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A Safety Improvement for the Design Change of Westinghouse 2 Loop Auxiliary Feedwater System

웨스팅하우스형 원전의 보조급수계통 설계변경 영향 평가

  • 나장환 (한국수력원자력(주) 중앙연구원) ;
  • 배연경 (한국수력원자력(주) 중앙연구원) ;
  • 이은찬 (한국수력원자력(주) 중앙연구원)
  • Received : 2013.07.18
  • Accepted : 2013.08.20
  • Published : 2013.09.01

Abstract

The auxiliary feedwater is an important to remove the heat from the reactor core when the main feedwater system is unavailable. In most initiating events in Probabilistic Safety Assessment(PSA), the operaton of this system is required to mitigate the accidents. For one of domestic nuclear power plants, a design change of a turbine-driven auxiliary feedwater pump(TD-AFWP), pipe, and valves in the auxiliary system is implemented due to the aging related deterioration by long time operation. This change includes the replacement of the TD-AFWP, the relocation of some valves for improving the system availability, a new cross-tie line, and the installation of manual valves for maintenance. The design modification affects the PSA because the system is critical to mitigate the accidents. In this paper, the safety effect of the change of the auxiliary feedwater system is assessed with regard to the PSA view point. The results demonstrate that this change can supply the auxiliary feedwater from the TD-AFWP in the accident with the motor-driven auxiliary feedwater pump(MD-AFWP) unavailable due to test or maintenance. In addition, the change of MOV's normal position from "close" to "open" can deliver the water to steam generator in the loss of offsite power(LOOP) event. Therefore, it is confirmed that the design change of the auxiliary feedwater system reduces the total core damage frequency(CDF).

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