• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2003.05a
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• pp.403-414
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• 2003

Periodic safety review on Kori Unit 1 has been successfully done for the first time in Korea. 11 safety factors of the review were fully evaluated in accordance with the domestic legal system. Although it is the oldest nuclear power plant in Korea, Kori Unit 1 was found to have maintained good operating conditions and continuously enhanced its safety by implementing post-TMI action plans and other safety issues, such as replacing steam generators and process/control system. It can be therefore confirmed that safe operation of Kori Unit 1 is guaranteed until next periodic safety review. Nevertheless, some corrective action items were recommended to enhance further its safety level, such as equipment qualification, additional ageing management program, strengthening of some procedures related to administration and human factor. The results of PSR can be utilized for the continued operation beyond the design life as long as the plant safety is maintained and improved. Experiences of the PSR on Kori Unit 1 can be also applied to PSR on other plants.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.9 no.1
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• pp.20-24
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• 2013

Reactor Vessel Internals(RVIs), which are installed within the reactor pressure vessel and support the fuel assembly, take responsibility for safety of reactor core. In operating Nuclear Power Plants(NPPs), the RVIs have been exposed to severe conditions such as neutron irradiation, high temperature, high pressure, and high velocity of coolant flow and have degraded by materials aging with long-term operation. Therefore, the effective aging management plan and the appropriate regulatory requirements are necessary to maintain the integrity of RVIs. The purpose of this paper is to provide a review guide for Periodic Safety Review(PSR) of RVIs in presurized water reactor. The review guide is developed based on the revised review guides and reports established from IAEA and USNRC, and the analysis results of design characteristics, aging mechanisms, and operating experiences of RVIs in domestic and international NPPs. Consequently, the developed review guide for PSR of RVIs is expected to contribute an overall strategy and standard for the PSR of RVIs.

• Nuclear Engineering and Technology
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• v.41 no.4
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• pp.545-548
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• 2009

Korean utility has utilized a Periodic Safety Review (PSR) that assesses the cumulative effects of plant aging, modifications, operating experience, technical developments, and site characteristics since 2000. In particular, the assessment and management of plant aging is one of the major areas in PSR. It includes identification of critical Systems, Structures, and Components (SSCs) for aging, assessment of aging effects, and implementation of aging management programs. Since the PSR system was introduced based on the atomic energy acts and related laws, PSRs of eight sets for 12 Nuclear Power Plants (NPPs) that have been operating more than 10 years have been completed. PSRs of two sets for 4 NPPs are currently being carried out. The utility has confirmed that domestic NPPs have been operated safely through these PSRs and have implemented the follow-up corrective activities to increase the nuclear safety. In this paper, the status of PSR implementation is discussed and improvement programs to conduct PSR follow-up corrective activities efficiently for NPPs are suggested based on experiences with aging assessments.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.455-462
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• 2003

According to Korean nuclear code requires Periodic Safety Review(PSR) every 10 years should be perform for operating reactor, and selects the eleven PSR safety factors. Among them the review objective of the environmental impact is to determine whether the operator has an adequate programme for surveillance of the environmental impact of the nuclear power plant based on current safety standards. In this paper, the environmental impact in PSR of Wolsong Unit 1 was reflected current safety standards as of the evaluation date. As a result, all items generally satisfied the standards, and the staff also verified that the population dose due to the operation of Wolsong Unit 1 was controlled safely as of the evaluation date.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.1213-1214
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• 2005

• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.666_667
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• 2009

원자력발전소의 비상전력계통은 소외정전 시 발전소 안전정지에 필요한 안전관리 설비에 비상전력을 공급하는 계통으로 비상전력계통 모선에 비상디젤발전기(Emergency Diesel Generator : EDG)가 설치되어 있다. 본 논문에서는 국내 중수로형 원자력 발전소에 대해서 최초로 주기적 안전성 평가(Periodic Safety Review : PSR)을 수행한 결과를 기술하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.05a
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• pp.381.1-381.1
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.1321-1322
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• 2005

• Journal of Radiation Protection and Research
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• v.28 no.4
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• pp.349-351
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• 2003

To ensure the safety of the currently operating nuclear power plant, the Periodic Safety Review program has been conducted. In PSR program, the cumulative behavior of the radionuclide that might be released from the power plant is addressed. The Cs-137 in soil around Kori nuclear power plant was investigated. The soil sample was analyzed and compared with the reference area. The model calculation explained the depth profile of Cs-137.

• Nuclear Engineering and Technology
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• v.40 no.4
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• pp.277-284
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• 2008

Recently, the long-term operation of a nuclear power plant beyond its licensed term has become a worldwide trend as long as the safety of the plant is maintained in the extended period. Kori Unit 1, the oldest PWR in Korea, is the foremost example of this type of long-term operation in Korea. Comprehensive technical evaluation of the long-term operation of this plant was completed to confirm the overall safety of the plant. The technical evaluation included a review of PSR results, an assessment on aging management programs and time limited aging analyses, and a statement of radiological impact on the environment. Based on all of the results of the technical evaluation activities, Kori Unit 1 was approved to operate for an additional 10 years beyond its original design life of 30 years.