• Nuclear Engineering and Technology
• /
• v.43 no.2
• /
• pp.105-132
• /
• 2011

The concept of improved performance indicators (PIs) for use in the KINS Safety Performance Indicator (SPI) program for reactor safety area is proposed in this paper. To achieve this, the recently developed PIs from the USNRC that use risk information were investigated, and a feasibility study for the application of these PIs in Korean NPPs was performed. The investigated PIs are Baseline Risk Index for Initiating Events (BRIIE), Unplanned Scrams with Complications (USwC), and Mitigating System Performance Index (MSPI). Moreover, the thresholds of the existing safety performance indicators of KINS were evaluated in consideration of the risk and regulatory response to different levels of licensee performance in the graded inspection program.

• Journal of the Korean Society for Nondestructive Testing
• /
• v.4 no.1
• /
• pp.23-29
• /
• 1984

This paper describes the evolution of quality assurance in Korea from it's total reliance on foreign contractors to the present status of conducting all QA functions independently. A brief status of the Republic of Korea Regulatory Bodies, licensing precess, codes and standards, and the quality organization of the Korea Electric Power Corporation are also included.

• Transactions of the Korean Society for Noise and Vibration Engineering
• /
• v.21 no.1
• /
• pp.47-55
• /
• 2011

Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. nuclear regulatory commission regulatory guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors because the measurement is conducted during the critical path of the construction period of nuclear power plants. Therefore, we analyzed RVI thermal-hydraulic and structure design data of Palo Verde nuclear power plant(U.S.), Yonggwang nuclear power plant(Korea) and APR1400 and researched measuring sensors used in them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected suitable measuring sensors for RVI CVAP in advanced power reactor 1400(APR1400).

• Proceedings of the Korean Society of Applied Pharmacology
• /
• 1997.11a
• /
• pp.57-74
• /
• 1997

To make a proposal for the revision of KGCP, ICH Harmonized Tripartite Guideline for Good Clinical Practice, which is on the stage of worldwide implementation, was compared with current GCPs of tripartite countries of ICH, namely USA, Europe and Japan as well as Korea. On the basis of the classification in ICH GCP, comprehensive comparisons among the corresponding articles of 4 regions or countries were made in the order of IRB / IEC, Investigator, Sponsor and Clinical Trial Protocol. Based on the comparisons of the contents in ICH-GCP with those in current GCPs, major suggestions for the revision of current KGCP can be made as follows. Firstly, the function of IRB / IEC needs to be strengthened for the initiation and continuation of clinical trial. Current 2-step approval system of IRB / IEC and Health Authorities requires to be converted into the system similar to that of developed countries. Secondly, sponsor's obligation needs to be tightened to control and assure the quality of clinical trial. Inspection of regulatory authorities should be made to perform during and / or after clinical trial, when it is necessary. In other words, sponsor should be made to establish written Standard Operating Procedures (SOPs) for all aspects of clinical trial including monitoring to ensure that trials are conducted and data are generated, documented, and reported in compliance with the protocol, GCP, and the applicable regulatory requirement (s). Besides, the provision of ‘Quality Control and Quality Assurance’ should be added to the protocol to establish the credibility of the result of the clinical trial.

• Nuclear Engineering and Technology
• /
• v.45 no.2
• /
• pp.249-256
• /
• 2013

In accordance with the US Nuclear Regulatory Commission (US NRC), Regulatory Guide 1.20, the reactor vessel internals comprehensive vibration assessment program (RVI CVAP) has been developed for an Advanced Power Reactor 1400 (APR1400). The purpose of the RVI CVAP is to verify the structural integrity of the reactor internals to flow-induced loads prior to commercial operation. The APR1400 RVI CVAP consists of four programs (analysis, measurement, inspection, and assessment). Thoughtful preparation is essential to the measurement program, because data acquisition must be performed only once. The optimized design of a vibration and stress measurement system for the RVI CVAP is essential to verify the integrity of the APR1400 RVI. We successfully designed a vibration and stress measurement system for the APR1400 RVI CVAP based on the design materials, the hydraulic and structural analysis results, and performance tests of transducers in an extreme environment. The measurement system designed in this paper will be utilized for the APR1400 RVI CVAP as part of the first construction project in Korea.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.13 no.2
• /
• pp.163-169
• /
• 2015

In many nuclear power plant sites in Korea, high density storage racks were installed in the spent fuel pool to expand the spent fuel storage capacity. Nevertheless, the capability of the Hanbit nuclear site will be saturated by 2024. Also, 10 NPPs will reach their design life expiration date by 2029. In the case of the US, SFPI (Spent Fuel Pool Island) operated temporarily as a spent fuel storage option before spent nuclear fuels were transported to an interim storage facility or a final disposal facility. As a spent fuel storage option after shutdown during decommissioning, the SFPI concept can be expected to have the following effects: reduced occupational exposure, lower cost of operation, strengthened safety, and so on. This paper presents a case study associated with the regulations, operating experiences, and systems of SFPI in the US. In conclusion, the following steps are recommended for applying SFPI during decommissioning in Korea: confirmation of design change scope of SFPI and expected final cost, the submission of a decommissioning plan which is reflected in SFPI improvement plans, safety assessment using PSR, application of an operating license change for design change, regulatory body review and approval, design change, inspection by the regulatory body, education and commissioning for SFPI, SFPI operation and periodic inspection, and dismantling of SFPI.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.9 no.1
• /
• pp.62-69
• /
• 2013

A probabilistic assessment code, PRO-LOCA ver. 3.7 which was developed in an international co-operative research program, PARTRIDGE was evaluated by conducting sensitivity analysis. The effect of some variables such as simulation methods (adaptive sampling, iteration numbers, weld residual stress model), crack features(Poisson's arrival rate, maximum numbers of cracks, initial flaw size, fabrication flaws), operating and loading conditions(temperature, primary bending stress, earthquake strength and frequency), and inspection model(inspection intervals, detectable leak rate) on the failure probabilities of a surge line nozzle was investigated. The results of sensitivity analysis shows the remaining problems of the PRO-LOCA code such as the instability of adaptive sampling and unexpected trend of failure probabilities at an early stage.

• Proceedings of the Korea Concrete Institute Conference
• /
• 2006.11a
• /
• pp.237-240
• /
• 2006

Almost 30 years have been passed since the first nuclear power plant was operated in Korea. Many studies have been actively conducted from the early 1990's in order to develop the deterioration management system for concrete structures in NPPs(Nuclear Power Plants) accordingly. Base on these studies, a systematic deterioration management program has developed and operated since 1997. According to this program, systematic inspections to provide database and evaluation were periodically performed (every overhaul at intervals of $12{\sim}18$ month and every five years). Accumulated deterioration database was usefully utilized for the NPP PSR (Periodic Safety Review). In this paper, the long-term durability and integrity of Kori 1,2 NPP concrete structures which are the oldest ones in Korea were evaluated based on the precise inspection database and regulatory inspection results including compressive strength, depth of carbonation, amount of chlorination and spontaneous potential of reinforcing bar, etc. It was noted that Kori 1,2 NPP structures have not any serious durability problems.

• Journal of Technology Innovation
• /
• v.28 no.4
• /
• pp.1-26
• /
• 2020

Due to the spread of Corona 19 around the world, Infectious Disease Medicine and New Medical Devices such as Diagnostic Agent are being rapidly developed and launched, and for the fast supply and demand of these, each country has eased import regulations or has implemented policies for fast approval(NIDS, 2020). On the other hand, New Developed Medical Devices that are not related to New Infectious Diseases, they are still entering the market through strict licensing and licensing regulations, such as delay and cancellation in the test inspection process, etc. Therefore, This Study specialized in the government-managed laws encountered when New Medical Devices enter the market, derive Factors influencing the Strength of Regulations, analyzes the Strength of Regulations, and proposes a Regulatory Response Framework. The Research Method was conducted by Literature Research, was applied by Failure Mode and Effects Analysis(FMEA) Method, Expert Interview(1st): Idea Collection, Expert Interview(2nd): Validation, and Priority through the Application Process of FMEA Method. A Method of Quantifying the Intensity of Regulation was proposed by multiplying the Impact of the Influencing Factors for each stage of regulation and the Burden Impact for each type of Regulatory Affairs to find the Importance of the Regulatory Factors and multiplying the Severity of the Regulatory Impact. The Implications are that major overseas countries and the Korean government are actively responding with Special Regulatory Policies and Mitigation Policies for fast licensing of New Developed Medical Devices in accordance with Corona 19. It is expected that the direction for improvement of regulations and measures to respond to regulations will be implemented so that a more proactive and preemptive response to the regulatory process of the licensing policy for New Devices can be achieved.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.05a
• /
• pp.153-158
• /
• 1997

This paper describes a formal safety analysis technique which is demonstrated by performing empirical formal safety analysis with the case study of beamline hutch door Interlock system that is developed by using PLC(Programmable Logic Controller) systems at the Pohang Accelerator Laboratory. In order to perform formal safety analysis, we have built the Z formal specifications representation from user requirement written in ambiguous natural language and target PLC ladder logic, respectively. We have also studied the effective method to express typical PLC timer component by using specific Z formal notation which is supported by temporal history. We present a formal proof technique specifying and verifying that the hazardous states are not introduced into ladder logic in the PLC-based safety critical system.