Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

Technical Report · Thu Oct 01 04:00:00 EDT 1992

OSTI ID:6862386

Puglia, B; Gallagher, D; Amico, P; Atefi, B ^[1]

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1. Science Applications International Corp., Reston, VA (United States)

This report describes a process developed to convert an existing PRA into model amenable to real time risk-based technical specification calculations. In earlier studies culminating in (NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The accuracy of the master logic model was confirmed. The model was then used to evaluate the core damage frequency associated with several plant configurations using the IRRAS code. For all cases analyzed the computational time was less than three minutes.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Operational Events Assessment; Science Applications International Corp., Reston, VA (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 6862386
• Report Number(s): NUREG/CR-5925-Vol.1; SAIC--92/6668-R1-Vol.1; ON: TI93002315
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAILURES
FAULT TREE ANALYSIS
LOSS OF COOLANT
MAINTENANCE
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SPECIFICATIONS
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