Browse > Article

Equipment Qualification of a Safety-related Large Induction Motor for Nuclear Power Plants  

Lee, Hyoung-Woo (부산대학교 기계공학부)
Ko, Woo-Sik ((주)효성중공업)
Ryu, Jeong-Hyeon (부산대학교 기계기술연구소)
Park, No-Gill (부산대학교 기계공학부)
Publication Information
Journal of the Korean Society for Precision Engineering / v.24, no.6, 2007 , pp. 72-77 More about this Journal
Abstract
A safety-related equipment for the nuclear power plant should be needed an equipment qualification. In this paper, the approach, methods, philosophies, and procedures for qualifying the large squirrel-cage induction electric pump motors for use in ULCHIN 5, 6 Nuclear Power Plants were presented. The method of qualification is a combination of experimental test and analytic method, which is composed of radiation exposure test, seismic simulation test, thermal aging analysis for non-metallic materials, and seismic analysis. The results showed that the motor performed its safety function with no failure mechanism under postulated service conditions.
Keywords
Equipment Qualification; Large Induction Motor; Safety-related; Nuclear Power Plants;
Citations & Related Records
연도 인용수 순위
  • Reference
1 Gunther, W. E., Higgins, J. C. and Aggarwal, S. K., 'The effect of plant aging on equipment qualification and human performance issues related to license renewal, Nuclear Science Symposium and Medical Imaging Conference, pp. 1419-1423, 1991   DOI
2 KEPCO(Korea Electric Power Corporation) Technical Specification No. 9-132-N201, 'Essential Service Water Pumps and Screen Wash Pumps,' for ULCHIN 5&6
3 'IEEE Std. 323, Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,' IEEE Standard, 1974
4 'IEEE Std. 344, Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations,' IEEE Standard, 1987
5 Schiff, A. J. and Kempner, L., 'Issues and Guidance for Institute of Electrical and Electronics Engineers (IEEE) 693 Equipment Qualification Tests,' Lifeline earthquake engineering, ASCE, pp. 607-616, 2003
6 Lindenmeyer, D., Mosherf, A., Schaeffer, C. and Benge, A., 'Simulation of the start-up of a hydro power plant for the emergency power supply of a nuclear power station,' IEEE Transactions on Power Systems, Vol. 16, pp. 163-169, 2001   DOI   ScienceOn
7 'IEEE Std. 334, Standard for Qualifying Continuous Duty Class IE Motors for Nuclear Power Generating Stations,' IEEE Standard, 1994
8 Bohm, G. J., 'Present and future of equipment qualification for dynamic loads,' Nuclear engineering and design, Vol. 59, No. 1, pp. 143-148, 1980   DOI   ScienceOn
9 Antaki, G. A. and Eder, S. J., 'Use of Seismic Experience Data in National Codes and Standards for Equipment Qualification,' Current issues related to nuclear power plant structures, equipment and piping, NCSU, pp. VIII-4, 1994
10 Yeager, K., Willis, J., Bloethe, W., Deeb, N. and Shah, S., 'Modeling of emergency diesel generators in an 800-megawatt nuclear-power-plant,' IEEE Transactions on Energy Conversion, Vol. 8, pp. 433-441, 1993   DOI   ScienceOn
11 Mukhopadhyay, S. and Chaudhuri, S., 'A featurebased approach to monitor-operated valves used in nuclear power plants,' IEEE Transactions on Nuclear Science, Vol. 42, pp. 2209-2220, 1995   DOI   ScienceOn
12 Roos, E., Herter, K. H. and Schuler, X., 'Lifetime management for mechanical systems, structures and components in nuclear power plants,' International Journal of Pressure Vessels and Piping, Vol. 83, pp. 756-766, 2006   DOI   ScienceOn
13 Baxter, F., 'The dangers of bypassing thermal overload relays in nuclear-power plant motor operated valve circuits,' IEEE Transactions on Power Apparatus and Systems, Vol. 99, pp. 2287-2291, 1980   DOI   ScienceOn
14 'Regulatory Guide 1.92, Combination of modes and Spatial Components in Seismic Response Analysis, U.S.,' Atomic Energy Commission, 1974
15 Serhat, S., Emine, A. and Erdino, T., 'Elman's recurrent neutral network applications to condition monitoring in nuclear power plant and rotating machinery,' Engineering Application of Artificial intelligence, Vol. 16, pp. 647-656, 2003   DOI   ScienceOn
16 Teemu, R. and Pia, O., 'Assessing the maintenance unit of a nuclear power plant - identifying the cultural conceptions concerning the maintenance work and the maintenance organization,' Safety Science, Vol. 44, pp. 821-850,2006   DOI   ScienceOn