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Rationale for Independent Site Clean-Up and Radiological Clearance Standards

[+] Author Affiliations
Paul H. Genoa

Nuclear Energy Institute, Washington, DC

Paper No. ICEM2003-4930, pp. 1117-1120; 4 pages
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME


Over the past few years, the U.S. nuclear power industry has gained substantial experience and appreciation of the technical complexity and rigor required to meet a performance-based site clean-up standard. Five large power reactors and several smaller ones are now well along the path to license termination. They have not been on this journey alone. There has been a steep learning curve for all stakeholders involved in the process including state and federal radiation regulators, legislators, and the public. We have all learned that the translation of results from a post remediation survey interpreted through pathway modeling for comparison with a dose-based clean-up standard is for many a leap of faith. Our regulator has an understandable desire to address this uncertainty by demanding conservative analysis at each turn. As a result, it is extremely demanding to demonstrate that a clean-up standard in the 0.15–0.25 mSv/a range has been met. It is not likely that a standard in the 10 μSv/a level, typically associated with radiological clearance standards, can be practically demonstrated while still meeting the current expectations of U.S. Nuclear Regulatory Commission for technical rigor.

Copyright © 2003 by ASME



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