Containment structure testing is intended to assure the leak-tight integrity of the containment structure under all design basis conditions. In Korea, ILRT testing frequency for PWR-type plants had been 1 every 5 years following the requirements of operating license. However, the utility had performed more frequently ILRT than the requirements due to the refueling outage of 18 months. The feasibility study of reducing the frequency of ILRT from 1 every 5 years to 1 every 10 years was performed with the method of performance-based containment leak-test program (NUREG-1493). To verify the justification of relaxation of test frequency, two activities were conducted. First, the recent 3 periods experiences of containment leakage-rate test were reviewed. And, Level 3 PSA for Ulchin Units 3 &4 as pilot plants was performed.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4688-1
PROCEEDINGS PAPER
The Use of Level 3 PSA for the Integrated Leakage Rate Test Interval Relaxation in Korea
Hae-Cheol Oh,
Hae-Cheol Oh
Korea Electric Power Research Institute, Daejeon, Korea
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Mi-Ro Seo,
Mi-Ro Seo
Korea Electric Power Research Institute, Daejeon, Korea
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Myung-Ki Kim,
Myung-Ki Kim
Korea Electric Power Research Institute, Daejeon, Korea
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Bag-Soon Chung,
Bag-Soon Chung
Korea Electric Power Research Institute, Daejeon, Korea
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Sung-Yull Hong
Sung-Yull Hong
Korea Electric Power Research Institute, Daejeon, Korea
Search for other works by this author on:
Hae-Cheol Oh
Korea Electric Power Research Institute, Daejeon, Korea
Mi-Ro Seo
Korea Electric Power Research Institute, Daejeon, Korea
Myung-Ki Kim
Korea Electric Power Research Institute, Daejeon, Korea
Bag-Soon Chung
Korea Electric Power Research Institute, Daejeon, Korea
Sung-Yull Hong
Korea Electric Power Research Institute, Daejeon, Korea
Paper No:
ICONE12-49213, pp. 591-595; 5 pages
Published Online:
November 17, 2008
Citation
Oh, H, Seo, M, Kim, M, Chung, B, & Hong, S. "The Use of Level 3 PSA for the Integrated Leakage Rate Test Interval Relaxation in Korea." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 25–29, 2004. pp. 591-595. ASME. https://doi.org/10.1115/ICONE12-49213
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