Code requirements
The objective of this ASME Research Task Force is to develop and to apply a methodology for incorporating quantitative risk analysis techniques into the definition of in-service inspection (ISI) programs for a wide range of industrial applications. An additional objective, directed towards the field of nuclear power generation, is ultimately to develop a recommendation for comprehensive revisions to the ISI requirements of Section XI of the ASME Boiler and Pressure Vessel Code. This will require development of a firm technical basis for such requirements, which does not presently exist. Several years of additional research will be required before this can be accomplished. A general methodology suitable for application to any industry has been defined and published. It has recently been refined and further developed during application to the field of nuclear power generation. In the nuclear application probabilistic risk assessment (PRA) techniques and information have been incorporated. With additional analysis, PRA information is used to determine the consequence of a component rupture (increased reactor core damage probability). A procedure has also been recommended for using the resulting quantified risk estimates to determine target component rupture probability values to be maintained by inspection activities. Structural risk and reliability analysis (SRRA) calculations are then used to determine characteristics which an inspection strategy must posess in order to maintain component rupture probabilities below target values. The methodology, results of example applications, and plans for future work are discussed.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 7129942
- Report Number(s):
- PNL-SA-21211; CONF-9209144-1; ON: DE93004323
- Resource Relation:
- Conference: 2. annual fluid systems testing and analysis forum, Boston, MA (United States), 15-16 Sep 1992
- Country of Publication:
- United States
- Language:
- English
Similar Records
ASME development of risk-based inspection guidelines for nuclear power plants
ASME development of risk-based inspection guidelines for nuclear power plants
Related Subjects
NUCLEAR POWER PLANTS
RISK ASSESSMENT
IN-SERVICE INSPECTION
PRESSURE VESSELS
PROBABILITY
RECOMMENDATIONS
RELIABILITY
RUPTURES
CONTAINERS
FAILURES
INSPECTION
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories