Assessment of RELAP5/MOD3.2-NPA3.4 Against an Inadvertent Closure of all Three MSIV's in VANDELLOS-II Nuclear Power Plant (NUREG/IA-0197)
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Date Published: January 2001
C. Llopis, A. Tanarro, R.M. Fanegas
Avda. Montes de Oca, 1,
San Sebastian de los Reyes
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
The work consists in reproducing an actual inadvertent manual closure of all three main steam isolation valves transient that occurred at Vandellós II Nuclear Power Plant (Tarragona, Spain), by means of the RELAP 5/MOD 3.2 code, thus becoming part of an assessment type exercise.
The calculations have been performed by the plant technical support staff and TECNATOM S.A. in a jointly effort. Vandellós NPP input model for RELAP 5/MOD 3.2, has been developed, starting from the input model for the former versions RELAP 5/MOD 2 and MOD 2.5, by the licensee technical services department. The model was provided to TECNATOM S.A., along with the plant data, transient available records and associated information in order to perform the transient calculation and sensitivity studies. Finally, the results and conclusions were discussed and presented jointly by both organizations.
The present report is mainly focused to the steady state and transient calculations and the findings and conclusions derived from them. The general purpose model provided by. the licensee, along with some little modifications implemented for the specific transient calculation, are described. A thorough description of the model build-up process is not included.
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