• Journal of Energy Engineering
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• v.23 no.3
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• pp.96-101
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• 2014

The Instrument Channel setpoints of the Reactor Protection System(RPS) and the Engineered Safety Feature Actuation System(ESFAS) ensures the safety of Nuclear Power Plants (NPPs), and the actuation of the protection system should be guaranteed on power change condition. The goal of this study is to verify the appropriateness of the sensor drift and rack drift which are important factors for setpoints evaluation and to improve the setpoints margin using the operation data, design specifications and operation manuals of the NPPS.

• Journal of the Korean Society of Safety
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• v.26 no.5
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• pp.99-104
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• 2011

An ILRT Interval for a nuclear power plant in Korea was extended from once in five years to once in ten years. Therefore, it is necessary to evaluate risk impact for ILRT interval extensions. In this paper, input data were generated for the reference plants, KSNP, using raw data such as meteorological data, population distribution data and source term data. And, using MACCS II code the risk impact assessment was performed based on the two methodologies of NUREG-1493 and NEI Interim Report. The risk impact derived from an ILRT interval extension was identified not to be significant. It is considered to apply this study and results to making an accident management plan and safety goal, and to the field of public acceptance.

• Journal of the Korean Society for Nondestructive Testing
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• v.34 no.5
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• pp.384-389
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• 2014

In this paper, the result of an ultrasonic performance demonstration are analyzed. The requirements for an ultrasonic performance demonstration (PD) for a nuclear power plant were first described in ASME B&P Code Section XI, Appendix VIII (1989 winter addenda). In order to establish the performance demonstration scheme in Korean nuclear power plants, the Korea Hydro & Nuclear Power Co. Ltd (KHNP) has developed the Korean Performance Demonstration (KPD) system for the for the ultrasonic examination of nuclear power plants. An analysis of the ultrasonic performance demonstration results from 2004 through 2013 will improve the detection of flaws in an ultrasonic examination, as well as the further development of the KPD training system.

• Nuclear Engineering and Technology
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• v.53 no.1
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• pp.351-356
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• 2021

Korean nuclear power plants (NPPs) have various radiation protection programs to attain radiation exposure as low as reasonably achievable (ALARA). In terms of ALARA, this paper provides a comprehensive overview of administrative dose control for occupationally-exposed workers in Korean NPPs. In addition to dose limits, administrative dose constraints are implemented to resolve an inequity of radiation exposure in which some individuals in NPPs receive relatively higher doses than others. Occupational dose constraints in Korean NPPs are presented in this paper with the background of how those values were determined. For pressurized water reactors, 80% and 90% of the annual average limit for an effective dose, 20 mSv/y, are set as the primary and secondary dose constraints, respectively. Pressurized heavy water reactors (PHWRs) have also established the primary and secondary dose constraints corresponding to 70% and 80% of the effective dose limit, and additional constraints for tritium concentration are provided to control internal exposure in PHWRs. Follow-up measures for exceeding these administrative dose constraints are also introduced compared to exceeding the dose limits. Finally, analysis results of dose distributions show how the implementation of administrative dose constraints impacted the occupational dose distributions in Korean NPPs during the years 2009-2018.

• Proceedings of the KIEE Conference
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• 2007.07a
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• pp.614-615
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• 2007

There are roughly a hundred types of cables in power plants. The distribution of circuits in a nuclear plant is comprised of 20% instrument cables, 61% control cables, 13% AC power cables, 1% DC power cables, and 5% communication lines. In the nuclear power plant, medium voltage cables are generally included in the scope of systems reviewed for safety and are included in a plant's maintenance program. Medium voltage cables provide power to many critical components in plants, including feed water pumps, circulating water pumps, and condensate pumps. Among these cables, high temperature sections of cables feeding electrical power to the circulating water pump and the condenser extraction pump were found. The evaluation for these cables is performed to find the maximum allowable current and temperature. The result shows that the load current flowed about 85% of the allowable current ampacity, and the temperature of conductor at full load current did not exceed the limited temperature. Therefore, existing cables for circulating water pump and condenser extraction pump system are going to be used during design life.

• Journal of Energy Engineering
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• v.26 no.2
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• pp.12-22
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• 2017

Korea Hydro & Nuclear Power Co. (KHNP) has implemented engineering programs for operating nuclear power plants. Engineering programs are maintenance rule (MR), functional importance determination (FID), single point vulnerability (SPV) and functional equipment group (FEG). Recently, KHNP has developed engineering programs for APR1400 feedwater supplying system to establish the advanced engineering system and will verify the suitability of engineering programs through implementing in new nuclear power plant. Consequently, it is expected that the reliability of APR1400 feedwater supplying system will be improved by implementing engineering programs.

• Proceedings of the KIEE Conference
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• 2011.07a
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• pp.804-805
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• 2011

국내 원자력발전소의 고압 케이블의 체계적인 열화 진단 및 수명예측을 위한 사전작업으로 원자력발전소에서 불리한 환경 하에서 장기간 사용된 후 철거된 XLPE 전력 케이블을 대상으로 성능 측정을 수행하였다. 측정 방법으로는 VLF(Very Low Frequency) Tan${\delta}$ 방법 및 상용주파 부분방전시험을 택하였다. 또한 고주파변류기(HFCT)를 사용하는 부분방전 측정방법(HFPD)에 VLF 내압기를 적용할 수 있는지 확인하였다.

• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.638_639
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• 2009

The motors faults including mechanical rotor imbalances, broken rotor bar, bearing failure and eccentricities problems are reflected in electric, electromagnetic and mechanical quantities. This paper presents a study and the practical implementation of an induction motor for reactor containment fan cooler in nuclear power plant with Electric Signature Analysis(ESA). The results obtained present a good degree of reliability hence; the ESA predictive maintenance tools enable a pro-active evaluation of induction motors performance prior to failure.

• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.1678_1679
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• 2009

원전에 설치되어 있는 노외 핵계측 검출기는 설계수명과 품질보증 수명의 차이가 크기 때문에 적절한 검출기 교체 프로그램의 수립이 어렵다. 따라서 본 논문에서는 노외 핵계측검출기에 대한 노화 진행정도 판단 및 최적 교체주기 수립을 위한 원전 노외 핵계측 검출기 성능진단 시스템 및 분석기술에 대해 고찰하였다.

• Proceedings of the KIEE Conference
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• 2008.07a
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• pp.2036-2037
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• 2008

An Emergency Diesel Generator (EDG) manufactured by a French company Wartsila SACM, is a tandem type engine, consisted of two 10 cylindered diesel engines on each side. Manual provided by the manufacturer states that engine bearing requires inspection every 15 years. However, it is difficult for an inspector to access through a manhole located in the lower compartment of engine. Furthermore, during a routine or scheduled maintenance, it is not possible to disassemble main engine bearing and crank shaft, and perform inspection. Two methodologies are suggested here to resolve the problem. One method is to lift the engine and partially perform the maintenance service, and the other method is to disassemble the engine completely and to perform maintenance service by the manufacturer. Pros and cons of two methodologies were thoroughly compared.