1、Designation: E 1892 97 (Reapproved 2003)Standard 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 revi
2、sion, 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.1. Scope1.1 This standard guide applies to developing nuclear facil-ity characterization plans to define the ty
3、pe, magnitude, loca-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 addres
4、s themethodology necessary 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-equ
5、ate characterization 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-p
6、riate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:E 1167 Standard Guide for Radiation Protection Programfor Decommissioning Operations2E 1278 Standard Guide for Radioactive Pathway Method-ology for Rele
7、ase of Sites Following Decommissioning2E 1281 Standard Guide for Nuclear Facility Decommission-ing Plans23. Terminology3.1 Definitions:3.1.1 Characterization, nA systematic identification ofthe types, quantities, forms, and locations of contaminationwithin a facility.3.1.2 Decommission, vtTo remove
8、safely from serviceand to reduce residual contamination to a level that permitstermination of any applicable licenses and release of theproperty for unrestricted use.3.1.3 Decontamination, nActivities employed to reducethe levels of (radioactive or hazardous chemical) contamina-tion in or on structu
9、res, equipment, materials and personnel.3.1.4 Facility, nAs applied to a decommissioning projectincludes the structure and the soil around and 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 p
10、lan is developed to define the nature,extent and location of contaminants, determine sampling loca-tions and protocols, determine quality assurance objectives forcharacterization, and define documentation requirements. Thecharacterization plan considers the historic use of the facility toidentify th
11、e likely contaminants due to the radiological processinvolved, the chemicals introduced during the processing, andany resulting contaminants that may be formed during theprocessing. Records or recounting of any process upsets orspills that may have occurred during the operating life of thefacility s
12、hould be considered to help determine the likelylocation of contaminants. In addition to examining processrecords, interview should be conducted with personnel knowl-edgeable in the past operation of the facility to identifyconditions that may not have been recorded. During thispre-characterization
13、data collection phase, an approach for thecharacterization plan is developed.4.2 Methodology:4.2.1 The actual characterization of a facility is an iterativeprocess that involves initial sampling according to the charac-terization plan, field management (such as labeling, packaging,storing, and trans
14、port) of the samples, laboratory analysis,conformance to the data quality objectives (DQOs), and thenidentifying any additional sampling required, refining theDQOs, and modifying the characterization plan accordingly.The final product of the facility characterization is a documentthat describes the
15、type, amount, and location of contaminants1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of Subcommittee E10.03 on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities and Components.C
16、urrent edition approved June 10, 1997. Published October 1997.2Annual Book of ASTM Standards, Vol 12.02.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.that will require consideration and removal during the decom-missioning operation
17、s sufficient to prepare a decommissioningplan. Sufficient information must be provided to:1) estimate volumes for various waste types2) plan work to keep radiation exposure as low as reasonablyachievable (ALARA)3) plan work to keep exposures to hazardous materialsALARA5. Significance and Use5.1 Know
18、ledge of the nature and extent of contamination ina nuclear 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 inaccordanc
19、e with this standard, will result in obtaining orderiving 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
20、project. Thisinformation may be included in the Decommissioning 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 hazard
21、ous constituent characterizationof a facility shall be 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 a
22、nd structure of such a writtenplan follows:6.1.1 Characterization 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, th
23、e data collected during the characteriza-tion activity 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 Objectiv
24、esData quality objectives(DQO) are quantitative and qualitative 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
25、 characterization objectiveleads to defining DQOs in the 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 in
26、formation is obtained to preparerequired National Environmental Policy Act (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
27、 or environment should be described.6.1.3.2 Site CharacteristicsA description of the entirenuclear facility to be decommissioned should be providedincluding results of surveys performed prior to initiation ofother decommissioning activities. As described in the U. S.Department of Energy document, A
28、Guide for RadiologicalCharacterization and Measurement for Decommissioning of U.S. Department of Energy Surplus Facilities, site characteristicsthat should be addressed include topography, soils and geology,hydrology, seismology, demography, and meteorology.3Spe-cific details such as those found in
29、safety analysis reports maybe provided in appendices or by reference. Facility character-istics that should be addressed include a general facilitydescription, a facility structures description, and a facilitysystems description. Radiological and hazardous material char-acteristics of the nuclear fa
30、cility shall be included as well. Theradionuclide and hazardous chemical inventory for the facilityshould be presented with all of the major contributors identifiedand quantified. Environmental as well as radiological charac-teristics of the site should be discussed as they affect exposurepathways.6
31、.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 be a description of any process upsets or spillsthat may have occurred.6.1.3.4 Information SourcesSources of
32、informationshould be identified and summarized, especially those relevantto possible contaminants, contaminating events, cleanup is-sues, and suspect areas. Previous samplings, facility wasteplans, radiations surveys, and local sampling problems shouldalso be included.6.1.4 Sampling Plan and Survey
33、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 andphysical sampling.4Examples are radiation field measurementsin all areas of the facility, scraping inside of p
34、iping, pumps, andother equipment, surface wipes for loose contamination, andcoring samples from concrete surfaces, as practical. Thesampling plan should be devised to minimize errors but mustmeet the practical objective of providing only information thatis relevant to decommissioning planning and op
35、erations. In-cluded in the sampling plan must be a consideration of ALARAfor personnel exposure, contamination, and the costs associatedwith laboratory analyses and the possible benefit that may beobtained by additional samples.3U. S. Department of Energy, A Guide for Radiological Characterization a
36、ndMeasurement for Decommissioning of U. S. Department of Energy SurplusFacilities, DOE/EP-0100, 1983.4Environmental Protection Agency, Test Methods for Evaluating Solid Waste,Chapter 9, “Sampling Plan,” SW-846.E 1892 97 (2003)26.1.4.1 The MARSSIM document provides information oninstrument selection,
37、 measurement protocols, and sample ac-quisition.5This document is intended to provide guidance inthese areas for EPA, NRC, DOE, D decommissioning; characterization;radiation surveys; facility surveys; contamination surveysASTM International takes no position respecting the validity of any patent rig
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41、TM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959,United States. Individual reprints (single or multiple copies) of this standard may be obtained by contacting ASTM at the aboveaddress or at 610-832-9585 (phone), 610-832-9555 (fax), or serviceastm.org (e-mail); or through the ASTM website(www.astm.org).E 1892 97 (2003)4
