Analyses of selected ATWS transients are presented to illustrate the sensitivity of transient consequences to: (1) an uncontrolled boron dilution during the initial 10 minutes of the transient, (2) inoperability of 50 percent of the auxiliary feedwater system capacity, and (3) failure of one CVCS charging pump to provide borated flow. Responses to the majority of more ยป requests for justification of system availability require detailed descriptions of the systems as installed at the particular plants and as such can only be provided on a plant-specific basis. The general tenor of the NRC questions is to request justification for assuming operability of certain systems used to mitigate the consequences of an ATWS event, or to provide additional analyses demonstrating the sensitivity of the consequences to the inoperability of these systems. Responses are presented to all NRC questions concerning transient analyses contained in the ''Status Report for Anticipated Transients Without Scram for Combustion Engineering Reactors,'' dated December 9, 1975, which have not previously been answered in CENPD-158, Revision 1, ''Analyses of Anticipated Transients Without Reactor Scram in Combustion Engineering NSSSs,'' dated May, 1976.
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