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Study of Transients Related to AMSAC Actuation, Sensitivity Analysis (NUREG/IA-0150)

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Publication Information

Date Published: November 1998

Prepared by:
J.M. Posada, P.M.S.A., F. Revetos, A.N.A., J. Sanchez-Baptista, A.N.A.
A. Perez-Navas, A.N.A., P. Moreno, P.M.S.A.

P.M.S.A.
Av. Viñuelas, N°33, 1°D
Tres Cantos – 28760 MADRID
SPAIN

Asociacion Nuclear ASCO (A.N.A)
Paral.lel, 51
08004 BARCELONA
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

The Asociación Nuclear Ascó (ANA) has prepared a model of Ascó NPP using, RELAP5/MOD3.2. This model, which includes thermal-hydraulics, kinetics and protection and control systems, has been qualified in previous calculations of several actual plant transients.

Ascó NPP is a two unit station of three loop Pressurized Water Reactors (PWR) of Westinghouse design operated by ANA. ANA is a spanish utility that contributes to the Code Application and Maintenance Project (CAMP) as a member of UNIDAD ELECTRIICA S. A. (UNESA).

This report summarizes the results obtained with Ascó NPP model for a loss of normal feedwater ATWS event and presents a sensitivity analysis to kinetic parameters for the same transient.

The phenomenology prediction has been useful from the operation and safety point of view.

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