1、Designation:E 1278 88(Reapproved 1996)e1Standard Guide forRadioactive Pathway Methodology for Release of SitesFollowing Decommissioning1This standard is issued under the fixed designation E 1278;the number immediately following the designation indicates the year oforiginal adoption or,in the case of
2、 revision,the year of last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon(e)indicates an editorial change since the last revision or reapproval.e1NOTEKeywords were added editorially in January 1996.1.Scope1.1 The purpose of this guide is to provide guidan
3、ce indetermining site-specific conversion factors for translatingbetween dose limits and residual radioactive contaminationlevels on equipment,structures,and land areas.This guidedoes not endorse specific levels of allowable residual radioac-tive contamination,nor does it provide a methodology forpo
4、pulation dose calculations.1.2 Standards prescribing dose limits for decommissionednuclear facilities or sites and/or private properties contami-nated with radioactive materials are necessary to identifydecommissioning methods,guide cleanup(remedial action)efforts,determine cleanup costs,identify th
5、e amount of radio-active waste to be disposed,and protect the public.Suchstandards,however,are not yet available for all types ofnuclear facilities,sites,or properties.Regulatory Guide 1.86 ofthe U.S.Nuclear Regulatory Commission(NRC)(1),2as wellas specific promulgations of the Environmental Protect
6、ionAgency(EPA)and the Department of Energy(DOE),providesome specific guidance.1.3 This guide is not intended to establish these federalpolicies.They will be promulgated by the EPA and otherfederal agencies.Rather,it is to serve as a guide to acceptablemethodology for translating the yet to be determ
7、ined doselimits into allowable levels of residual radioactive materialsthat can be left at a site following decommissioning.1.4 This standard does not purport to address all of thesafety concerns,if any,associated with its use.It is theresponsibility of the user of this standard to establish appro-p
8、riate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2.Referenced Documents2.1 ASTM Standards:E 1034 Specification for Nuclear Facility Transient WorkerRecords3E 1167 Guide for a Radiation Protection Program for De-commissioning Operations32.2ANSI
9、 Standard:ANSI-ASME-NQA-1 American National Standards Insti-tute QualityAssurance Program Requirements for NuclearFacilities43.Terminology3.1 Definitions:3.1.1 criteria,ngoals or objectives,or both,to beachieved against which the degree of accomplishment can bemeasured.3.1.2 decommission,vtto remove
10、 a nuclear facility safelyfrom service and reduce residual radioactivity to levels thatpermit release of the property or facility for unrestricted useand termination of any applicable license(s).3.1.3 decontamination,nthose activities employed to re-duce the levels of radioactive contamination in or
11、 on structures,equipment,materials,and property.3.1.4 dose equivalent,nthe product of the absorbed dose,the quality factor(Q),and any other modifying factors(N).3.1.5 effective dose equivalent,nthe sum of the weightedcommitted dose equivalents and the dose equivalent receivedfrom external sources.Th
12、e sum represents the same risk as ifthe whole body were irradiated uniformly.3.1.6 nuclear facility,na facility whose operations in-volve(or involved)radioactive materials in such form orquantity that a radiological hazard potentially exists(or ex-isted)to the employees or the general public.Include
13、d arefacilities that are(or were)used to produce,process,or storeradioactive materials.Some examples are nuclear reactors(power,test,or research),fuel fabrication plants,fuel repro-cessing plants,uranium/thorium mills,UF-6 production andenrichment plants,radiochemical laboratories,and radioactivewas
14、te disposal sites.3.1.7 remedial action,ndecontamination,waste removal,and site restoration conducted as part of a site or property1This guide is under the jurisdiction of ASTM Committee E-10 on NuclearTechnology and Applicationsand is the direct responsibility of SubcommitteeE10.03on Radiological P
15、rotection for Decontamination and Decommissioning ofNuclear Facilities and Components.Current edition approved November 25,1988.Published February 1989.2The boldface numbers in parentheses refer to the list of references appended tothis guide.3Annual Book of ASTM Standards,Vol 12.02.4Available from
16、American National Standards Institute,11 W.42nd St.,13thFloor,New York,NY 10036.1Copyright ASTM,100 Barr Harbor Drive,West Conshohocken,PA 19428-2959,United States.decommissioning effort.3.1.8 surface contamination,nthe results of the deposi-tion and attachment of foreign materials(here most commonlythought of as radioactive materials)to exposed surfaces.4.Significance and Use4.1 Applying the considerations in this guide will provideassurance that the allowable residual radioactive contamination
