The risk management implications of NUREG--1150 methods and results
- Sandia National Labs., Albuquerque, NM (USA)
This report describes the potential uses of NUREG-1150 and similar Probabilistic Risk Assessments (PRAs) in NRC and industry risk management programs. NUREG-1150 uses state-of-the-art PRA techniques to estimate the risk from five nuclear power plants. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. While the development of plant-specific risk management strategies is beyond the scope of this document, examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management from prevention of initiating events though reduction of offsite consequences are discussed, with particular attention given to the early phase of accidents. 14 refs., 9 figs., 28 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5559609
- Report Number(s):
- NUREG/CR-5263; SAND--88-3100; ON: TI90000558
- Country of Publication:
- United States
- Language:
- English
Similar Records
The role of NUREG-1150 in accident management
The role of NUREG-1150 in accident management
Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
EMERGENCY PLANS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FISSION PRODUCT RELEASE
FLUID MECHANICS
GAS COOLED REACTORS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
LOSS OF COOLANT
MAINTENANCE
MANAGEMENT
MECHANICS
N CODES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS