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Additional resources for Syetems Analysis of the CANDU-3 Reactor
_'P. J. , Atomic Energy of Canada Limited, "CANDU 3 External Analysis Report, Conceptual Probabilistic Safety Assessment," 74-03660-AR-001, 10- 3 The frequencies assigned were order-of-magnitude values because of the preliminary nature of the plant design. 2 along with the reference Several sources were considered to develop a comprehensivelist of IEs for this analysis. t,_ In addition, a limited operatinghistory of CANDU plants and other AECLdesignedplants was reviewed for initiators that have occurred or events that may be precursors to possible IEs.
2 along with the reference Several sources were considered to develop a comprehensivelist of IEs for this analysis. t,_ In addition, a limited operatinghistory of CANDU plants and other AECLdesignedplants was reviewed for initiators that have occurred or events that may be precursors to possible IEs. 0, February 28,1989. :I:R. , Atomic Energy of Canada Limited, "CANDU 3 Systematic Review of the Plant Design for Identification of Initiating Events," 74-00580-ASD-001, Rev. 2, April 10, 1992. 2 Selection of Representative Initiating Events plant responses as other categories and (2) show the safety significance of the respective systems, structures,and components.
7. Group 2, Class I and Class II power supplies are connected to each channel. The logic and instrumentation are designed so that a channel trips on loss of power. Loss of power to individual transmitters is annunciated and causes a parameter trip due to the faulted signal. The outputs from each sensor after amplification are fed to a trip computer, and the trip computersends a tripsignal to the triplogic circuits. SDS2 has three trip logic circuits, one for each pair of the quick-opening helium supply valves.
Syetems Analysis of the CANDU-3 Reactor