A process for risk-focused maintenance
- Science Applications International Corp., McLean, VA (USA)
This report presents a process for focusing maintenance resources on components that enable nuclear plant systems to perform their essential functions and on components whose failure may initiate challenges to safety systems, so as to have the greatest impact in decreasing risk. The process provides criteria, based on risk, for deciding which components are critical to risk and determining what maintenance activities are required to ensure reliable operation of those risk-critical components. Two approaches are provided for selection of risk-critical components. One approach uses the results of a Probabilistic Risk Assessment (PRA); the other is based on the methodology developed for this report, which has a basis in PRA although it does not use the results of a PRA study. Following identification of risk-critical components, both approaches use a single methodology for determining what maintenance activities are required to ensure reliable operation of the identified components. The report also provides demonstrations of application of the two approaches to selection of risk-critical components and demonstrations of application of the methodology for determining what maintenance activities are required to an active standby safety system, a normally operating system, and passive components. 5 refs., 11 figs., 1 tab.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Regulatory Applications; Science Applications International Corp., McLean, VA (USA)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
- OSTI ID:
- 5974178
- Report Number(s):
- NUREG/CR-5695; ON: TI91010631
- Country of Publication:
- United States
- Language:
- English
Similar Records
The role of PRA in implementing the maintenance rule
Risk-based evaluation of AOT and STI requirements at ANO-1 nuclear power plant
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ENGINEERED SAFETY SYSTEMS
REACTOR MAINTENANCE
RELIABILITY
PWR TYPE REACTORS
PROGRAM MANAGEMENT
CONTAINMENT SYSTEMS
FEEDWATER
LIQUID PENETRANT INSPECTION
PLANNING
PRIMARY COOLANT CIRCUITS
PROBABILISTIC ESTIMATION
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY INJECTION
SECONDARY COOLANT CIRCUITS
VENTILATION SYSTEMS
CONTAINMENT
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
HYDROGEN COMPOUNDS
MAINTENANCE
MANAGEMENT
MATERIALS TESTING
NONDESTRUCTIVE TESTING
OPERATION
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled