Browse > Article

The Experience of Inservice Inspection for Yonggwang Nuclear Power Plant Unit 6  

Kim, Young-Ho (Korea Electric Power Research Institute)
Nam, Min-Woo (Korea Electric Power Research Institute)
Yang, Seung-Han (Korea Electric Power Research Institute)
Yoon, Byung-Sik (Korea Electric Power Research Institute)
Kim, Yong-Sik (Korea Electric Power Research Institute)
Publication Information
Abstract
As the increase of the operation year of nuclear power plants, the probabilities of the degradation of the major facilities and materials in the nuclear power plants are increased. The integrity of those facilities shall be monitored and verified by the non-destructive examination methods with the regulation codes, so called inservice inspection(ISI). The ISI of Yonggwang unit 6 was performed in four different parts, 1) non-destructive examinations for the components, piping weldments and structures, 2) automated ultrasonic examinations for pressure vessels, 3) visual examinations for the interior structures of the reactor, 4) eddy current examinations for the steam generator tubes. As the results, there was no severe indication and all detected indications were evaluated as non-relavent. Especially for the examinations of the piping weldments, PD(Performance Demonstration) was applied as a W examination method defined in the 1995 edition of ASME Code Sec. XI. The implementation of the PD for the piping weld results in an improvement of the reliability of the UT examinations.
Keywords
Inservice Inspection; Performance Demonstration;
Citations & Related Records
연도 인용수 순위
  • Reference
1 ANSI/ASNT CP-189, 1991 Edition
2 US NRC Regulatory Guide 1.65, 'Material & Inspections for Reactor Vessel Cl osure Studs'
3 US NRC 10 CFR 50.55a, 'Codes & Standards'
4 영광 5, 6호기 최종 안전성 분석보고서
5 미국원자력 규제법 및 규제위원회 (US NRC)의 지침
6 ASME B&PV Code Section XI, 'Rules for Inservice Inspection of Nuclear Power Paint Components, ' 1995 Edition & 1996 Addenda
7 US NRC Regulatory Guide 1.147, 'Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1'
8 미국비파괴검사학회 (ASNT) SNT-TC-1A, 'Personnel Qualification and Certification in Nondestructive Testing', 1984 Edition
9 영광원자력 5호 기 1주기 장기 가동중점검 계획서
10 US NRC Bulletin 88-08, 'Thermal Stress in piping Connected to Reactor Coolant Systems'
11 한수원(주) 품질보증계획서 및 품절보증 절차서
12 US NRC 10 CFR 50 Appendix B, 'Quality Assurance Requirements for Nuclear Power Plants and Fuel Reprocessing Plants'
13 ASME B&PV Code Section V, 'Nondestructive Examination, ' 1995 Edition & 1996 Addenda