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2. “Root Cause Analysis Report—Significant Degradation of the Reactor Pressure Vessel Head,” CR 2002-0891 (Apr. 15, 2002) and CR 2002-0891, Rev.1 (Aug. 27, 2002), First Energy Nuclear Operating Company, Davis Besse Nuclear Power Station.
3. “Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations,” NRC Generic Letter 97-01, U.S. Nuclear Regulatory Commission.
4. “Inadequate Core Cooling Studies of Scenarios with Feedwater Available,” WCAP-9754, Westinghouse Electric Corporation (1980) (nonproprietary version).
5. “Analysis of Delayed Coolant Pump Trip During Small Loss of Coolant Accidents for Westinghouse Nuclear Steam Supply Systems,” WCAP-9585, Westinghouse Electric Corporation (1979) (nonproprietary version).