• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.136.2-136.2
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.536-537
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2019.05a
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• pp.21-22
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• 2019

• KEPCO Journal on Electric Power and Energy
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• v.6 no.3
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• pp.321-322
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• 2020

• Journal of the Korean Society for Nondestructive Testing
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• v.34 no.4
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• pp.311-317
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• 2014

The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI' sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

• Journal of Korean Academy of Fundamentals of Nursing
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• v.24 no.4
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• pp.277-285
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• 2017

Purpose: The purpose of this study was to identify occurrence of needle stick and sharp injuries(NSI) among students, level of faculty stress, and necessity of informed consent when students practice injection skills in fundamentals of nursing practice (FNP). Methods: Data were collected using self-reporting questionnaires and 74 faculty members who teach FNP responded it. Questionnaires included general characteristics, experiences of NSI, stress level, and informed consent. Data were analyzed using frequency, percent and paired t-test. Results: Of 74 faculty members, 51.4% experienced NSI 3~4 times or more during their FNP classes. Major procedures causing NSI during FNP were 'breaking the neck of ampules', 'disposing of used items', and 'inserting needles'. The stress level of faculty was higher and more than doubled when training with human beings compared to manikins. Most faculties (86.5%) agreed to the necessity of informed consent so that the safety of faculty and students could be protected and to provide enough information even though only 10.8% of faculty in this study got informed consent. Conclusion: Because there is high risk in every procedure of NSI, faculty has a high level of stress during injection practice in FNS. Therefore, it is necessary to develop a standard NSI precaution program for junior nursing students and discuss informed consent.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.887-892
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• 1998

A risk informed approach to relax AOTs and STIs of RPS/ESPAS in technical specifications of kori units 3, 4 was performed in this paper. With the proposed AOTs and STIs, system unavailabilities and core damage frequency were quantified using PSA model. The results shoe that core damage frequency is slightly increased by extending AOTs and STIs but negligible. As considering the benefits such as reduction of plant transients and man power for test and maintenance, the relaxation of AOTs/STIs of RPS/ESFAS is justified

• Journal of the Korean Society of Safety
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• v.16 no.2
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• pp.110-116
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• 2001

The objective of the Maintenance Rule (MR) is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that the safety related and certain nonsafety-related SSCs are capable of performing their intended functions. In Korea, as risk informed applications and regulation become active, the necessity of Performance Based Regulation (PBR) has increased. The objective of this article is to study the effectiveness of MR based on performance and feasibility of MR adoption at Korean Nuclear Power Plants (NPPs) for effective maintenance and regulation.

• Nuclear Engineering and Technology
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• v.34 no.4
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• pp.331-343
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• 2002

We performed an importance analysis of In-Service Testing (157) components for Ulchin Unit 3 using the integrated evaluation method for categorizing component safety significance developed in this study. The developed method is basically aimed at having a PSA expert perform an importance analysis using PSA and its related information. The importance analysis using the developed method is initiated by ranking the component importance using quantitative PSA information. The importance analysis of the IST components not modeled in the PSA is performed through the engineering judgment, based on the expertise of PSA, and the quantitative and qualitative information for the 157 components. The PSA scope for importance analysis includes not only Level 1 and 2 internal PSA but also Level 1 external and shutdown/low power operation PSA. The importance analysis results of valves show that 167 (26.55%) of the 629 IST valves are HSSCs and 462 (73.45%) are LSSCs. Those of pumps also show that 28 (70%)of the 40157 pumps are HSSCs and 12 (30%) are LSSCs.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.499-500
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• 2004