Abstract
This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs.
Citation Formats
None.
Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation.
IAEA: N. p.,
1992.
Web.
None.
Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation.
IAEA.
None.
1992.
"Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation."
IAEA.
@misc{etde_10119076,
title = {Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation}
author = {None}
abstractNote = {This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs.}
place = {IAEA}
year = {1992}
month = {Oct}
}
title = {Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation}
author = {None}
abstractNote = {This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs.}
place = {IAEA}
year = {1992}
month = {Oct}
}