Assessment of RELAP5/MOD2 Against a Main Feedwater Turbopump Trip Transient in the Vandellos II Nuclear Power Plant (NUREG/IA-0110, ICSP–V2–TURFW–R)
On this page:
Download complete document
Date Published: December 1993
C. Llopis, A. Casals/A. N. V.
J. Perez, R. Mendizabal/C. S. N.
Asociacion Nuclear Vandellos (A. N. V.)
Consejo de Seguridad Nuclear (C. S. N.)
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
The Consejo de Seguridad Nuclear (CSN) and the Asociacion Nuclear Vandellos (ANV) have developed a model of Vandellos II Nuclear Power Plant. The ANV collaboration consisted in the supply of design and actual data, the cooperation in the simulation of the control systems and other model components, as well as in the results analysis.
The obtained model has been assessed against the following transients occurred in plant:
- A trip from the 100% power level (CSN)
- A load rejection from 100% to 50% (CSN)
- A load rejection from 75% to 65% (ANV)
- A feedwater turbopump trip (ANV)
This copy is a report of the feedwater turbopump trip transient simulation. This transient ocurred actually in plant on June 19, 1989.