ASTM E1892-2015 Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities《编制核设备退役特征计划的标准指南》.pdf

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1、Designation: E1892 09E1892 15Standard Guide forPreparing Characterization Plans for DecommissioningNuclear Facilities1This standard is issued under the fixed designation E1892; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the ye

2、ar 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.1. Scope1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude,

3、 location, andextent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifiesguidance regarding facility characterization indicated inASTM Standard E1281 on Nuclear Facility Decommissioning Plans. Thisguide does not address the methodolog

4、y necessary to release a facility or site for unconditional use. This guide specificallyaddresses:1.1.1 the data quality objective for characterization as an initial step in decommissioning planning.1.1.2 sampling methods,1.1.3 the logic involved (statistical design) to ensure adequate characterizat

5、ion for decommissioning purposes; and1.1.4 essential documentation of the characterization information.1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety and h

6、ealth practices and determine the applicability of regulatorylimitations prior to use.2. Referenced Documents2.1 ASTM Standards:2E1167 Guide for Radiation Protection Program for Decommissioning OperationsE1281 Guide for Nuclear Facility Decommissioning Plans2.2 ANSI Standard:3ANSI N323AB American Na

7、tional Standard for Radiation Protection Instrumentation Test and Calibration, Portable SurveyInstruments3. Terminology3.1 Definitions:3.1.1 Characterization, nA systematic identification of the types, quantities, forms, and locations of contamination within afacility.3.1.2 Decommission, vtTo remove

8、 safely from service and to reduce residual contamination to a level that permits terminationof any applicable licenses and release of the property for unrestricted use.3.1.3 Decontamination, nActivities employed to reduce the levels of (radioactive or hazardous chemical) contamination in oron struc

9、tures, equipment, materials and personnel.3.1.4 Facility, nAs applied to a decommissioning project includes the structure and the soil around and under the structureto an agreed upon distance.4. Requirements4.1 General:1 This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technolog

10、y and Applicationsand is the direct responsibility of Subcommittee E10.03 onRadiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.Current edition approved June 1, 2009Jan. 1, 2015. Published June 2009January 2015. Originally approved in 1997. Last previ

11、ous edition approved in 20032009 asE1892-97(2003).E1892-09. DOI: 10.1520/E1892-09.10.1520/E1892-15.2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Docu

12、ment Summary page on the ASTM website.3 Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http:/www.ansi.org.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have

13、 been made to the previous version. Becauseit may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official docu

14、ment.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States14.1.1 As an initial part of facility decommissioning planning, a characterization plan is developed to define the nature, extentand location of contaminants, determine sampling loca

15、tions and protocols, determine quality assurance objectives forcharacterization, and define documentation requirements. The characterization plan considers the historic use of the facility toidentify the likely contaminants due to the radiological process involved, the chemicals introduced during th

16、e processing, and anyresulting contaminants that may be formed during the processing. Records or recounting of any process upsets or spills that mayhave occurred during the operating life of the facility should be considered to help determine the likely location of contaminants.In addition to examin

17、ing process records, interviews should be conducted with personnel knowledgeable in the past operation ofthe facility to identify conditions that may not have been recorded. During this pre-characterization data collection phase, anapproach for the characterization plan is developed.4.2 Methodology:

18、4.2.1 The actual characterization of a facility is an iterative process that involves initial sampling according to thecharacterization plan, field management (such as labeling, packaging, storing, and transport) of the samples, laboratory analysis,conformance to the data quality objectives (DQOs),

19、and then identifying any additional sampling required, refining the DQOs, andmodifying the characterization plan accordingly. The final product of the facility characterization is a document that describes thetype, amount, and location of contaminants that will require consideration and removal duri

20、ng the decommissioning operationssufficient to prepare a decommissioning plan. Sufficient information must be provided to:1) estimate volumes for various waste types,2) plan work to keep radiation exposure as low as reasonably achievable (ALARA),3) plan work to keep exposures to hazardous materials

21、ALARA, and4) support development of a decommissioning radiation protection program based on guidance from E1167.5. Significance and Use5.1 Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing theoptimum methods for decontamination and

22、decommissioning, and estimating the resulting waste volumes and personnelexposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or derivingthe above information.5.2 Information on the proposed decommissioning methods, waste volumes, and

23、estimated personnel radiation exposures canbe used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This informationmay be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a functiono

24、f the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.6. Elements of Characterization Plan6.1 Radiological and hazardous constituent characterization of a facility shall be conducted in accordance with a written plan.The plan must provide direction for the performance of

25、 effective sampling and inform concerned individuals as to the intent andmethods used in the characterization process. Guidance on possible content and structure of such a written plan follows:6.1.1 Characterization ObjectivesThe overall objective of the characterization task is to obtain informatio

26、n on the location,type, and amount of contaminants. This information will assist in the planning and performance of decommissioning operations;and, the data collected during the characterization activity is valuable for source term evaluations to support risk assessments.Specific objectives must be

27、clearly stated in the characterization plan to ensure obtaining information that is relevant to thedecommissioning process.6.1.2 Data Quality ObjectivesData quality objectives (DQO) are quantitative and qualitative statements developed by datausers to specify the quality of data needed from a partic

28、ular data collection activity. The development of DQOs is an iterativeprocess involving both the data users and the technical staff. Establishment of the characterization objective leads to defining DQOsin the characterization plan. These DQOs are typically specified in terms of six characteristics:

29、 precision, accuracy,representativeness, completeness, comparability, and detection limit. For decommissioning planning the DQOs ensure thatsufficient information is obtained to prepare required National Environmental Policy Act (NEPA) documentation and to supportthe detailed engineering.6.1.3 Backg

30、round Information:6.1.3.1 Site LocationThe location and a description of the facility relative to other facilities on the site and surroundingcommunities or environment should be described.6.1.3.2 Site CharacteristicsA description of the entire nuclear facility to be decommissioned should be provide

31、d includingresults of surveys performed prior to initiation of other decommissioning activities. The multi-agency document MARSSIMdescribes site characteristics that should be addressed including topography, soils and geology, hydrology, seismology,demography, and meteorology.4 Specific details such

32、 as those found in safety analysis reports may be provided in appendices or4 Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), Rev 1,August 2000, Washington, DC NUREG-1575; DOE/EH-0624; EPA402-R-97-0116.E1892 152by reference. Facility characteristics that should be addressed inc

33、lude a general facility description, a facility structures description,and a facility systems description. Radiological and hazardous material characteristics of the nuclear facility shall be included aswell. The radionuclide and hazardous chemical inventory for the facility should be presented with

34、 all of the major contributorsidentified and quantified. Environmental as well as radiological characteristics of the site should be discussed as they affectexposure pathways.6.1.3.3 Facility UsesThe history of uses for the facility should be stated to give a perspective of the possible contaminants

35、that may be found in the characterization process. Included should be a description of any process upsets or spills that may haveoccurred.6.1.3.4 Information SourcesSources of information should be identified and summarized, especially those relevant to possiblecontaminants, contaminating events, cl

36、eanup issues, and suspect areas. Previous samplings, facility waste plans, radiations surveys,and local sampling problems should also be included.6.1.4 Sampling Plan and Survey MethodologyAs described in the EPA document, Test Methods for Evaluating Solid Waste,the sampling plan should provide speci

37、fic locations within the facility for instrument measurements and physical sampling.5Examples are radiation field measurements in all areas of the facility, scraping inside of piping, pumps, and other equipment,surface wipes for loose contamination, and coring samples from concrete surfaces, as prac

38、tical. The sampling plan should bedevised to minimize errors but must meet the practical objective of providing only information that is relevant to decommissioningplanning and operations. Included in the sampling plan must be a consideration ofALARAfor personnel exposure, contamination,and the cost

39、s associated with laboratory analyses and the possible benefit that may be obtained by additional samples.6.1.4.1 The MARSSIM document provides information on instrument selection, measurement protocols, and sampleacquisition.4 This document is intended to provide guidance in these areas for EPA, NR

40、C, DOE, and DOD and environmentalcleanup activities.6.1.5 Statistical Design for CharacterizationA variety of statistical designs are available to meet characterization objectives.The designs range from random “grab” sampling (meeting specified statistical criteria) to a detailed grid specifically t

41、ailored to theexpected contamination levels. The parameters of interest in any characterization effort introduce several sources of statisticaluncertainty including those associated with sampling, instrumentation, and analyses. The development of the DQOs requiresconsideration of these sources of un

42、certainty, an estimate of their magnitude, and if necessary, a review of the methods to minimizethe overall variability in a cost-effective manner.6.1.5.1 The most common statistical tests used in decommissioning are tests about the mean of a population, such as theStudents t-test. For these tests o

43、ne infers information about the mean of the population based on a comparatively small numberof random measurements. These measurements are used to compute a sample average and standard deviation. These values arethen used to estimate the population mean. Because of variation within the population an

44、d the randomness of the samples, anuncertainty will always be associated with this inferred sample mean.6.1.5.2 Statistical design, error tolerance, etc will be influenced by the current state of the decommissioning project. During theearly planning stages large error can be tolerated since one is t

45、rying to “get your arms around” the scope of the project. Later intothe project when components are being surveyed for waste stream separation smaller error values are necessary. Finally when thedecommissioning is completed and final surveys are being performed, the allowable uncertainty is very sma

46、ll.6.1.5.3 The MARSSIM document provides information on statistical design.46.1.6 ALARA ConsiderationsThe desire for accurate data from the characterization effort must factor in ALARAconsiderations for obtaining the data. In cases of high radiation fields or excessive contamination levels, accurate

47、 measurementsand/or extensive sampling for laboratory analysis may not warrant the health risks associated with radiation dose to personnel orpossible contact with hazardous materials. In these cases, it is acceptable to estimate the required information by calculationalmethod or extrapolations util

48、izing conservative methods.6.1.7 Quality AssuranceAs characterization data are acquired, the information should be examined to assure that theobjectives of the characterization plan are met. If the plan objectives are not being met, additional sampling may be required, whichshould be addressed. EPA

49、documentation provides further guidance on quality assurance requirements for characterizationactivities.6,76.1.8 Quality Control:6.1.8.1 Quality Control SamplesThe characterization plan should specify that replicate, spike, and blank samples will beincluded in any set of samples to be sent to a laboratory for analyses.6.1.8.2 Sample IdentificationUnique labels for sample identification should be required by the characterization plan. Thesamples can then be tracked for chain of custody records, packing lists for transportation, laboratory verification of receipt, a