RETRAN02 analysis of reactor water level controller failure

This study provides a detailed examination of a feedwater flow excursion caused by a Reactor Water Level Controller Failure at the Perry Nuclear Power Plant (3579 Mwth, GE BWR 6). The feedwater flow excursion led to a plant scram due to high reactor water level. Plant conditions were as follows: power 63.5%, coreflow 50.4% and steamflow 60.5%. Both one-dimensional kinetics and point kinetics RETRAN neutronic models for the actual point conditions are implemented. Confidence in the model and modeling techniques was achieved by comparing the analytical transient response with the actual plant data. Measured parameters consisted of recorded data from the Emergency Response Information System, the plant process computer, and other available data acquisition systems. RETRAN observables consist of major and minor edit variables, Trip Summary table, and other printed RETRAN output. Good agreement was found with the parameters monitored: core power, reactor steam dome pressure, core flow, steamflow, and reactor water level