Journal of the Korean Society of Radiology (한국방사선학회논문지)

The Korean Society of Radiology (한국방사선학회)
권호 표지
DOI QR코드

DOI QR Code

An Analysis on the DCGL setting Method of the United States for Demonstrating Nuclear Power Plants Site Release Criteria

국내 원전 부지 해제 기준 준수 입증을 위한 미국의 유도농도기준(DCGL) 설정 방법에 대한 분석

  • Jeon, Yeo Ryeong (Department of Radiological Science, Catholic University of Daegu) ;
  • Park, Sang June (School of Mechanical Engineering, Pusan National University) ;
  • Ahn, Seokyoung (School of Mechanical Engineering, Pusan National University) ;
  • Lee, Jong Seh (Department of Civil Engineering, Hanyang University, ERICA) ;
  • Kim, Yongmin (Department of Radiological Science, Catholic University of Daegu)
  • 전여령 (대구가톨릭대학교 방사선학과) ;
  • 박상준 (부산대학교 기계공학부) ;
  • 안석영 (부산대학교 기계공학부) ;
  • 이종세 (한양대학교 토목공학과) ;
  • 김용민 (대구가톨릭대학교 방사선학과)
  • Received : 2016.11.17
  • Accepted : 2017.02.28
  • Published : 2017.02.28
Download PDF
⟨ Previous Next ⟩

Abstract

The U.S. NRC establishes a radiological criteria with regard to restricted or unrestricted use of nuclear plant site after decommissioning in NUREG-1757. According to this, a nuclear plant site can be released in a restricted way or unrestricted way only if a licensee demonstrates that the dose criteria is fulfilled after the site decontamination and remediation. In order to prove compliance with the radiological criteria of site release, LTP(License Termination Plan) must include the site release criteria, site characterization, final survey plan with major radionuclides and DCGL(Derived Concentration Guideline Levels), etc. Based on the decommissioning case of Rancho Seco nuclear power plant in the United States, this paper analyzed a method of setting the DCGL that can be applied to Kori NPP Unit 1 which will be permanently disabled in 2017.

원전 해체 이후 원전 부지의 제한적 또는 무제한적 이용에 대해서 미국 NRC는 NUREG-1757 문서를 통해 제한적 또는 무제한적 부지 이용에 관한 방사선학적 기준을 제시하였고 사업자가 제염 및 복원 후 이 선량 기준이 충족됨을 증명할 수 있어야만 부지가 제한적 또는 무제한적으로 해제될 수 있다고 하였다. 이와 관련하여 NRC는 운영허가종료계획서(LTP; License Termination Plan)에 방사선학적 부지 해제 기준 준수를 입증하기 위하여 부지 해제 기준, 부지 특성 평가, 최종 방사선 조사 계획에서 주요 방사선원항, 유도농도기준(DCGL) 등을 기재하도록 하고 있다. 이 논문은 국내 원전 해체에 있어서 참조사례가 될 수 있는 Rancho Seco 원전 해체 사례를 참고 및 절차를 분석함으로써 2017년 영구정지가 예정된 고리 1호기뿐만 아니라 향후 해체 원전 부지의 해제 기준 마련에 있어 사용될 수 있는 방법을 검토하였다.

Keywords

References

  1. Nuclear Safety and Security Commission, "Nuclear Safety Yearbook", pp. 11, 2014.
  2. http://www.khnp.co.kr/content/196/main.do?mnCd=FN050504.
  3. Nuclear Safety and Security Commission, "Nuclear Safety Act", 2014.
  4. United States Nuclear Regulatory Commission, NUREG-1757, Volume 2, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria, September 2003.
  5. United States Nuclear Regulatory Commission, Rancho Seco License Termination Plan, Chapter 6, 2006.
  6. United States Nuclear Regulatory Commission, NUR EG/CR-6697, Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes, Attatchment A, pp. 48, 2000.
  7. S. Park, "A Study on the Optimization Method for Decommissioning Site Remediaction", Graducate School of Kyung Hee University, pp. 35, 2016.
  8. LEBrown. DTBD-04-001, Revision No.2, Radionuclides for Consideration During Rancho Seco Nuclear Generating Station Characterization or Final Status Surveys, United States Nuclear Regulatory Commission, 2005.
  9. United States Nuclear Regulatory Commission, NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual, pp. 126, August 2000.
  10. United States Nuclear Regulatory Commission,. NUREG/CR-5512, Volume 1, Residual Radioactive Contamination From Decommissioning, pp. 42-50, Octo ber 1992.
  11. R. Decker. DTBD-05-015, Rancho Seco Nuclear Generating Station Structure Nuclide Fraction and DCGLs, United States Nuclear Regulatory Commission, 2006.
  12. United States Nuclear Regulatory Commission, NUREG/CR-6676, Volume 1, Probabilistic Dose Analysis Using Parameter Distributions Developed for RESRAD and RESRAD-BUILD Codes, pp. 19-20, May 2000.
  13. G. Pillsbury. DTBD-05-009, Embedded Piping Scenario and DCGL Determination Basis, NRC, pp. 21- 25, November 2005.
  14. United States Nuclear Regulatory Commission, 10CFR20, Subpart E, Radiological Criteria for License Termination, 2011.
  15. Y. J. Bae, Y. M. Kim, S. Y. Ahn, C. M. Kim, "A n Integrative Review on Domestic Site Release Criteria of Nuclear Power Plant based on the Analysis of Foreign Site Release Criteria," Journal of the Korean Society of Radiology, Vol.9, No.5, pp.269-277, 2015. https://doi.org/10.7742/jksr.2015.9.5.269
  16. P. Zaho, Y. R. Jeon, Y. Kim, J. S. Lee, and S. Ahn, "A Radionuclides Suite Selection for Site Characterization and Final Status Survey in the U.S. NPPs, Journal of Nuclear Feul Cycle and Waste Technology, Vol.14, No.3, pp. 267-277, 2016. https://doi.org/10.7733/jnfcwt.2016.14.3.267