Abstract Much progress has been made over the years in the area of common cause failure (CCF) analysis, including the development of both qualitative and quantitative analysis methods. Until now, however, CCF methodologies have not explicitly and systematically accounted for the impact of plant-specific defenses, such as design features and operational and maintenance policies, that are in place to reduce the likelihood of failure occurrences at nuclear power plants. Since plant-specific defenses generally have different impacts on different types of causes of failure, the beneficial effects of defenses must be considered separately for each type of cause. A cause-defense matrix is a very convenient tool for presenting these impacts. This paper discusses qualitative cause-defense matrices and the projected advantages of their use. Once developed these matrices may be used by analysts to help perform comprehensive analyses of common cause failures (CCFs) for any nuclear power plant. To truly account for design features and operational and maintenance policies, however, these matrices need to be detailed and, therefore, need to be developed for individual component types, accounting for variations in the design of components within a component type and variations in the way components are tested, maintained, and operated at different plants. Although the matrices discussed here are qualitative, they are, as illustrated through an example in this paper, useful in quantitative CCF analysis as well, regardless of the quantitative method that is used.
[1]
R E Battle,et al.
Reliability of emergency ac power systems at nuclear power plants
,
1983
.
[2]
M. Subudhi,et al.
Operating experience and aging-seismic assessment of battery chargers and inverters
,
1986
.
[3]
H. M. Paula,et al.
A cause-defense approach to the understanding and analysis of common cause failures
,
1990
.
[4]
W. L. Ferrell,et al.
Analysis of core damage frequency from internal events: Peach Bottom, Unit 2
,
1986
.
[5]
Amendola Aniello,et al.
CCF-RBE Common Cause Failure Reliability Benchmark Exercise
,
1987
.
[6]
J. E. Hardin,et al.
Aging of Class 1E batteries in safety systems of nuclear power plants
,
1987
.
[7]
D. M. Rasmuson,et al.
COMCAN II-A: a computer program for automated common cause failure analysis. [LMFBR]
,
1979
.
[8]
K. N. Fleming,et al.
Classification and analysis of reactor operating experience involving dependent events
,
1985
.