Abstract
This paper presents methods and results of an analysis to determine the maximum expected frequency decay rate (FDR) at Pilgrim Station Unit 2, a nuclear power generating station utilizing a pressurized water reactor design. The maximum expected FDR would be of concern if it was greater than the FDR analogous to the freewheeling coast-down rate of the reactor coolant pump motors. This paper should benefit utilities and regulatory agencies evaluating pressurized water reactor station designs as it describes how to analyze the off-site power system. The paper includes discussions of the criteria for analytically creating overloads to force frequency excursions, load shedding and under-frequency relay effects on the FDR's, important assumptions made, a comparison of FDR's using different load models, and a comparison of the findings with those of other investigators.
Published Version
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