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Technical Brief

Functional Information of System Components Influenced by Operators' Actions on Emergency Operating Procedure

[+] Author and Article Information
Tulis Jojok Suryono

Graduate School of Natural Science and Technology, Okayama University, 3-1-1 Tsushimanaka, Kita-ku, Okayama, 700-8530, Japan; Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN), Gd. 80, Kawasan Puspiptek Serpong, Setu, Tangerang Selatan, Banten, 15310, Indonesia
jojok.s.mif@s.okayama-u.ac.jp

Akio Gofuku

Professor, Graduate School of Natural Science and Technology, Okayama University, 3-1-1 Tsushimanaka, Kita-ku, Okayama, 700-8530, Japan
gofuku-a@okayama-u.ac.jp

1Corresponding author.

ASME doi:10.1115/1.4040366 History: Received October 25, 2017; Revised May 12, 2018

Abstract

In an emergency condition of nuclear power plant, operators have to mitigate the accident in order to remove the decay heat and to prevent the release of radioactive material to the environment following the emergency operating procedures. The action of operators on a component, for example changing the parameter level of a component, which is described in a procedure step, will impact other components of the plant and the plant behavior. Nowadays, the advanced main control rooms have been equipped with the computer-based procedures (CBPs) which provide some features and benefits which are not available in paper-based procedures (PBPs). However, most of CBPs do not provide information of the impact of the counteractions on each procedure step (components influenced and future plant behavior) although it is useful for operators to understand the purpose of the procedure steps before making decisions and taking the actions. This paper discusses the functional information and the method to generate the information using multilevel flow modeling (MFM) model of operator actions on some procedure steps of a simplified emergency operating procedure (EOP) of PWR plant, as an example. Keywords: emergency operating procedures, functional information, components influenced, future plant behavior, steam generator tube rupture, PWR plant

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