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New Start, New Standard
Business/R&D[Operation] Safety evaluation lifespan management

KEPCO E&C assumes a pivotal role to play in safe operation of nuclear facilities and stable power supply by providing technical services for safety evaluations, periodic safety reviews and continued operation of nuclear facilities. Given that our extensive expertise encompasses evaluation, management, and analysis technologies related to aging deterioration such as fatigue, corrosion, and embrittlement that can affect facility’s integrity, we are conducting periodic safety reviews for all domestic nuclear facilities in operation every 10 years and safety evaluations for continued operation of domestic nuclear facilities reaching their design life (Kori Units 2, 3, and 4, Hanbit Units 1 and 2, Hanul Units 1 and 2, and Wolseong Units 2, 3, and 4). Moreover, through continuous technology development, we have secured the optimal technology for Probabilistic Safety Assessment (PSA) and are building proprietary technology in For Risk-Informed Applications. Also, we strive to improve the safety of industrial facilities by evaluating the safety level and identifying the areas of safety improvement for large industrial facilities such as Plant facilities including petrochemical facilities.

Description

Periodic safety review (PSR)

PSR is a comprehensive safety evaluation conducted to secure a higher safety level, taking into account the effect of aging deterioration of the structures, systems, and equipment that make up reactor facilities, the use of domestic and international operational experience and research results, and the development of science and technology. Nuclear facilities can secure their safety during the operational period, including continued operation through this evaluation.

Equipment integrity evaluation and management

  • Equipment integrity evaluation and management employs technology that evaluates the integrity for various aging deterioration that can occur during the operation of nuclear facilities and manages them systematically
    • Real Model
    • CFD/FEA case of interpretation

Nuclear reactor stress test

  • Stress test of nuclear facilities employs a technology for evaluating the safety and response capability against severe natural disasters such as earthquakes and tsunamis that exceed design limits. Improvement measures are identified and implemented through the relevant activity to strengthen the safety of nuclear facilities.
    • Highest sea level due to an earthquake and tsunami exceeding design limits

Pipe wall-thinning management

  • Pipe wall-thinning management employs a technology that evaluates the gradual thinning of pipes due to physical and electrochemical effects between carbon steel pipes and high-temperature, high-press, and high-speed fluids and manages their stability and integrity.

DB building stage

Building DB for each piping location

Analysis stage

Water chemistry/thermal hydraulics & thinning analysis

Parts selection stage

Determining parts based on analysis results

Inspection stage

UT inspection of selected parts

Evaluation stage

UT inspection data analysis & evaluation

Maintenance/replacement stage

UT inspection data analysis & evaluation

PSA

  • PSA improves the safety of industrial facilities by identifying all risk factors in large-scale industrial facilities, including nuclear reactor facilities and analyzes the accident development process to evaluate the probability and importance of an accident, identifying the main contributory factors that affect relevant risks through the process to derive countermeasures.

Risk information utilization

  • Risk-informed Application and technology effectively improves industrial facilities' safety, operability, and economic efficiency by comprehensively evaluating the extension of Inservice inspection interval, extension of Allowable outage time, and Revision of Technical Specification using risk information.
    • Risk management
    • Risk monitoring system

Seismic performance evaluation

  • Seismic performance evaluation technology evaluates the seismic safety of structures, systems, and equipment against earthquakes, exceeding the design of large-scale industrial facilities such as nuclear reactor facilities and petrochemical plants. Through seismic performance evaluations, the vulnerability of industrial facilities to earthquakes can be identified, so that the safety of the facility is improved by reinforcing and enhancing seismic performance.
    structure collapse image
    Earthquake-resistant design of structures image

SAREX

  • SAREX is a computer program for performing PSA and reliability/utilization analysis of nuclear reactor facilities, large-scale petrochemical industrial facilities, transportation facilities, and complex facilities. The users of SAREX can evaluate the safety and reliability of all facilities and individual systems, identify vulnerabilities and relative importance ranging from individual devices to systems, and find alternatives to improve the facility’s safety and reliability and increase facility utilization.

    Event Tree Analyzer

    Fault Tree Analyzer

    Acquired nuclear safety mark

Valve performance evaluation technology

  • The valve performance evaluation checks the operability of active motor-operated valves (MOV) and air-operated valves (AOV) related to the safety of nuclear reactor facilities during operation and construction. It evaluates valve performance and improves the safety of nuclear reactor facilities, which is pivotal in mitigating the results of nuclear reactor accidents.
    • Analysis of required force and actuator output