대한기계학회논문집A (Transactions of the Korean Society of Mechanical Engineers A)

  • 제34권4호
  • /
  • Pages.495-499
  • /
  • 2010
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  • 1226-4873(pISSN)
  • /
  • 2288-5226(eISSN)
대한기계학회 (The Korean Society of Mechanical Engineers)
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CANDU형 원전 계속운전 평가지침서 개발

Development of the Regulatory Guidelines for Continued Operation of CANDU Reactor in Korea

  • 최영환 (한국원자력안전기술원 공학연구실) ;
  • 김홍기 (한국원자력안전기술원 공학연구실)
  • Choi, Young-Hwan (Engineering Research Department, Korea Institute of Nuclear Safety) ;
  • Kim, Hong-Key (Engineering Research Department, Korea Institute of Nuclear Safety)
  • 발행 : 2010.04.01
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초록

이 연구에서는 우리나라 CANDU형 원전의 계속운전 규제지침을 개발하였다. CANDU 600 로형인 월성 1호기는 2012년에 30년 설계수명에 도달한다. 설계수명이후에 계속운전을 원하는 원전 사업자는 11개 인자를 포함하는 주기적안전성 평가 보고서를 제출해야 하며, 추가로 다음 사항에 대한 보고서를 제출해야 한다. (1) 경년열화 관리에 대한 범위 및 사전 검토 결과 (2) 경년열화 관리 프로그램 (3) 계속 운전기간을 포함하는 시간제한 경년열화 수명평가, (4) 운전경험 및 주요 연구결과의 반영. 이 연구에서는 상기 항목에 대한 54개의 규제지침이 개발되었다.

In this paper, the regulatory guidelines for the continued operation of the CANDU reactor in Korea were introduced. Wolsong Unit 1, which is a CANDU 600 reactor in Korea, will reach its design life of 30 years in 2012. A licensee who wants to operate a nuclear power plant beyond its design life should submit reports of periodic safety reviews (PSRs) conducted on the basis of 11 safety factors. In addition, the licensee should provide the following: (1) scoping and screening results for aging management, (2) aging management program, (3) TLAA, including the continued operation term, (4) operation-experience feedback, and (5) important safety-research results. In this study, 54 regulatory guidelines for the five above-mentioned items for the CANDU reactor in Korea were developed.

키워드

참고문헌

  1. Korea Government, 2009, "Korea's Nuclear Law," Korea Government.
  2. Korea Government, 2009, "Guideline on an application of technical standard for the continued operation evaluation of reactor facilities," Korea's MEST Notice 2009-37.
  3. USNRC, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," 10CFR54.
  4. National Standard of Canada, 1995, "In service Examination and Testing Requirements for Concrete Containment Structure for CANDU NPPs", CAN/CSA N287.7
  5. USNRC, 1981, "Standard review plan for the Review of Safety Analysis Reports for Nuclear Power Plants," NUREG-0800.
  6. USNRC, 2001, "Generic Aging Lessons Learned (GALL) Report," NUREG-1801.
  7. NEI, 2001, "Industry Guideline for Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule Revision 3," NEI 95-10.