Use of a success-oriented GO-FLOW method for system configuration risk management at NPPs

Abstract In this paper, a framework of improved risk monitor system that integrates multiple applications of retrospective investigation analysis of risk factors, point-in-time risk monitoring and proactive risk management is presented. Among these applications capabilities, the plant configuration risk management is implemented and demonstrated with a safety injection system in the event of medium-break LOCA at nuclear power plants. The system reliability and safety analysis are conducted on the success-oriented logic models using GO-FLOW method. Both quantitative and qualitative risk measures addressed respectively by risk matrix and goal tree-success tree scheme with risk band display could provide global risk insights regarding plant configuration control.

[1]  Ming Yang,et al.  Development of a risk monitoring system for nuclear power plants based on GO-FLOW methodology , 2014 .

[2]  Michiyuki Kobayashi,et al.  GO-FLOW: A New Reliability Analysis Methodology , 1988 .

[3]  Peter Kafka,et al.  Living PSA-risk monitoring—current use and developments , 1997 .

[4]  Andrew C. Kadak,et al.  The nuclear industry's transition to risk-informed regulation and operation in the United States , 2007, Reliab. Eng. Syst. Saf..

[5]  A. Introduction.  AN APPROACH FOR PLANT-SPECIFIC, RISK-INFORMED DECISIONMAKING: TECHNICAL SPECIFICATIONS , 2012 .

[6]  Ming Yang,et al.  Design of Risk Monitor for Nuclear Reactor Plants , 2014 .

[7]  Michiyuki Kobayashi,et al.  The GO-FLOW Methodology: A Reliability Analysis of the Emergency Core Cooling System of a Marine Reactor Under Accident Conditions , 1989 .

[8]  Yang Ming,et al.  A method for developing living PSA for NPPs by using the GO-FLOW methodology , 2014 .

[9]  Fengjun Li,et al.  Online application of a risk management system for risk assessment and monitoring at NPPs , 2016 .

[10]  Tim Bedford,et al.  Safety and Reliability , 2003 .

[11]  Takahiro Kuramoto.  Risk Monitoring for Nuclear Power Plant Applications Using Probabilistic Risk Assessment , 2014 .

[12]  Takeshi Matsuoka.  FFTA: A fast fault tree analysis program , 1986 .

[13]  Inn Seock Kim,et al.  Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part II, Risk-informed approaches , 2010, Reliab. Eng. Syst. Saf..

[14]  Inn Seock Kim,et al.  Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part I, deterministic approaches , 2010, Reliab. Eng. Syst. Saf..