Systems interaction results from the digraph matrix analysis of the Watts Bar Nuclear Power Plant high pressure safety injection systems. Volume 1

Technical Report · Fri Jul 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/5281090· OSTI ID:5281090

Sacks, I. J.; Ashmore, B. C.; Alesso, H. P.

Spatial and functional coupling (including human actions) of nuclear power plant systems that lead to interdependencies are called Systems Interactions. At present, the US Nuclear Regulatory Commission (NRC) is investigating ways of integrating a systems interactions study with existing Probabilistic Risk Assessment efforts. One approach is based on graph-theoretic methods utilizing matrix representations of logic diagrams called Digraph Matrix Analysis (DMA). The objective in this report is to demonstrate the capabilities of Digraph Matrix Analysis to model an accident sequence (including front-line systems, support systems and human actions) as a continuous, well-integrated logic model in order to identify and evaluate functional systems interactions. The selected accident sequence, loss of high pressure safety injection during a LOCA, was modeled and qualitative and quantitative comparisons were made to the Reactor Safety Study (WASH 1400) and other studies.

• Research Organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5281090
• Report Number(s): NUREG/CR-3593-Vol.1; UCRL-53467-Vol.1; ON: DE84005139
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WATTS BAR-1 REACTOR
ENGINEERED SAFETY SYSTEMS
RISK ASSESSMENT
SAFETY INJECTION
WATTS BAR-2 REACTOR
FAILURE MODE ANALYSIS
FAILURES
HUMAN FACTORS ENGINEERING
LOSS OF COOLANT
REACTOR SAFETY
ACCIDENTS
ENGINEERING
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled