The role of PRA in implementing the maintenance rule
- Duke Power Company, Charlotte, NC (United States)
When the maintenance rule takes effect in 1996, it may be one of the most significant uses of probabilistic risk assessment (PRA) in the regulatory environment outside the severe accident area. Both the Nuclear Management Resources council (NUMARC) guidance and the US Nuclear Regulatory Commission's draft regulatory guide indicate that the rule is intended to be performance based and results oriented. Utilities can use PRA methods to establish performance criteria and reliability goals that assure an acceptable level of safety, while at the same time avoiding the cost of activities that do not add to the safety of the plant. The NUMARC guidelines provide specific tasks associated with implementation of the maintenance rule that are ideally suited to the use of PRA methods. These include (a) selecting equipment within scope, (b) determining risk-significant structures, systems, and components (SSCs), (c) determining performance criteria and goals, and (d) assessing the effect on safety of the total plant equipment out of service. This paper briefly discusses the way that Duke Power Company plans to use PRA methods to meet the requirements of the maintenance rule.
- OSTI ID:
- 6022643
- Report Number(s):
- CONF-930601--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 68; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Lessons learned from early implementation of the maintenance rule at nine nuclear power plants
Lessons learned from the Maintenance Rule implementation at Northeast Utilities operating plants
Related Subjects
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
LOSS OF COOLANT
MAINTENANCE
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
WATER COOLED REACTORS