Integrated performance validation facility for KNICS

Conference · Sat Jul 01 00:00:00 EDT 2006

OSTI ID:22030070

Kim, D G; Choi, J J; Choi, M J; Choe, I N ^[1]; Gong, Y H; Kim, K H ^[2]

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1. I and C Engineering Dept., Korea Power Engineering Company, 360-9, Mabuk-Dong, Yongin-Si. Gyeonggi-Do. 446-713 (Korea, Republic of)
2. KNICS R and D Center, 28-1, Seongju-Dong, Changwon-Si. 641-120 (Korea, Republic of)

For the application of new digital control and monitoring systems in nuclear power plants (NPPs), it is required to satisfy the proven technology requirements. They should have at least three years of documented, satisfactory service as modules of subsystems in power plant applications similar to that of NPP, or it should have three years of documented, satisfactory service in other plant applications which are similar to the use in NPP (EPRI-URD's first option). However, tlte digital control and monitoring systems developed by Korea Nuclear Instrumentation A Control System (KNICS) R and D Center, due to the nature of the firstly developed system, have had no prior application in any NPPs as well as industrial and fossil power plants. Therefore, well defined program using 'Integrated Performance Validation Facility (IPVF) 'for prototype testing has been prepared to verify their performance, operability and reliability according to EPRI-URD's second option: It has satisfactorily completed a defined program of prototype testing which has been designed to verify its performance. The IPVF for KNICS is being designed to justify that new control systems are proven to meet utility's requirements. The IPVF comprises Virtual Operating Crew (VOC) and Test Commander (TC). Human System Interface (HIS). Evaluation System, and Simulator and Interface System. PLC and DCS developed by KNICS are connected with IPVF. Control logics and HIS of real NPP are implemented in the KNICS PLC and DCS, which are the validation object. Finally. IPVF will be extremely valuable for other activities in addition to the validation of the new control system equipment, including the testing and evaluation of plant control algorithms, personnel training, and support for long-term maintenance of the control systems. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22030070
• Resource Relation: Conference: NPIC and HMIT 2006: 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology, Albuquerque, NM (United States), 12-16 Nov 2006; Other Information: Country of input: France; 4 refs.; Related Information: In: Proceedings of the 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology| 1430 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ALGORITHMS
EVALUATION
INTERFACES
MAN-MACHINE SYSTEMS
NUCLEAR POWER PLANTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR MONITORING SYSTEMS
REACTOR OPERATORS
RELIABILITY
REPUBLIC OF KOREA
SIMULATORS
TRAINING
VALIDATION