1、Designation: E 1892 09Standard Guide forPreparing Characterization Plans for DecommissioningNuclear Facilities1This standard is issued under the fixed designation E 1892; 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 () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This standard guide applies to developing nuclear facil-ity characterization plans to define the type, magnitude, loca
3、-tion, and extent of radiological and chemical contaminationwithin the facility to allow decommissioning planning. Thisguide amplifies guidance regarding facility characterizationindicated in ASTM Standard E 1281 on Nuclear FacilityDecommissioning Plans. This guide does not address themethodology ne
4、cessary to release a facility or site for uncon-ditional use. This guide specifically addresses:1.1.1 the data quality objective for characterization as aninitial step in decommissioning planning.1.1.2 sampling methods,1.1.3 the logic involved (statistical design) to ensure ad-equate characterizatio
5、n for decommissioning purposes; and1.1.4 essential documentation of the characterization infor-mation.1.2 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-priate safety and he
6、alth practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2E 1167 Guide for Radiation Protection Program for Decom-missioning OperationsE 1281 Guide for Nuclear Facility Decommissioning Plans3. Terminology3.1 Definitions:3.1.1 Ch
7、aracterization, nA systematic identification ofthe types, quantities, forms, and locations of contaminationwithin a facility.3.1.2 Decommission, vtTo remove safely from serviceand to reduce residual contamination to a level that permitstermination of any applicable licenses and release of thepropert
8、y for unrestricted use.3.1.3 Decontamination, nActivities employed to reducethe levels of (radioactive or hazardous chemical) contamina-tion in or on structures, equipment, materials and personnel.3.1.4 Facility, nAs applied to a decommissioning projectincludes the structure and the soil around and
9、under thestructure to an agreed upon distance.4. Requirements4.1 General:4.1.1 As an initial part of facility decommissioning plan-ning, a characterization plan is developed to define the nature,extent and location of contaminants, determine sampling loca-tions and protocols, determine quality assur
10、ance objectives forcharacterization, and define documentation requirements. Thecharacterization plan considers the historic use of the facility toidentify the likely contaminants due to the radiological processinvolved, the chemicals introduced during the processing, andany resulting contaminants th
11、at may be formed during theprocessing. Records or recounting of any process upsets orspills that may have occurred during the operating life of thefacility should be considered to help determine the likelylocation of contaminants. In addition to examining processrecords, interviews should be conduct
12、ed with personnel knowl-edgeable in the past operation of the facility to identifyconditions that may not have been recorded. During thispre-characterization data collection phase, an approach for thecharacterization plan is developed.4.2 Methodology:4.2.1 The actual characterization of a facility i
13、s an iterativeprocess that involves initial sampling according to the charac-terization plan, field management (such as labeling, packaging,storing, and transport) of the samples, laboratory analysis,conformance to the data quality objectives (DQOs), and thenidentifying any additional sampling requi
14、red, refining theDQOs, and modifying the characterization plan accordingly.The final product of the facility characterization is a documentthat describes the type, amount, and location of contaminants1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications an
15、d is the direct responsibility of SubcommitteeE10.03 on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities and Components.Current edition approved June 1, 2009. Published June 2009. Originallyapproved in 1997. Last previous edition approved in 2003 as E 1892-97(2003
16、).2For referenced ASTM standards, visit the ASTM website, 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.1Copyright ASTM International, 100 Barr Harbor Drive, PO Bo
17、x C700, West Conshohocken, PA 19428-2959, United States.that will require consideration and removal during the decom-missioning operations sufficient to prepare a decommissioningplan. Sufficient information must be provided to:1) estimate volumes for various waste types,2) plan work to keep radiatio
18、n exposure as low as reasonablyachievable (ALARA),3) plan work to keep exposures to hazardous materialsALARA, and4) support development of a decommissioning radiationprotection program based on guidance from E 1167.5. Significance and Use5.1 Knowledge of the nature and extent of contamination ina nu
19、clear facility to be decommissioned is crucial to choosingthe optimum methods for decontamination and decommission-ing, and estimating the resulting waste volumes and personnelexposures. Implementing a characterization plan, developed inaccordance with this standard, will result in obtaining orderiv
20、ing the above information.5.2 Information on the proposed decommissioning methods,waste volumes, and estimated personnel radiation exposurescan be used to define the overall work scope, costs, schedules,and manpower needs for the decommissioning project. Thisinformation may be included in the Decomm
21、issioning Plan.The extent of over- or under-estimating these project param-eters will be a function of the sampling plan and statisticaldesigns, described in Sections 6.1.4 and 6.1.5.6. Elements of Characterization Plan6.1 Radiological and hazardous constituent characterizationof a facility shall be
22、 conducted in accordance with a writtenplan. The plan must provide direction for the performance ofeffective sampling and inform concerned individuals as to theintent and methods used in the characterization process.Guidance on possible content and structure of such a writtenplan follows:6.1.1 Chara
23、cterization ObjectivesThe overall objectiveof the characterization task is to obtain information on thelocation, type, and amount of contaminants. This informationwill assist in the planning and performance of decommission-ing operations; and, the data collected during the characteriza-tion activity
24、 is valuable for source term evaluations to supportrisk assessments. Specific objectives must be clearly stated inthe characterization plan to ensure obtaining information that isrelevant to the decommissioning process.6.1.2 Data Quality ObjectivesData quality objectives(DQO) are quantitative and qu
25、alitative statements developedby data users to specify the quality of data needed from aparticular data collection activity. The development of DQOs isan iterative process involving both the data users and thetechnical staff. Establishment of the characterization objectiveleads to defining DQOs in t
26、he characterization plan. TheseDQOs are typically specified in terms of six characteristics:precision, accuracy, representativeness, completeness, compa-rability, and detection limit. For decommissioning planning theDQOs ensure that sufficient information is obtained to preparerequired National Envi
27、ronmental PolicyAct (NEPA) documen-tation and to support the detailed engineering.6.1.3 Background Information:6.1.3.1 Site LocationThe location and a description of thefacility relative to other facilities on the site and surroundingcommunities or environment should be described.6.1.3.2 Site Charac
28、teristicsA description of the entirenuclear facility to be decommissioned should be providedincluding results of surveys performed prior to initiation ofother decommissioning activities. The multi-agency documentMARSSIM describes site characteristics that should be ad-dressed including topography, s
29、oils and geology, hydrology,seismology, demography, and meteorology.3Specific detailssuch as those found in safety analysis reports may be providedin appendices or by reference. Facility characteristics thatshould be addressed include a general facility description, afacility structures description,
30、 and a facility systems descrip-tion. Radiological and hazardous material characteristics of thenuclear facility shall be included as well. The radionuclide andhazardous chemical inventory for the facility should be pre-sented with all of the major contributors identified and quan-tified. Environmen
31、tal as well as radiological characteristics ofthe site should be discussed as they affect exposure pathways.6.1.3.3 Facility UsesThe history of uses for the facilityshould be stated to give a perspective of the possible contami-nants that may be found in the characterization process.Included should
32、be a description of any process upsets or spillsthat may have occurred.6.1.3.4 Information SourcesSources of informationshould be identified and summarized, especially those relevantto possible contaminants, contaminating events, cleanup is-sues, and suspect areas. Previous samplings, facility waste
33、plans, radiations surveys, and local sampling problems shouldalso be included.6.1.4 Sampling Plan and Survey MethodologyAs de-scribed in the EPA document, Test Methods for EvaluatingSolid Waste, the sampling plan should provide specific loca-tions within the facility for instrument measurements andp
34、hysical sampling.4Examples are radiation field measurementsin all areas of the facility, scraping inside of piping, pumps, andother equipment, surface wipes for loose contamination, andcoring samples from concrete surfaces, as practical. Thesampling plan should be devised to minimize errors but must
35、meet the practical objective of providing only information thatis relevant to decommissioning planning and operations. In-cluded in the sampling plan must be a consideration ofALARAfor personnel exposure, contamination, and the costs associatedwith laboratory analyses and the possible benefit that m
36、ay beobtained by additional samples.6.1.4.1 The MARSSIM document provides information oninstrument selection, measurement protocols, and sample ac-quisition.3This document is intended to provide guidance inthese areas for EPA, NRC, DOE, and DOD and environmentalcleanup activities.3Multi-Agency Radia
37、tion Survey and Site Investigation Manual (MARSSIM),Rev 1, August 2000, Washington, DC NUREG-1575; DOE/EH-0624; EPA 402-R-97-0116.4Environmental Protection Agency, Test Methods for Evaluating Solid Waste,Physical/Chemical Methods Chapter 9, “Sampling Plan,” SW-846.E 1892 0926.1.5 Statistical Design
38、for CharacterizationA variety ofstatistical designs are available to meet characterization objec-tives. The designs range from random “grab” sampling (meet-ing specified statistical criteria) to a detailed grid specificallytailored to the expected contamination levels. The parametersof interest in a
39、ny characterization effort introduce severalsources of statistical uncertainty including those associatedwith sampling, instrumentation, and analyses. The develop-ment of the DQOs requires consideration of these sources ofuncertainty, an estimate of their magnitude, and if necessary, areview of the
40、methods to minimize the overall variability in acost-effective manner.6.1.5.1 The most common statistical tests used in decom-missioning are tests about the mean of a population, such as theStudents t-test. For these tests one infers information about themean of the population based on a comparative
41、ly small numberof random measurements. These measurements are used tocompute a sample average and standard deviation. Thesevalues are then used to estimate the population mean. Becauseof variation within the population and the randomness of thesamples, an uncertainty will always be associated with t
42、hisinferred sample mean.6.1.5.2 Statistical design, error tolerance, etc will be influ-enced by the current state of the decommissioning project.During the early planning stages large error can be toleratedsince one is trying to “get your arms around” the scope of theproject. Later into the project
43、when components are beingsurveyed for waste stream separation smaller error values arenecessary. Finally when the decommissioning is completed andfinal surveys are being performed, the allowable uncertainty isvery small.6.1.5.3 The MARSSIM document provides information onstatistical design.36.1.6 AL
44、ARA ConsiderationsThe desire for accurate datafrom the characterization effort must factor in ALARA consid-erations for obtaining the data. In cases of high radiation fieldsor excessive contamination levels, accurate measurementsand/or extensive sampling for laboratory analysis may notwarrant the he
45、alth risks associated with radiation dose topersonnel or possible contact with hazardous materials. Inthese cases, it is acceptable to estimate the required informa-tion by calculational method or extrapolations utilizing conser-vative methods.6.1.7 Quality AssuranceAs characterization data are ac-q
46、uired, the information should be examined to assure that theobjectives of the characterization plan are met. If the planobjectives are not being met, additional sampling may berequired, which should be addressed. EPA documentationprovides further guidance on quality assurance requirementsfor charact
47、erization activities.5,66.1.8 Quality Control:6.1.8.1 Quality Control SamplesThe characterization planshould specify that replicate, spike, and blank samples will beincluded in any set of samples to be sent to a laboratory foranalyses.6.1.8.2 Sample IdentificationUnique labels for sampleidentificati
48、on should be required by the characterization plan.The samples can then be tracked for chain of custody records,packing lists for transportation, laboratory verification ofreceipt, and sample tracking during analyses.6.1.8.3 Calibration ProceduresInstrumentation used forcharacterization data collect
49、ion should be calibrated using astandard source that has an activity level in the same range asthe expected level of the sample or radiation level of thefacility. Laboratory analysis equipment calibration is a routinetask performed by the laboratory and it is probably sufficient tospecify that calibrations be performed before and after thesample measurements are made.6.1.8.4 Performance and System AuditsSeveral methodsare employed to ensure that correct analyses are performed.Allanalyses should be performed according to a workplan, fol-lowing a QA/QC program. Data s
