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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsSensitivity Analyses of a Hypothetical 6 Inch Break, LOCA in Ascó NPP using RELAP/MOD3.2 (NUREG/IA-0240)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0240 (PDF - 1.36 MB)Publication Information **Manuscript Completed:**August 2010**Date Published:**September 2010 **Prepared by:** R. Pericas, L. Batet, and F. Reventós 1Institute of Nuclear Energy Research Atomic Energy Council, R.O.C. 1000, Wenhua Rd., Chiaan Village, Lungtan, Taoyuan, 325 TAIWAN Department of Physics and Nuclear Engineering Technical University of Catalonia ETSEIB, Av. Diagonal 647, Pav. C 08028 Barcelona Spain Antony Calvo, NRC Project Manager **Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the International Code Assessment and Maintenance Program (CAMP) **Prepared for:** Division of Systems Analysis Office of Nuclear Regulatory Research  U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Availability Notice Abstract A postulated 6 inch break Loss-of-Coolant Accident (LOCA) is analyzed for the Ascó I plant (a 3 loop PWR Westinghouse design) using RELAP5/Mod3.2. Different scenarios are calculated, including the total loss of the High Pressure Injection System (HPIS). In this case, the maximum cladding temperature rises above the steady state value at full power but, before the end of the transient, temperatures return to normal values by the effect of the accumulators injection. Passive heat structures in the reactor pressure vessel have been incorporated to the model (i.e. the pressure vessel walls and some internals). Calculations with the model including passive heat structures lead to more severe scenarios (i.e. higher cladding temperatures) but still accumulators action is able to return the temperatures to normal values. Finally, sensitivity to the trip time of the reactor coolant pumps is analyzed. Results show that lower cladding temperatures result when the pump trip is delayed. 
      
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