ASTM D5608-2010 3125 Standard Practices for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites《用于低水平放射性废物场所的现场设备去污染标准规范》.pdf

《ASTM D5608-2010 3125 Standard Practices for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites《用于低水平放射性废物场所的现场设备去污染标准规范》.pdf》由会员分享，可在线阅读，更多相关《ASTM D5608-2010 3125 Standard Practices for Decontamination of Field Equipment Used at Low Level Radioactive Waste Sites《用于低水平放射性废物场所的现场设备去污染标准规范》.pdf（8页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: D5608 10Standard Practices forDecontamination of Field Equipment Used at Low LevelRadioactive Waste Sites1This standard is issued under the fixed designation D5608; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the y

2、ear 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. Scope*1.1 These practices cover the decontamination of fieldequipment used in the sampling of soils, soil gas, sludges,s

3、urface water and ground water at waste sites known orsuspected of containing 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 ofequipment used in known

4、or suspected transuranic, or mixedwastes when used by itself or in conjunction with PracticeD5088.1.3 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-lary equipment that has not

5、 contacted the sample, but may havebecome contaminated during use (non-contacting equipment).For sample contacting equipment there are four separateprocedures (Procedure A through D) in Section 8. For non-contacting equipment, one procedure is presented as covered inSection 9.1.4 This practice is ap

6、plicable to most conventional sam-pling equipment constructed of metallic and hard, smoothsynthetic materials. Materials with rough or porous surfaces, orhaving a high sorption rate should not be used in radioactivewaste sampling due to the difficulties with decontamination.1.5 In those cases where

7、sampling will be periodicallyperformed, such as sampling of wells, consideration should begiven to the use of dedicated sampling equipment if legitimateconcerns exist for the production of undesirable or unmanage-able waste byproducts, or both, during the decontamination oftools and equipment.1.6 Th

8、is practice does not address regulatory requirementsfor personnel protection or decontamination, or for the han-dling, labeling, shipping, or storing of wastes or samples.Specific radiological release requirements and limits must bedetermined by users in accordance with local, state and federalregul

9、ations.1.7 For additional information in the United States, see U.S.Department of Energy (DOE) 10 CFR Part 835 and U.S.Nuclear Regulatory Commission (NRC) 10 CFR Part 20.1.8 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.1.9 Th

10、is practice offers an organized collection of informa-tion or a series of options and does not recommend a specificcourse of action. This document cannot replace education orexperience and should be used in conjunction with professionaljudgement. Not all aspects of this practice may be applicable in

11、all 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 word “standard” in thetitle of this doc

12、ument 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 appro-priate safety and health practices

13、 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:2D653 Terminology Relating to Soil, Rock, and ContainedFluidsD5088 Practice for Decontamination of Field EquipmentUsed at Wast

14、e Sites2.2 United States Code of Federal Regulations:310 CFR Part 20 Standards for Protection Against Radiation10 CFR Part 835 Radiological Protection for OccupationalWorkers1This practice is under the jurisdiction of ASTM Committee D18 on Soil andRock and is the direct responsibility of Subcommitte

15、e D18.21 on Ground Water andVadose Zone Investigations.Current edition approved May 1, 2010. Published June 2010. Originallyapproved in 2001. Last previous edition approved in 2006 as D560801(2006).DOI: 10.1520/D5608-10.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact

16、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 Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.1*A Summary of Changes section appears at t

17、he end of this standard.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 as low as reasonable achievable (ALARA)an ap-proach to radiological control to manage expos

18、ures to the workforce and to the general public at levels as low as is reasonable,taking into account social, technical, economic, practical andpublic policy. ALARA has the objective of maintaining dosesat a level far below applicable controlling limits.3.1.2 barriera physical separation, such as a

19、fence, wall,or temporary enclosure to prevent uncontrolled access andrelease from an area.3.1.3 contaminationeither fixed or removable radioactivematerials in or on an item.3.1.4 contamination reduction corridora defined pathwaythrough a hazardous waste site where decontamination occurs.3.1.5 decont

20、aminationthe process of removing or reduc-ing to a known level undesirable physical, chemical, orradiological constituents from equipment. Decontamination ofsample contacting equipment maximizes the representative-ness of the physical, chemical, or radioactive analyses pro-posed for a given sample.3

21、.1.6 fixed contaminationradioactive material that cannotbe readily removed from surfaces by nondestructive means,such as casual contact, wiping, brushing, or washing.3.1.7 inorganic desorbing agentsacid rinse solutions,typically of 10 % nitric or hydrochloric acid solutions madefrom reagent grade ni

22、tric or hydrochloric acid and deionizedwater (1 % should be applied to low-carbon steel equipment).The desorbing agent may include dilute sodium hydroxide.3.1.8 mixed wasteswastes containing both radioactivity(as defined by the United States Atomic Energy Act of 1954 asamended) and quantities of Uni

23、ted States Environmental Pro-tection Agency Resource Conservation and Recovery Act(RCRA) listed wastes.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 rigs, hand tools,

24、 drill rods, excavation equip-ment, or barrier materials.3.1.10 organic desorbing agentssolvent rinse solutions ofisopropanol, acetone, hexane, or methanol.3.1.11 QC water (control rinse water)water having aknown chemistry, free (below detection levels) of organic orradiological constituents. Deioni

25、zed water of reagent grade isnormally sufficient.3.1.12 radioactive wastewaste containing radioactive el-ements or activation of negligible economic value, consideringthe cost of recovery or use. Waste can generally be classifiedinto three levels, all of which are harmful. The classificationsare:3.1

26、.12.1 low level wastewastes usually containing smallamounts of radioactivity in a large amount of material. Typi-cally the radioactivity decays in a relatively short period oftime, within 500 years, although some low level wastes mayremain radioactive for much longer periods. Low level radio-active

27、wastes are those that are not high or mid level wastes.Examples 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.Typi

28、cal 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 greate

29、r 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.3.1.12.3 high level wasteswastes of highly concentratedradionuclides with

30、long half-lives. Examples of high levelwastes include spent nuclear fuels, nuclear fuel reprocessingwastes, syrups, and resins.3.1.13 radiological control technician (RCT)Individualswho protect people and the environment from the unwantedeffects of radiation through the principles of time, distance,

31、 andshielding. Also referred to by other titles including RadiationSafety Technicians, Health Physics Technician, Radiation Pro-tection Technicians.3.1.14 removable contaminationradioactive material thatcan be removed from surfaces by nondestructive means, suchas brushing, wiping, or washing.3.1.15

32、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 levels) ofradioactive or chemical constituents can be used.3.1.16 sample contacting

33、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, pumps, and sampling tubes.3.1.17 surveya radiation measurement with instrumenta-tion to

34、 evaluate and assess the presence of radioactive materialsor other sources of radiation under a specific set of conditions,(also known as frisking).3.1.18 unrestricted release limitthe maximum contamina-tion that an item may exhibit to be released for uncontrolleduse by the public. Release limits di

35、ffer, based on the type ofradioactive materials and the amount and type of emissions(gamma, alpha, beta).3.1.19 wipe testa radiation detection test performed todetermine the amount of removable radioactive material per100 cm2surface area by wiping with a dry filter or softabsorbent paper with modera

36、te 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 an uncontrolled area or for unrestricted use, (also known asswipe test).3.2 All ot

37、her terms and definitions are in accordance withTerminology D653.D5608 1024. 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 othe

38、r 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 classification

39、s of equipment, sample-contactingand non-contacting.4.3 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 protection of personnel,

40、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 equipment are ke

41、y 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 siteand preventing t

42、he 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 the waste types,

43、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-levelradioactive wastes mixed

44、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 alternativeprocedures for contaminat

45、ion 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 orregulatory ap

46、provals, or the accumulation, handling, or dis-posal of generated 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 unneces

47、sary 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 kno

48、wn 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 expos

49、ure, 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 in 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 d