Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System

2002 ◽  
Vol 139 (1) ◽  
pp. 42-49
Author(s):  
Cheol Shin Lee ◽  
Chan Eok Park ◽  
Chul Jin Choi ◽  
Jong Tae Seo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Protection ◽  
Plant Response ◽  
Protection System ◽  
Common Mode ◽  
Plant Protection System ◽  
Mode Failure

Performance and Unavailability Analysis of RPS/ESFAS in Korea Standard Nuclear Power Plant (KSNPP)

2002 ◽  
Author(s):  
Seung-Cheol Jang ◽  
Kyung-Ran Min ◽  
Sang-Hoon Han
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Protection ◽  
Technical Specification ◽  
Operating Experience ◽  
Protection System ◽  
Operational Experience ◽  
Actuation System ◽  
Safety Features

The safety-related performance analysis of plant protection system (PPS) comprising reactor protection system/engineered safety features actuation system (RPS/ESFAS) was performed from the operating experience of the Korean standard nuclear power plant (KSNPP). The PPS operational data was collected from the trouble reports (TR) to record details of test and maintenance activities at sites. The total operating experience of 8.63 commercial reactor years at four units during the period 1995 through 2000 was studied. The system unavailability analysis was also performed through the detailed fault tree models, using plant specific data based on observed operational experience. Estimated were the unavailabilities on 11 automatic trip parameters for the RPS and 6 signals for the ESFAS. Results of the data analysis and system unavailability were close to ones published for other CE-supplied plants, though this study included a lot of failures occurred in the beginning periods of commercial operation without percolation. This study was performed to provide technical basis for risk-informed applications like technical specification improvement.

Design of the Communication Independence for ACPR1000 Nuclear Power Plant Digital Safety I&C System

2017 ◽  
Author(s):  
Sun Na ◽  
Shi Gui-lian ◽  
Xie Yi-qin ◽  
Li Gang ◽  
Jiang Guo-jin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Communication Networks ◽  
Nuclear Power ◽  
Protection System ◽  
Plant Safety ◽  
Safety And Reliability ◽  
Digital Protection ◽  
Architecture And Design ◽  
Reactor Protection System

Communication independence is one of the key criteria of digital safety I&C system design. This paper mainly analyzes the requirements for communication independence in safety regulations and standards, and then introduces the architecture and design features, including communication failure processing measures, of communication networks of ACPR1000 nuclear power plant safety digital protection system based on FirmSys platform developed by CTEC. The communication design meets the regulations requirements and effectively improves the safety and reliability of the system, and it is successfully applied in reactor protection system (RPS) of Yang Jiang nuclear power plant unit 5&6. In addition this design can provide reference for communication designs of other NPPs and industries.

Sign in / Sign up

Export Citation Format

Share Document