ASTM D5608-2016 0817 Standard Practices for Decontamination of Sampling and Non Sample Contacting Equipment Used at Low Level Radioactive Waste Sites《低水平放射性废物场所使用取样或非样品接触设备去污染的标准实施.pdf

《ASTM D5608-2016 0817 Standard Practices for Decontamination of Sampling and Non Sample Contacting Equipment Used at Low Level Radioactive Waste Sites《低水平放射性废物场所使用取样或非样品接触设备去污染的标准实施.pdf》由会员分享，可在线阅读，更多相关《ASTM D5608-2016 0817 Standard Practices for Decontamination of Sampling and Non Sample Contacting Equipment Used at Low Level Radioactive Waste Sites《低水平放射性废物场所使用取样或非样品接触设备去污染的标准实施.pdf（9页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: D5608 16Standard Practices forDecontamination of Sampling and Non Sample ContactingEquipment Used at Low Level Radioactive Waste Sites1This standard is issued under the fixed designation D5608; the number immediately following the designation indicates the year oforiginal adoption or, i

2、n the case of revision, the year 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 samplingand non-sample contacting eq

3、uipment used in the sampling ofsoils, soil gas, sludges, surface water and groundwater at wastesites known or suspected of containing low level radioactivewastes. It may also have application for decontamination ofsampling and heavy construction equipment used during reme-diation activities.1.2 This

4、 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 or suspected transuranic, or mixedwastes when used by itself or in conjunction with PracticeD5088.1.3 Procedures a

5、re 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 contacted the sample, but may havebecome contaminated during use (non-contacting equipment).For sample contacting

6、 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 The user is reminded of the importance of properdecontamination planning to minimize the amount of decon-tamination wastes generated

7、and to reduce or eliminate the useof cleaning agents that are themselves hazardous materials.Quality Assurance/Quality Control (QA/QC) radiological sur-veys and samples that document decontamination effectivenesscan be used to modify or enhance decontamination techniques.1.5 This practice is applica

8、ble 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.1.6 In those cases where sampl

9、ing 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.1.7 This pr

10、actice does not address regulatory requirementsfor personnel protection or decontamination, or for thehandling, labeling, shipping, or storing of wastes or samples.Specific radiological release requirements and limits must bedetermined by users in accordance with local, state and federalregulations.

11、1.8 Other jurisdictions may have equivalent requirements.For additional information in the United States, for example,see United States Department of Energy (DOE) 10 CFR Part835 and U.S. Nuclear Regulatory Commission (NRC) 10 CFRPart 20.1.9 The values stated in SI units are to be regarded asstandard

12、. No other units of measurement are included in thisstandard.1.10 This practice offers an organized collection of infor-mation or a series of options and does not recommend aspecific course of action. This document cannot replace edu-cation or experience and should be used in conjunction withprofess

13、ional judgement. Not all aspects of this practice may beapplicable in all circumstances. This ASTM standard is notintended to represent or replace the standard of care by whichthe adequacy of a given professional service must be judgednor should this document be applied without consideration ofa pro

14、jects many unique aspects. The word “standard” in thetitle of this document means only that the document has beenapproved through the ASTM consensus process.1.11 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is the1This practice is under the

15、 jurisdiction of ASTM Committee D18 on Soil andRock and is the direct responsibility of Subcommittee D18.21 on Groundwater andVadose Zone Investigations.Current edition approved Feb. 1, 2016. Published February 2016. Originallyapproved in 2001. Last previous edition approved in 2010 as D560810. DOI:

16、10.1520/D5608-16.*A Summary of Changes section appears at the end of this standardCopyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1responsibility of the user of this standard to establish appro-priate safety and health practices and de

17、termine 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 ContainedFluidsD1193 Specification for Reagent WaterD5088 Practice for Decontamination

18、of Field EquipmentUsed at Waste Sites2.2 United States Code of Federal Regulations:310 CFR Part 20 Standards for Protection Against Radiation10 CFR 6010 CFR Part 835 Radiological Protection for OccupationalWorkers2.3 Multi-Agency Radiation Survey and Site InvestigationManual (MARSSIM), Nureg-1575, R

19、ev 1, EPA 402-R-97-016,Rev 1, DOE/EH-0624, Rev 1ANSI/HPS N13.12 Surface and Volume RadioactivityStandards for Clearance3. Terminology3.1 Definitions:3.1.1 For definitions of general technical terms used withinthis practice refer to Terminology D653.3.2 General Definitions Used in This Practice3.2.1

20、as low as reasonably achievable (ALARA)a processused for radiation protection to manage and control exposures(both individual and collective to the work force and to thegeneral public) and releases of radioactive materials to theenvironment so that the levels are as low as is reasonabletaking into a

21、ccount social, technical, economic, practical, andpublic policy consideration (from ANSI/HPS N13.12).3.2.2 contaminationeither fixed or removable radioactivematerials in or on an item where it is not wanted.3.2.2.1 DiscussionRadioactive materials in a glovebox,for example, are not contamination.3.2.

22、3 mixed wasteswastes containing both radioactivity(as defined by the United States Atomic Energy Act of 1954 asamended) and quantities of United States Environmental Pro-tection Agency Resource Conservation and Recovery Act(RCRA) listed wastes.3.2.4 radioactive wastewaste containing radioactive ele-

23、ments or activation of negligible economic value, consideringthe cost of recovery or use.3.3 Definitions of Terms Specific to This Standard:3.3.1 controlled areaan area to which access is physicallylimited in order to protect individuals from exposure toradiation, contamination, hazardous materials

24、or other hazards.3.3.1.1 DiscussionControlled areas are intended to pre-vent the inadvertent access by establishing a boundary(fencing, walls, or other natural features). Exit from a con-trolled area may be controlled to prevent the spreading ofcontamination by decontamination processes (known as ad

25、econtamination path or zone) prior to personnel or equipmentmoving to the support zone.3.3.2 decontaminationthe process of removing or reduc-ing to a known level undesirable physical, chemical, orradiological constituents from equipment.3.3.2.1 DiscussionDecontamination of sample contactingequipment

26、 maximizes the representativeness of the physical,chemical, or radioactive analyses proposed for a given sample.3.3.3 non-contacting equipmentequipment used in andaround the sampling that may become contaminated, but thatdoes not contact the sample at anytime.3.3.3.1 DiscussionExamples would include

27、 drilling rigs,hand tools, drill rods, excavation equipment, or barrier mate-rials.3.3.4 organic desorbing agentssolvent rinse solutionssuch as isopropanol, acetone, hexane, or methanol.3.3.5 QC water (control rinse water)water having aknown chemistry, free (below detection levels) of organic orradi

28、ological constituents.3.3.5.1 DiscussionDeionized water of reagent grade isnormally sufficient, such as ASTM D1193, Type IV.3.3.6 rinse waterwater having a known chemistry.3.3.6.1 DiscussionDeionized or distilled water may beused when small quantities are required. When large quantitiesare required,

29、 potable water of a chemistry known to be free(below detection levels) of radioactive or chemical constituentscan be used.3.3.7 sample contacting equipmentequipment and toolsthat physically come in contact with a sample and that couldallow cross-contamination from one sample to another.3.3.7.1 Discu

30、ssionExamples include drive cylinders,bailers, sample handling, equipment, pumps, and samplingtubes.3.3.8 surveya radioactivity measurement with instrumen-tation to evaluate and assess the presence of radioactivematerials or other sources of radioactivity under a specific setof conditions.3.3.8.1 Di

31、scussionAlso known as frisking.3.3.9 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 moderate pressure and then assessing theamount of radioactivity with an instrumen

32、t of appropriateefficiency.3.3.9.1 DiscussionAradiological survey and a wipe test isgenerally required for release of equipment from a radiologicalarea to an uncontrolled area or for unrestricted use, (alsoknown as swipe test).3.3.10 remediation control surveya type of survey thatmonitors the progre

33、ss of remedial action by real-time measure-ment of areas being decontaminated to determine if efforts areeffective and to guide further decontamination activities.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book

34、 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.D5608 1624. Summary of Practice4.1 This practice provides guidance and details for thedevelopment of

35、 a site and sampling event specific decontami-nation plan for use in the decontamination of field equipmentused during sampling or other activities in areas known, orsuspected of containing low-level radioactive wastes. Fourtechniques or methods are provided, with the selection and usebased on the t

36、ype of contamination and the difficulty ofremoval.4.2 Planning should include an evaluation of the costs of thedecontamination process, including personnel exposures,waste disposal, personnel time, personal protective equipment(PPE) and other costs versus the use of less hazardousmaterials for decon

37、tamination, or avoidance of decontamina-tion by the use of dedicated equipment, or the use of disposableequipment.4.3 Approaches and procedures are provided for decontami-nation of two classifications of equipment, sample-contactingand non-contacting.4.4 This practice includes the principles of ALAR

38、A 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, prevention of thespread of contamination, minimization of additional wastes,protection of sample data

39、 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 key aspects of achieving thesegoals.5.3 This practice provides guidance in the planning of workto preve

40、nt 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 the spread outside of the work area.5.3.2 Reducing the potential exposure of workers during thework an

41、d 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, such as protectiveclothing, cleaning equipment, cleaning solutions, and protec-tive wraps and drapes.

42、5.3.4 Improving the quality of sample data and reliability.5.3.5 Selecting equipment based on total life-cycle costscounting labor, waste, containment, disposal, treatment, andadditional analytical costs, such as using dedicated or dispos-able equipment rather than decontaminating between uses.5.4 T

43、his practice may not be applicable to all low-levelradioactive waste sites, such as sites containing low-levelradioactive wastes mixed with chemical or reactive wastes.Field personnel, with assistance from trained radiologicalcontrol professionals, should have the flexibility to modify thedecontamin

44、ation procedures with due consideration for thesampling objectives, or if past experience supports alternativeprocedures for contamination protection or decontamination.5.5 This practice does not address the monitoring,protection, or decontamination of personnel working withlow-level radioactive was

45、tes.5.6 This practice does not address regulatory requirementsthat may control or restrict work, the need for permits orregulatory approvals, or the accumulation, handling, or dis-posal of generated wastes.5.7 This practice does not set the release levels for equip-ment that has been decontaminated.

46、 Release levels are to bedetermined in advance in the QA/QC planning process. Guid-ance for release limits can be found in the reference docu-ments.5.8 This practice does not address the regulatory require-ments for the handling, labeling, shipping, or storage of wastesor samples.5.9 The decontamina

47、tion process should be planned to usethe least aggressive methods and materials to be used tominimize the generation of additional wastes while resulting inan acceptable decontamination while minimizing the genera-tion of wastes. Studies have found that the use of chemicals canoften be avoided, usin

48、g pressure washes, steam cleaning, or theuse of applied heat.5.10 The practice of performing remediation control sur-veys can decrease the effort required to achieve decontamina-tion release levels.6. Hazards6.1 Equipment decontamination activities involving radio-active constituents provide numerou

49、s opportunities for person-nel contamination and radiation exposure, the uncontrolledspread of contamination, and the unnecessary 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 Work performed in a known or suspected radiologicallycontaminated site should be under the continuous control of atrained Radiological Control Technician (also known b