Evaluation of surveillance test interval from risk viewpoint

Author

Chou, H.P. ; Wang, Y.H. ; Wei, Y.S. ; Lin, T.J.

Author_Institution

Dept. of Nucl. Eng., Nat. Tsing Hua Univ., Hsinchu, Taiwan

Volume

2

fYear

1997

fDate

9-15 Nov 1997

Firstpage

903

Abstract

The paper presents the application of the probabilistic risk assessment (PRA) technique for surveillance test interval (STI) evaluation. Assessment was performed for the reactor protection system (RPS) based upon the living PRA model of the Taipower´s Maanshan power plant. Fault tree was developed and analyzed to find the most proper subsystem for test interval relaxation. Event tree analyses were made to calculate core meltdown frequencies for test induced transients and anticipated transient without scram events and to evaluate the effect of STI relaxation. Results indicated that an extension of three times of the current RPS test interval has no significant risk impact for the Maanshan plant

Keywords

fission reactor safety; nuclear power stations; probability; Maanshan power plant; anticipated transient without scram events; core meltdown frequencies; fault tree; probabilistic risk assessment; reactor protection system; risk viewpoint; surveillance test interval; test induced transients; Fault trees; Frequency; Inductors; Power generation; Power system modeling; Power system protection; Risk management; Surveillance; Testing; Transient analysis;

fLanguage

English

Publisher

ieee

Conference_Titel

Nuclear Science Symposium, 1997. IEEE

Conference_Location

Albuquerque, NM

ISSN

1082-3654

Print_ISBN

0-7803-4258-5

Type

conf

DOI

10.1109/NSSMIC.1997.670445

Filename

670445