Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
|Publication Date:||10 June 2002|
|ICS Code (Nuclear energy in general):||27.120.01|
This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.
This standard guide is based on the "Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites," (Arnish, J. et.al., 2000) from which the analysis methodology and supporting data are taken.
Guide E 1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E 1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E 1760 and E 1278, and provides a more detailed approach for the release of concrete.