1、Designation: E2421 15Standard Guide forPreparing Waste Management Plans for DecommissioningNuclear Facilities1This standard is issued under the fixed designation E2421; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of la
2、st revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () 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-mission
3、ing 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 Re
4、gula-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, t
5、ransportation, andoff-site treatment or disposal, or both, of conventional,hazardous, 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 thesaf
6、ety 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:2D5283 Practice for Generation o
7、f Environmental Data Re-lated to Waste Management Activities: Quality Assuranceand Quality Control Planning and ImplementationD5792 Practice for Generation of Environmental Data Re-lated to Waste Management Activities: Development ofData Quality ObjectivesE1892 Guide for Preparing Characterization P
8、lans for De-commissioning Nuclear Facilities2.2 Code of Federal Regulations:310 CFR 60 Disposal of High-Level Radioactive Wastes inGeologic Repositories10 CFR 61 Licensing Requirements for Land Disposal ofRadioactive Waste10 CFR 71 Packaging and Transportation of RadioactiveMaterials10 CFR 830.120 N
9、uclear Safety Management, Subpart A,“Quality Assurance Requirements”29 CFR Subpart H, “Hazardous Materials: Section1910.120, “Hazardous Waste Operations and EmergencyResponse”40 CFR 261 Identification and Listing of Hazardous Waste40 CFR 262 Standards Applicable to Generators of Hazard-ous Waste40 C
10、FR 761 Polychlorinated Biphenyls (PCBs)Manufacturing, Processing, Distribution in Commerce,and Use Prohibitions40 CFR 763 Asbestos49 CFR 172 Hazardous Materials Table, Special Provisions,Hazardous Materials Communications, Emergency Re-sponse Information, and Training Requirements49 CFR 173 Shippers
11、General Requirements for Ship-ments and Packagings49 CFR 397 Transportation of Hazardous Materials; Drivingand Parking Rules2.3 DOE Documents:3DOE Order 460.1A Packaging and Transportation SafetyDOE Order 460.2A Departmental Materials Transportationand Packaging ManagementDOE Order 414.1C Quality As
12、suranceDOE Manual M 435.1-1 Radioactive Waste ManagementManual2.4 United States Code:3USC 2014 Definitions1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applicationsand is the direct responsibility of SubcommitteeE10.03 on Radiological Protection for Decontamina
13、tion and Decommissioning ofNuclear Facilities and Components.Current edition approved June 1, 2015. Published July 2015. Originally approvedin 2005. Last previous edition approved in 2010 as E2421-10. DOI: 10.1520/E2421-15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orconta
14、ct 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, Washington, DC 20401.C
15、opyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States12.5 NRC Standards and Guides:3NUREG-1575 Multi-Agency Radiation Survey and Site In-vestigation Manual (MARSSIM)NUREG-1575, Supplement 1 Multi-Agency Radiation Sur-vey and Assessment of Ma
16、terials and Equipment (MAR-SAME)NUREG-1576 Multi-Agency Radiologial Laboratory Ana-lytical Protocols (MARLAP)2.6 Other Documents:EPA QA/R-2 Requirements for Quality Management Plans4EPA QA/G-4 Guidance on Systematic Planning Using theData Quality Objectives Process4NQA-1-2000 American Society of Mec
17、hanical Engineers,200843. Terminology3.1 Definitions:3.1.1 documentsinstructions, procedures and drawingsthat control policy, administrative, and technical information.3.1.2 recordselectronic, written, printed, microfilm,photographs, radiographs, or optical disks that contain data thatare retained f
18、or their future value.3.1.3 waste acceptance requirementscriteria 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
19、 atreatment, storage, or disposal facility.4. Significance 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 ha
20、ndlingof identified waste from generation to final disposition.4.2 The waste management plan will identify the generalwaste types, characterization, packaging, transportation,disposal, and quality assurance requirements for potentialwaste streams.5. General Waste Types5.1 RadioactiveRadioactive wast
21、es are defined as dis-carded material in any form that 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 t
22、he highly radioactive materialresulting from the reprocessing 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 hal
23、f-livesgreater than 20 years and in concentrations greater than 100nanocuries per gram (3.7 kBq g-1) (110-7Ci/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 ra
24、diationincident to the process of producing or utilizing 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 USC 2014(e).5.1.4 Naturally Occurring and Accelerator Prod
25、uced Ra-dioactive Materials:5.1.4.1 NORM (Naturally 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 (Natura
26、lly Occurring or Accelerator Pro-duced Radioactive 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
27、to manhave been increased by or because of human practices.5.1.5 Low LevelLow level wastes are radioactive wastesthat are not spent fuel, high level radioactive wastes, tran-suranic radioactive wastes, by-product material, or naturallyoccurring radioactive materials. Low level wastes are definedinto
28、 categories per 10 CFR 61.55(a)(2)(i) and accompanyingtables. 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
29、 posing minimal potentialhuman dose within 100 years. 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
30、 composed ofgreater quantities of short-lived radionuclides 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 typicall
31、y composed of greaterconcentrations of short-lived 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
32、Class Cwastes are all radioactive wastes, defined 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
33、ignitable, corrosive,reactive, or toxic as defined in 40 CFR 261, Subpart C,4U.S. Environmental Protection Agency, Quality Staff (281 1R), 1200 Pennsyl-vania Ave., NW, Washington, DC 20460. E-mail: qualityepa.govE2421 1525.2.2 Is identified as a listed waste under the F, K, P, or Ulists as defined i
34、n 40 CFR 261, Subpart D,5.2.3 Is composed of a mixture of a solid waste and a listedwaste 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 RCRAhazard-ous mat
35、erial and an NRC regulated radioactive material.5.4 Co-mingled WasteWaste containing any 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 r
36、equire-ments of 40 CFR 761, Subpart D.5.6 ConventionalConventional wastes are any non-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
37、a descrip-tion of the waste characterization methodology. The wastecharacterization methodology 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 wi
38、thsufficient accuracy to ensure worker protection, propersegregation, treatment, storage, and disposal. Useful informa-tion relative to the characterization of waste streams can befound in Guide E1892. Waste characterization methodologiesshould focus on total data acquisition and be based on directm
39、ethods (surveys and sampling and analysis), and indirectmethods (process knowledge). Characterization data shouldinclude information obtained from direct measurement, andfrom sampling and analysis of the waste materials. Guidanceon direct measurement is contained in the MARSSIM andMARSAME documents.
40、6.2 Sampling and AnalysisThe sampling and analysis ofwaste streams should be conducted in accordance with awritten plan that identifies the data life cycle process. The datalife cycle process is composed of three essential elements:planning, implementation, and assessment. Guidance for sam-pling and
41、 analysis can be found in the MARLAP manual.6.2.1 PlanningThe planning process is a project manage-ment tool that identifies and documents the qualitative andquantitative statements that define the data quality objectivesprocess (for example, Practice D5792). A graded approach tothe planning process
42、 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 analyte(s), the sampling design and meth-odology as determined during the planning process, the qualitycontrol parameters, a
43、nd the analytical requirements per theapproved statement of work.6.2.3 AssessmentThe three-step assessment process isbased on verification, validation, and data quality assessment.6.2.3.1 Verification is a systematic process performed exter-nally from the data generator that evaluates the laboratory
44、delivered data set (that is, data package) against the deliverablerequirements as stated in the laboratory statement of work. Italso checks for completeness, consistency, comparability, andcorrectness of the data set.(1) A verification report should be generated that identifiesany correctable and no
45、n-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 interactive process withthe laboratory. It should provide appropriate feedback toaddress correctable and non-correctable discrep
46、ancies 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 generator that addresses the reliability ofthe data and provides assurance of the presence or absence ofanalytes. This process
47、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 generated thatidentifies all data qualified based on the performance-basedcriteria. The report should be in a standardized form
48、at 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 type, quality, and quantity to support their intended use.”This process should not be limited to the verification andvalidati
49、on of data, but should encompass the entire samplecollection and analysis process and its impact on data qualityand usability.(1) A graded approach based on the intended use of thedata should be applied to the data quality assessment process.This should be done in such a manner that the three funda-mental premises are satisfied:(a) Are the samples representative?(b) Are the data accurate?(c) Can a decision be made?6.3 Process KnowledgeA characterization methodologythat relies on the knowledge of the physical, chemical, andradiological constituents of the
