1、Designation: D 5608 01 (Reapproved 2006)Standard Practices forDecontamination of Field Equipment Used at Low LevelRadioactive Waste Sites1This standard is issued under the fixed designation D 5608; the number immediately following the designation indicates the year oforiginal adoption or, in the cas
2、e of revision, 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. Scope*1.1 This practice covers the decontamination of field equip-ment used in the sampling of soil
3、s, soil gas, sludges, surfacewater, and ground water at waste sites known or suspected ofcontaining low level radioactive wastes.1.2 This practice is applicable at sites where low levelradioactive wastes are known or suspected to exist. Thispractice may also be applicable for the decontamination ofe
4、quipment used in known or suspected transuranic, or mixedwastes when used by itself or in conjunction with PracticeD 5088.1.3 Procedures are contained in this practice for the decon-tamination of equipment that comes into contact with thesample matrix (sample contacting equipment), and for ancil-lar
5、y equipment that has not contacted the sample, but may havebecome contaminated during use (non-contacting equipment).1.4 This practice is applicable to most conventional sam-pling equipment constructed of metallic and hard, smoothsynthetic materials. Materials with rough or porous surfaces, orhaving
6、 a high sorption rate should not be used in radioactivewaste sampling due to the difficulties with decontamination.1.5 In those cases where sampling will be periodicallyperformed, such as sampling of wells, consideration should begiven to the use of dedicated sampling equipment if legitimateconcerns
7、 exist for the production of undesirable or unmanage-able waste byproducts, or both, during the decontamination oftools and equipment.1.6 This practice does not address regulatory requirementsfor personnel protection or decontamination, or for the han-dling, labeling, shipping or storing of wastes,
8、or samples.Specific radiological release requirements and limits must bedetermined by users in accordance with local, state and federalregulations.1.7 For additional information see DOE Publication DOE/EH-0256T, DOE Order 5480.5, DOE Order 5480.11, and10CFR, Part 835.1.8 The values stated in SI unit
9、s are to be regarded as thestandard.1.9 This practice offers an organized collection of informa-tion or a series of options and does not recommend a specificcourse of action. This document can replace education orexperience and should be used in conjunction with professionaljudgement. Not all aspect
10、s of this practice may be applicable inall circumstances. This ASTM standard is not intended torepresent or replace the standard of care by which theadequacy of a given professional service must be judged norshould this document be applied without consideration of aprojects many unique aspects. The
11、word “standard” in thetitle of this document means only that the document has beenapproved through the ASTM consensus process.1.10 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 a
12、ppro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. Specific precau-tionary statements are given in Section 6.2. Referenced Documents2.1 ASTM Standards:2D 5088 Practices for Decontamination of Field EquipmentUsed at Waste Sites2.2 United S
13、tates Department of Energy Standards:DOE Publication DOE/EH-0256T Radiological ControlManual3DOE Order 5480.5 Radiation Protection of the Public andthe Environment3DOE Order 5480.11 Radiological Protection for Occupa-tional Workers32.3 United States Code of Federal Regulations:10CFR, Part 835, “Radi
14、ological Protection for Occupa-tional Workers”31This practice is under the jurisdiction of ASTM Committee D18 on Soil andRock and is the direct responsibility of Subcommittee D18.21 on Ground Water andVadose Zone Investigations.Current edition approved Sept. 15, 2006. Published November 2006. Origin
15、allyapproved in 2001. Last previous edition approved in 2001 as D 560801.2For 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 A
16、STM website.3Available from Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.1*A Summary of Changes section appears at the end of this standard.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.3. Termin
17、ology3.1 Definitions of Terms Specific to This Standard:3.1.1 as low as reasonable achievable (ALARA)an ap-proach to radiological control to manage exposures to the workforce and to the general public at levels as low as is reasonable,taking into account social, technical, economic, practical andpub
18、lic policy. ALARA has the objective of maintaining dosesat a level far below applicable controlling limits.3.1.2 barriera physical separation, such as a fence, wall,or temporary enclosure to prevent uncontrolled access andrelease from an area.3.1.3 contaminationeither fixed or removable radioactivem
19、aterials in or on an item.3.1.4 contamination reduction corridora defined pathwaythrough a hazardous waste site where decontamination occurs.3.1.5 decontaminationthe process of removing or reduc-ing to a known level undesirable physical, chemical, orradiological constituents from equipment. Decontam
20、ination ofsample contacting equipment maximizes the representative-ness of the physical, chemical, or radioactive analyses pro-posed for a given sample.3.1.6 fixed contaminationradioactive material that cannotbe readily removed from surfaces by nondestructive means,such as casual contact, wiping, br
21、ushing, or washing.3.1.7 inorganic desorbing agentsacid rinse solutions,typically of 10 % nitric or hydrochloric acid solutions madefrom reagent grade nitric or hydrochloric acid and deionizedwater (1 % should be applied to low-carbon steel equipment).3.1.8 mixed wasteswastes containing both radioac
22、tivity(as defined by the Atomic Energy Act) and quantities ofResource Conservation and Recovery Act (RCRA) listedwastes.3.1.9 non-contacting equipmentequipment used in andaround the sampling that may become contaminated, but thatdoes not contact the sample at anytime. Examples wouldinclude drilling
23、rigs, hand tools, drill rods, excavation equip-ment, or barrier materials.3.1.10 organic desorbing agentssolvent rinse solutions ofisopropanol, acetone, hexane, or methanol; pesticide grade.3.1.11 QC water (control rinse water)water having aknown chemistry, free (below detection levels) of organic o
24、rradiological constituents. Deionized water of reagent grade isnormally sufficient.3.1.12 radioactive wastewaste containing radioactive el-ements or activation regulated under the Atomic Energy Act,and is of negligible economic value, considering the cost ofrecovery. Waste is classified into three l
25、evels, all of which areharmful. The classifications are:3.1.12.1 low level wastewastes usually containing smallamounts of radioactivity in a large amount of material. Typi-cally the radioactivity dissipates in a relatively short period oftime, anywhere between 500 and 600 years, although some lowlev
26、el wastes may remain radioactive for longer periods. Ex-amples of Low Level Wastes are Uranium mining and milltailings, soils, equipment, sludges, or liquids contaminatedwith or mixed with radioactive materials. Naturally OccurringRadioactive Materials (NORM) also fall into this classification.Typic
27、al examples of NORM low level wastes include uraniumand thorium bearing sludges from water purification plants,high grade uranium ores, and petroleum pipeline sludges.3.1.12.2 mid level (transuranic) wasteswastes containingcontamination with radioactive man-made elements havingatomic weights greater
28、 than uranium (hence the name trans (orbeyond) uranic). Examples of mid level wastes include liquids,sludges, resins, or soils and equipment contaminated or mixedwith plutonium or other man-made alpha emitting radionu-clides with half-lives of greater than 20 years and concentra-tions greater than 1
29、00 nCi/g at the time of assay.3.1.12.3 high level wasteswastes of highly concentratedradionuclides with long half-lives. Examples of high levelwastes include spent nuclear fuels, nuclear fuel reprocessingwastes, syrups, and resins.3.1.13 removable contaminationradioactive material thatcan be removed
30、 from surfaces by nondestructive means, suchas brushing, wiping, or washing.3.1.14 rinse waterwater having a known chemistry.Deionized or distilled water may be used when small quantitiesare required. When large quantities are required, potable waterof a chemistry known to be free (below detection l
31、evels) ofradioactive or chemical constituents can be used.3.1.15 sample contacting equipmentequipment and toolsthat physically come in contact with a sample and that couldallow cross-contamination from one sample to another. Ex-amples include drive cylinders, bailers, sample handling,equipment, pump
32、s, and sampling tubes.3.1.16 surveya radiation measurement with instrumenta-tion to evaluate and assess the presence of radioactive materialsor other sources of radiation under a specific set of conditions,(also known as frisking).3.1.17 unrestricted release limitthe maximum contamina-tion that an i
33、tem may exhibit to be released for uncontrolleduse by the public. Release limits differ, based on the type ofradioactive materials and the amount and type of emissions(gamma, alpha, beta).3.1.18 wipe testa radiation detection test performed todetermine the amount of removable radioactive material pe
34、r100 cm2surface area by wiping with a dry filter or softabsorbent paper with moderate pressure and then assessing theamount of radioactivity with an instrument of appropriateefficiency. A radiological survey and a wipe test is generallyrequired for release of any equipment from a radiological areato
35、 an uncontrolled area or for unrestricted use, (also known asswipe test).4. Summary of Practice4.1 This practice provides guidance and details for thedevelopment of a site and sampling event specific decontami-nation plan for use in the decontamination of field equipmentused during sampling or other
36、 activities in areas known, orsuspected of containing low-level radioactive wastes. Fourtechniques or methods are provided, with the selection and usebased on the type of contamination and the difficulty ofremoval.4.2 Approaches and procedures are provided for decontami-nation of two classifications
37、 of equipment, sample-contactingand non-contacting.D 5608 01 (2006)24.3 This practice includes the principles of ALARA andwaste minimization as well as the protection of sample dataquality.5. Significance and Use5.1 The primary objectives of work at low-level radioactivewaste sites are the protectio
38、n of personnel, prevention of thespread of contamination, minimization of additional wastes,protection of sample data quality, and the unconditional releaseof equipment used.5.2 Preventing the contamination of equipment used atlow-level radioactive waste sites and the decontamination ofcontaminated
39、equipment are key aspects of achieving thesegoals.5.3 This practice provides guidance in the planning of workto prevent contamination and when necessary, for the decon-tamination of equipment that has become contaminated. Thebenefits include:5.3.1 Minimizing the spread of contamination within a site
40、and preventing the spread outside of the work area.5.3.2 Reducing the potential exposure of workers during thework and the subsequent decontamination of equipment.5.3.3 Minimizing the amounts of additional wastes gener-ated during the work, including liquid, or mixed wastes,including separation of t
41、he waste types, such as protectiveclothing, cleaning equipment, cleaning solutions, and protec-tive wraps and drapes.5.3.4 Improving the quality of sample data and reliability.5.4 This practice may not be applicable to all low-levelradioactive waste sites, such as sites containing low-levelradioacti
42、ve wastes mixed with chemical or reactive wastes.Field personnel, with assistance from trained radiologicalcontrol professionals, should have the flexibility to modify thedecontamination procedures with due consideration for thesampling objectives, or if past experience supports alternativeprocedure
43、s for contamination protection or decontamination.5.5 This practice does not address the monitoring, protec-tion, or decontamination of personnel working with low-levelradioactive wastes.5.6 This practice does not address regulatory requirementsthat may control or restrict work, the need for permits
44、 orregulatory approvals, or the accumulation or handling ofgenerated wastes.6. Hazards6.1 Equipment decontamination activities involving radio-active constituents provide numerous opportunities for person-nel contamination and radiation exposure, the uncontrolledspread of contamination, and the unne
45、cessary generation ofadditional radioactive or mixed wastes.6.2 Personnel involved in the decontamination of fieldequipment used in a known or suspected radiologically con-taminated site must be trained and qualified in the work beingperformed and in emergency procedures.6.3 Any work performed in a
46、known or suspected radiologi-cally contaminated site should be under the continuous controlof a trained Radiological Control Technician.6.4 Strict controls around the work area must be maintainedat all times to prevent the access or egress of personnel,equipment, or samples to prevent unnecessary ex
47、posure, un-controlled releases of contaminated equipment or personnel,and unnecessary contamination of equipment. The controlswill include barriers, such as fences, temporary building, orother enclosures to prevent access or egress without propermonitoring and decontamination.6.5 Personnel working i
48、n a radiologically contaminated areahave the potential for receiving radiation exposure as well asinternal and external contamination. Personnel shall be trainedto the Site Specific Health and Safety Plan which specifies therequired training, personnel protection, and dosimetry equip-ment required.6
49、.6 Some decontamination solutions may be hazardous tohumans, or may be incompatible with personnel protectiveclothing normally worn. For example, organic solvents or acidsmay permeate or degrade protective clothing or equipment.Protective clothing worn during decontamination should beselected for wet work involving the specific chemicals andsolutions to be used.6.7 Chemicals and solutions used during decontaminationmay be hazardous. Personnel involved should be properlytrained and provided with Material Safety Data Sheets (MS-DSs), and the appropriate emergency e
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