1、Designation: E 2421 05Standard Guide forPreparing Waste Management Plans for DecommissioningNuclear Facilities1This standard is issued under the fixed designation E 2421; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of
2、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.1. Scope1.1 This guide addresses the development of waste manage-ment plans for potential waste streams resulting from decom-miss
3、ioning activities at nuclear facilities, including identifying,categorizing, and handling the waste from generation to finaldisposal.1.2 This guide is applicable to potential waste streamsanticipated from decommissioning activities of nuclear facili-ties whose operations were governed by the Nuclear
4、 Regula-tory Commission (NRC) or Agreement State license, underDepartment of Energy (DOE) Orders, or Department of De-fense (DoD) regulations.1.3 This guide provides a description of the key elements ofwaste management plans that if followed will successfullyallow for the characterization, packaging
5、, transportation, andoff-site treatment or disposal, or both, of conventional, hazard-ous, and radioactive waste streams.1.4 This guide does not address the on-site treatment, longterm storage, or on-site disposal of these potential wastestreams.1.5 This standard does not purport to address all of t
6、hesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2D 5283 Practice for Genera
7、tion of Environmental DataRelated to Waste Management Activities: Quality Assur-ance and Quality Control Planning and ImplementationD 5792 Practice for Generation of Environmental DataRelated to Waste Management Activities: Development ofData Quality ObjectivesE 1892 Guide for Preparing Characteriza
8、tion Plans for De-commissioning Nuclear FacilitiesE 1893 Guide for Selection and Use of Portable Radiologi-cal Survey Instruments for Performing In Situ RadiologicalAssessments in Support of Decommissioning2.2 Code of Federal Regulations:310 CFR 60 Disposal of High-Level Radioactive Wastes inGeologi
9、c Repositories10 CFR 61 Licensing Requirements for Land Disposal ofRadioactive Waste10 CFR 71 Packaging and Transportation of RadioactiveMaterials10 CFR 830.120 Quality Assurance Requirements29 CFR 1910.120 Hazardous Waste Operations and Emer-gency Response40 CFR 261 Identification and Listing of Ha
10、zardous Waste40 CFR 262 Standards Applicable to Generators of Hazard-ous Waste40 CFR 761 Polychlorinated Biphenyls (PCBs) Manufac-turing, Processing, Distribution in Commerce, and UseProhibitions40 CFR 763 Asbestos49 CFR 172 Hazardous Materials Table, Special Provisions,Hazardous Materials Communica
11、tions, Emergency Re-sponse Information, and Training Requirements49 CFR 173 ShippersGeneral Requirements for Ship-ments and Packagings49 CFR 397 Transportation of Hazardous Materials; Driv-ing and Parking Rules2.3 DOE Documents:3DOE Order 460.1A Packaging and Transportation SafetyDOE Order 460.2 Dep
12、artmental Materials Transportationand Packaging ManagementDOE Order 474.1 Control and Accountability of NuclearMaterialsDOE Order 414.1A Quality AssuranceDOE Manual M 435.1-1 Radioactive Waste Management2.4 United States Code:31This guide is under the jurisdiction of ASTM Committee E10 on NuclearTec
13、hnology 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, 2005. Published February 2005.2For referenced ASTM standards, visit the ASTM website
14、, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE,
15、 Washington, DC 20401.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.United States Code, Title 42, Section 20142.5 USACE Documents:4Engineering Manual EM 385-1-1.06E Ionizing Radiation (3Nov. 2003)Radiation Protection Manual EM 385-
16、1-80 (30 May 1997)2.6 Other Documents:ASME Quality Assurance Requirements for Nuclear Facil-ity Applications5EPA QA/R-2 Requirements for Quality Management Plans6EPA QA/G-4 Guidance for Data Quality Objectives6NQA-1-2000 American Society of Mechanical Engineers,200163. Terminology3.1 Definitions:3.1
17、.1 documentsinstructions, procedures and drawingsthat control policy, administrative, and technical information.3.1.2 recordselectronic, written, printed, microfilm, pho-tographs, radiographs, or optical disks that contain data that areretained for their future value.3.1.3 waste acceptance requireme
18、ntscriteria and all otherrequirements that a facility receiving waste for treatment,storage, or disposal must meet to receive waste.3.1.4 waste acceptance criteriathe technical and admin-istrative criteria that a waste must meet to be accepted at atreatment, storage, or disposal facility.4. Signific
19、ance and Use4.1 A waste management plan based on the contents of thisguide will provide for the successful identification of potentialwaste streams anticipated from decommissioning activities,and provide a clear and concise methodology for the handlingof identified waste from generation to final dis
20、position.4.2 The waste management plan will identify the generalwaste types, characterization, packaging, transportation, dis-posal, and quality assurance requirements for potential wastestreams.5. General Waste Types5.1 RadioactiveRadioactive wastes are defined as dis-carded material in any form th
21、at must be managed for itsradioactive content per federal or agreement state regulations.Radioactive wastes are further categorized into the followingsubclasses.5.1.1 High LevelHigh level wastes are irradiated reactorfuel (spent nuclear fuel) and the highly radioactive materialresulting from the rep
22、rocessing of irradiated reactor fuel,including liquid waste and any solid material derived fromsuch liquid (10 CFR 60, DOE Manual M 435.1-1).5.1.2 TransuranicTransuranic wastes are any materialcontaining alpha-emitting transuranic nuclides with half-livesgreater than 20 years and in concentrations g
23、reater than 100nanocuries per gram (3.7 kBq g-1)(1310-7Ci/g) (DOE ManualM 435.1-1).5.1.3 By-Product MaterialBy-product material wastes areany radioactive material (except special nuclear material)yielded in or made radioactive by exposure to the radiationincident to the process of producing or utili
24、zing special nuclearmaterial, and the tailings or wastes produced by the extractionor concentration of uranium or thorium from any ore processedprimarily for its source material content (42 U.S.C. 2014(e).5.1.4 Naturally Occurring and Accelerator Produced Ra-dioactive Materials:5.1.4.1 NORM (Natural
25、ly Occurring RadioactiveMaterial)Any material that contains naturally occurringradionuclides. By-product material and the natural radioactiv-ity of rocks, soils, or background radiation are not to beincluded (DOE Manual M 435.1-1).5.1.4.2 NARM (Naturally Occurring or Accelerator Pro-duced Radioactiv
26、e Material)Any material that containsNORM or accelerator-produced radioactive materials.5.1.4.3 TENORM (Technologically Enhanced Naturally Oc-curring Radioactive Materials)NORM whose composition,radionuclide concentrations, availability, or proximity to manhave been increased by or because of human
27、practices.5.1.5 Low LevelLow level wastes are radioactive wastesthat are not spent fuel, high level radioactive wastes, transu-ranic radioactive wastes, by-product material, or naturallyoccurring radioactive materials. Low level wastes are definedinto categories per 10 CFR 61.55(a)(2)(i) and accompa
28、nyingtables. Those categories include:5.1.5.1 Class AClass A wastes contain the lowest concen-trations of radioactivity and typically are composed of short-lived radionuclides that generate no decay heat, do not need tobe shielded, and decay to levels posing minimal potentialhuman dose within 100 ye
29、ars. ClassAwastes typically have anaverage concentration less than 100 GBq m-3(2.7 Ci m-3) andconstitute the majority of generated radioactive waste.5.1.5.2 Class BClass B wastes contain the next lowestconcentrations of radioactivity and typically are composed ofgreater quantities of short-lived rad
30、ionuclides than Class A.Class B wastes typically have an average concentration of 3TBq m-3(81 Ci m-3).5.1.5.3 Class CClass C wastes contain the highest con-centrations of radioactivity acceptable for near-surface dis-posal. Class C wastes are typically composed of greaterconcentrations of short-live
31、d radionuclides than Class A or Bwastes, and may contain long-lived radionuclides. Class Cwastes on average have a concentration of 9 TBq m-3(243 Cim-3) and will not decay to acceptable levels within 100 years.5.1.5.4 Greater Than Class CGreater Than Class Cwastes are all radioactive wastes, defined
32、 as low level wastes,that do not qualify for near-surface disposal as defined in 10CFR 61.5.2 HazardousHazardous wastes are solid wastes as de-fined in 40 CFR 261 that meet any one of the following fourcriteria:5.2.1 Exhibits a characteristic such as ignitable, corrosive,reactive, or toxic as define
33、d in 40 CFR 261, Subpart C,4United States Army Corps of Engineers, USACE Publications Depot, ATTN:CEIM-IM-PD, 2803 52nd Ave., Hyattesville, MD 20781-1102.5Available from American Society of Mechanical Engineers, ASME, ASMEInternational Headquarters, Three Park Ave., New York, NY 10016-5990.6U.S. Env
34、ironmental Protection Agency, Quality Staff (281 1R), 1200 Pennsyl-vania Ave., NW, Washington, DC 20460. E-mail: qualityepa.govE24210525.2.2 Is identified as a listed waste under the F, K, P, or Ulists as defined in 40 CFR 261, Subpart D,5.2.3 Is composed of a mixture of a solid waste and a listedwa
35、ste as defined in 40 CFR 261.3(b),or5.2.4 Is a derived waste from the treatment, storage, ordisposal of a listed waste as defined in 40 CFR 261.3(c)(2)(i).5.3 Mixed WasteMixed Waste containing a RCRA haz-ardous material and an NRC regulated radioactive material.5.4 Co-mingled WasteWaste containing a
36、ny CERCLAhazardous substance other than the CERCLA radioactivehazardous substances and any radioactive materials.5.5 PCBPolychlorinated Biphenyl (PCB) wastes arePCBs and PCB items that are subject to the disposal require-ments of 40 CFR 761, Subpart D.5.6 ConventionalConventional wastes are any non-
37、hazardous discarded material in any form that does not containresidual amounts of radioactivity above the limits of thetreatment or disposal facility.6. Characterization6.1 The waste management plan should include a descrip-tion of the waste characterization methodology. The wastecharacterization me
38、thodology should be of sufficient detail toensure that physical, chemical, and radiological properties ofthe wastes are identified and known throughout the wastemanagement process and that they are characterized withsufficient accuracy to ensure worker protection, proper segre-gation, treatment, sto
39、rage, and disposal. Useful informationrelative to the characterization of waste streams can be foundin Guide E 1892. Waste characterization methodologies shouldfocus on total data acquisition and be based on direct methods(surveys and sampling and analysis), and indirect methods(process knowledge).
40、Characterization data should includeinformation obtained from direct measurement, and fromsampling and analysis of the waste materials. Guidance ondirect measurement is contained in Guide E 1893.6.2 Sampling and AnalysisThe sampling and analysis ofwaste streams should be conducted in accordance with
41、 awritten plan that identifies the data life cycle process. The datalife cycle process is composed of three essential elements:planning, implementation, and assessment.6.2.1 PlanningThe planning process is a project manage-ment tool that identifies and documents the qualitative andquantitative state
42、ments that define the data quality objectivesprocess (for example, Practice D 5792). A graded approach tothe planning process should be considered based on the size,complexity, available resources, and level of quality control.6.2.2 ImplementationSampling and analysis plans shouldidentify the target
43、 analyte(s), the sampling design and meth-odology as determined during the planning process, the qualitycontrol parameters, and the analytical requirements per theapproved statement of work.6.2.3 AssessmentThe three-step assessment process isbased on verification, validation, and data quality assess
44、ment.6.2.3.1 Verification is a systematic process performed exter-nally from the data generator that evaluates the laboratorydelivered data set (that is, data package) against the deliverablerequirements as stated in the laboratory statement of work. Italso checks for completeness, consistency, comp
45、arability, andcorrectness of the data set.(1) A verification report should be generated that identifiesany correctable and non-correctable discrepancies associatedwith the data set. The report should be in a standard format andremain as part of the data package.(2) Data verification should be an int
46、eractive process withthe laboratory. It should provide appropriate feedback toaddress correctable and non-correctable discrepancies whichresult in opportunities to improve the analytical work prior toproject completion.6.2.3.2 Validation is a systematic process performed exter-nally from the data ge
47、nerator that addresses the reliability ofthe data and provides assurance of the presence or absence ofanalytes. This process reviews the verification report, andlaboratory-delivered data set, and applies defined performance-based criteria to qualify the data.(1) A data validation report should be ge
48、nerated thatidentifies all data qualified based on the performance-basedcriteria. The report should be in a standardized format andremain as part of the data package.6.2.3.3 The data quality assessment process is the “scientificand statistical evaluation of data to determine if they are of theright
49、type, quality, and quantity to support their intended use.”This process should not be limited to the verification andvalidation of data, but should encompass the entire samplecollection and analysis process and its impact on data qualityand usability.(1) Agraded approach based on the intended use of the datashould be applied to the data quality assessment process. Thisshould be done in such a manner that the three fundamentalpremises are satisfied:(a) Are the samples representative?(b) Are the data accurate?(c) Can a decision be made?6.3 Process KnowledgeA c
