Assessment of a Reactor Coolant Pump Trip for TRILLO NPP with RELAP5/MOD3.2 (NUREG/IA-0177)

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Publication Information

Date Published: March 2000

Prepared by:
M. F. Lozano, P. Moreno, PMSA
A. L. Cedillo, M. N. Sanjurjo, C. N. TRILLO

PMSA
Sector Embarcaciones (Bloque 4°), 17, 1°D
28760 Tres Cantos – Madrid
SPAIN

C.N. TRILLO
Plaza Carlos Trias Bertran, 7, planta 7°
28020 Madrid
SPAIN

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

Availability Notice

Abstract

This document presents the comparison between the simulation results and the plant measurements during a Reactor Coolant Pump Trip in C. Trillo Nuclear Power Plant in different burnup conditions.

This work is part of the Spanish contribution to the Code Assessment and Maintenance Program (CAMP) as a member of UNIDAD ELÉCTRICA, S.A. (UNESA).

C. Trillo is a 3010 MWth three loop PWR Nuclear Power Plant designed by Siemens-KWU. Commercial operation started in August 1988, currently the Plant is running the 11^th annual cycle.

The simulation has been carried out with the RELAP5/MOD3.2 code, running on a HP 715/50 work-station.

The transient main parameters have been correctly assessed, however predictions at the beginning of transient are more difficult as the reactor remains at a high power level after pump trip.