ASTM_E_2216_-_02_2013.pdf

Designation:E221602(Reapproved 2013)Standard Guide forEvaluating Disposal Options for Concrete from NuclearFacility Decommissioning1This standard is issued under the fixed designation E2216;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon()indicates an editorial change since the last revision or reapproval.INTRODUCTIONNumerous nuclear facilities containing large amounts of concrete are scheduled for decontamina-tion and decommissioning over the next several decades.Much of this concrete is either notcontaminated or only lightly contaminated on or near the surface.However,since concrete is slightlyporous,it has the potential to be contaminated volumetrically.Volumetric contamination is moredifficult to measure than surface contamination,and currently there are no release guidelines forvolumetrically contaminated concrete.As a result,large volumes of concrete are often disposed of asradioactive waste at a large cost.Under certain conditions,the depth or amount of contamination may be limited such that a case canbe made for concrete release for other purposes outside of regulatory control.These cases are likelyto be ones where the radioactive contamination is shallow and is limited to a depth that can beremoved by scabbling(removal of the concrete surface),or where the depth can be estimated basedon the history and condition of the concrete.In addition to surface contaminated concrete,somefacilities contain activated concrete where the depths of contamination vary.This type of concreteshould be handled on a case-by-case basis.Accurate measurements of the radiation source are difficultfor activated concrete,because the activated portions of the embedded metal or concrete are partiallyshielded by the concrete that lies between the source and the measuring device.Care must be takento measure radiation levels of activated concrete accurately,so actual radiation levels are documentedand used when applying release criteria.This standard guide applies to nonrubbelized concrete that is still in place with a defined geometryand known history where the depth of contamination can be measured or estimated based on itshistory.It is not practical to measure radiation levels of concrete rubble.The process outlined herestarts with characterizing the concrete in place,then evaluating the dose to the public and cost ofvarious disposal options.1.Scope1.1 This standard guide defines the process for developing astrategy for dispositioning concrete from nuclear facility de-commissioning.It outlines a 10-step method to evaluatedisposal options for radioactively contaminated concrete.Oneof the steps is to complete a detailed analysis of the cost anddose to nonradiation workers(the public);the methodologyand supporting data to perform this analysis are detailed in theappendices.The resulting data can be used to balance dose andcost and select the best disposal option.These data,whichestablish a technical basis to apply to release the concrete,canbe used in several ways:(1)to show that the release meetsexisting release criteria,(2)to establish a basis to requestrelease of the concrete on a case-by-case basis,(3)to developa basis for establishing release criteria where none exists.1.2 This standard guide is based on the“Protocol forDevelopment of Authorized Release Limits for Concrete atU.S.Department of Energy Sites,”(1)2from which the analysismethodology and supporting data are taken.1.3 Guide E1760 provides a general process for release ofmaterials containing residual amounts of radioactivity.In1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.03 on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities and Components.Current edition approved Jan.1,2013.Published January 2013.Originallyapproved in 2002.Last previous edition approved in 2008 as E221602(2008).DOI:10.1520/E2216-02R13.2The boldface numbers in parentheses refer to a list of references at the end ofthis standard.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 addition,Guide E1278 provides a general process for analyz-ing radioactive pathways.This standard guide is intended foruse in conjunction with Guides E1760 and E1278,and pro-vides a more detailed approach for the release of concrete.2.Referenced Documents2.1 ASTM Standards:3E1278 Guide for Radioactive Pathway Methodology forRelease of Sites Following Decommissioning(Withdrawn2005)4E1760 Guide for Unrestricted Disposition of Bulk MaterialsContaining Residual Amounts of RadioactivityE1893 Guide for Selection and Use of Portable RadiologicalSurvey Instruments for Performing In Situ RadiologicalAssessments to Support Unrestricted Release from Fur-ther Regulatory