Workshop on the use of PRA methodology for the analysis of reactor events and operational data: Proceedings

Conference · Mon Jun 01 00:00:00 EDT 1992

OSTI ID:10167026

Rasmuson, D M ^[1]; Dingman, S ^[2]

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1. Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Programs
2. Sandia National Labs., Albuquerque, NM (United States)

A workshop entitled ``The Use of PRA Methodology for the Analysis of Reactor Events and Operational Data`` was held on January 29--30, 1992 in Annapolis, Maryland. Over 50 participants from the NRC, its contractors, and others participated in the meetings. During the first day, presentations were made by invited speakers to discuss issues in relevant topics. On the second day, discussion groups were held to focus on three areas: risk significance of operational events, industry risk profile and generic concerns, and risk monitoring and risk-based performance indicators. Important considerations identified from the workshop are the following: Improve the Accident Sequence Precursor models and data. Improve the SCSS and NPRDS (e.g., by adding detailed performance information on selected components, by improving narratives on failure causes). Develop risk-based performance indicators. Use risk insights to help focus trending and performance analyses of components, systems, initiators, and sequences. Improve the statistical quality of trending and performance analyses. Flag implications of special conditions (e.g., external events, containment performance) during data studies. Trend common cause and human performance using appropriate models to obtain a better understanding of the impact and causes of failure. Develop a method for producing an industry risk profile.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Programs
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10167026
• Report Number(s): NUREG/CP-0124; CONF-9201110-Summ.; ON: TI92018700
• Resource Relation: Conference: Workshop on the use of PRA methodology for the analysis of reactor events and operational data,Annapolis, MD (United States),29-30 Jan 1992; Other Information: PBD: Jun 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUCLEAR POWER PLANTS
RISK ASSESSMENT
BWR TYPE REACTORS
PWR TYPE REACTORS
PERFORMANCE
HUMAN FACTORS
FAILURES
MONITORING
SURVEILLANCE
220900
210100
210200
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED