ASTM E1167-1987(2008) Standard Guide for Radiation Protection Program for Decommissioning Operations《停止操作的辐射防护大纲的标准指南》.pdf

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1、Designation: E 1167 87 (Reapproved 2008)Standard Guide forRadiation Protection Program for DecommissioningOperations1This standard is issued under the fixed designation E 1167; 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 (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 This guide provides instruction to the individual chargedwith the responsibility for developing and implementin

3、g theradiation protection program for decommissioning operations.1.2 This guide provides a basis for the user to developradiation protection program documentation that will supportboth the radiological engineering and radiation safety aspectsof the decommissioning project.1.3 This guide presents a d

4、escription of those elements thatshould be addressed in a specific radiation protection plan foreach decommissioning project. The plan would, in turn, formthe basis for development of the implementation proceduresthat execute the intent of the plan.1.4 This guide applies to the development of radiat

5、ionprotection programs established to control exposures to radia-tion and radioactive materials associated with the decommis-sioning of nuclear facilities. The intent of this guide is tosupplement existing radiation protection programs as they maypertain to decommissioning workers, members of the ge

6、neralpublic and the environment by describing the basic elements ofa radiation protection program for decommissioning opera-tions.1.5 This guide defines the elements of a radiation protectionprogram that will ensure that the goals and objectives of adecommissioning activity are attained within the r

7、adiologicallimits and restrictions imposed by applicable governing andregulating agencies. The implementation of such a programwill provide radiological protection to personnel and theenvironment. This guide should be used for developing thedocumentation that defines the intent and implementation of

8、the radiation protection program for a specific decommission-ing project.1.6 The Radiation Protection Program should address thefollowing elements (see Note 1). This program shall bedeveloped and maintained such that it satisfies all applicableQuality Assurance requirements developed for the decommi

9、s-sioning project.NOTE 1If the site to be decommissioned is adjacent to an operatingsite, the radiological impact of the operating site must be considered in thedevelopment of the Radiation Protection Program for the decommission-ing site.1.7 This guide does not address the subjects of emergencyprep

10、aredness, safeguards, accountability, waste handling, stor-age, and transportation. Each of these issues has a directinterface with the radiation protection program. However, eachconstitutes a program in and of itself from program definitionthrough implementation.1.8 This standard does not purport t

11、o 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 and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2E 181 Te

12、st Methods for Detector Calibration and Analysisof RadionuclidesE 1134 Specification for Source-Separated Steel Cans (Dis-continued 2001)3E 1168 Guide for Radiological Protection Training forNuclear Facility WorkersE 1893 Guide for Selection and Use of Portable Radiologi-cal Survey Instruments for P

13、erforming In Situ RadiologicalAssessments in Support of Decommissioning2.2 ANSI Standards:ANSI N13.6 Practice for Occupational Radiation ExposureRecords System4ANSI N323A Radiation Protection Instrumentation Testand Calibration: Portable Survey Instruments4ANSI N323B Radiation Protection Instrumenta

14、tion Test andCalibration, Portable Survey Instrumentation for NearBackground Operation2.3 NRC Documents:1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applications and is the direct responsibility of SubcommitteeE10.03 on Radiological Protection for Decontaminat

15、ion and Decommissioning ofNuclear Facilities and Components.Current edition approved Jan. 1, 2008. Published February 2008. Last previousedition approved in 2002 as D 116787(02).2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org.

16、For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Withdrawn.4Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.1Copyright ASTM International, 100 Barr Harbo

17、r Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.USNRC Regulatory Guide 8.8 Information Relevant toInsuring that Occupational Radiation Exposure at NuclearPower Stations will be as Low as is Reasonably Achiev-able5USNRC Regulatory Guide 8.10 Operating Philosophy forMaintaining O

18、ccupational Radiation Exposures as Low asReasonably Achievable5USNRC Regulatory Guide 8.13 Instruction Concerning Pre-natal Radiation Exposure5USNRC Regulatory Guide 8.15 Acceptable Programs forRespiratory Protection5USNRC Regulatory Guide 8.29 Instruction ConcerningRisk from Occupational Radiation

19、Exposure52.4 DOE Document:DOE/EV/1830-T5 Guide to Reducing Radiation Exposureto as Low as Reasonably Achievable (ALARA)6DOE/IG G-10CFR835/E1 Implementation Guide, Instru-ment Calibration for Portable Survey InstrumentsDOE Standard 1070-94 Guidelines for Evaluation ofNuclear Facility Training Program

20、s2.5 INPO Document:INPO 82-004 General Employee Training72.6 USEPA Document:U.S. Environmental Protection Agency (EPA), 1972 Envi-ronmental Radioactivity Surveillance Guide, ORP/SID72-282.7 ICRP Document:ICRP Publication 43 Principles of Monitoring for the Ra-diation Protection of the Public; Annals

21、 of the ICRPVolume 15/1, December 198493. Terminology3.1 Descriptions of Terms Specific to This Standard:3.1.1 audit, nformal systematic examination to verifyadequate implementation.3.1.2 certified radioactivity standard source, ncalibratedradioactive source, with stated accuracy, whose calibration

22、iscertified by the source supplier, as traceable to the NationalRadioactivity Measurements System (see Test Methods E 181).3.1.3 decommission, vtto remove nuclear facilities safelyfrom service and reduce residual radioactivity to a level thatpermits release of the property for unrestricted use andte

23、rmination of any applicable licenses.3.1.4 decontamination, nthose activities employed to re-duce the levels of (radioactive) contamination in or on struc-tures, equipment, materials and personnel. Five levels ofdecontamination are defined as follows:3.1.5 decontamination for decommissioning, nat fa

24、cilitiessuch as nuclear reactors or accelerators, where high radiationfluxes have been present, structural materials may have be-come radioactive through activation. Removal of such radio-active material (such as a reactor vessel or internals) constitutes“decontamination.” Removal of intact equipmen

25、t or structurescontaining radioactive material (such as internally contami-nated pipes, valves, pumps, tanks, etc.) also constitutes“decontamination.”3.1.6 decontamination to reduce radiation levels,nexamples of this type of decontamination would be the useof chemicals to dissolve radioactive corros

26、ion product depositsfrom the inside of a piping system or the removal of the toplayer of a concrete floor into which contaminants had beenembedded and had become a part of the concrete matrix.3.1.7 decontamination supporting radiological protection,nthis category includes the“ housekeeping” type of

27、decon-tamination intended to reduce the spread of contamination, toreduce the amount of protective clothing required, or to reducethe probability or amount of airborne contamination.3.1.8 decontamination for unrestricted release, ninvolvesreducing radioactive contamination from material, tools, oreq

28、uipment to levels that satisfy “Radiological Release Criteria”(see section 3.1.18).3.1.9 personnel decontamination, nremoval of radioac-tive material from workers.3.1.10 nuclear facility, nfacility whose operations involve(or involved) radioactive materials in such form and quantitythat a radiologic

29、al hazard potentially exists (or existed) to theemployees and the general public.3.1.10.1 DiscussionIncluded are facilities that are (orwere) used to produce, process, or store radioactive materials.Some examples are as follows:(1) Nuclear reactor (power or research),(2) Fuel fabrication plant,(3) F

30、uel reprocessing plant,(4) Uranium or thorium mill,(5)UF6production plant,(6) Radiochemical laboratory, and(7) Radioactive waste processing or disposal site, or both.3.1.11 review, ncritical evaluation to ensure inclusion ofappropriate principles.3.1.12 survey plan, ndocument that describes the tech

31、-niques and procedures to be used to provide sufficient radiationmeasurements to describe the radiation source present within apredefined area.3.1.13 radiation protection plan, ndocument developedfor a specific decommissioning project that describes the goalsand intent of the radiation protection pr

32、ogram.3.1.13.1 DiscussionThe radiation protection plan is anelement of the radiation protection program and shall becomean integral part of the decommissioning plan.3.1.14 radiation protection procedures, ndocuments usedto implement the radiation protection plan.3.1.15 Radiation Protection Program,

33、nactions applied toa decommissioning project whose intent is to limit the expo-sure of workers, members of the general public, and theenvironment from radiation or radioactive materials, or both,and the written documentation supporting these actions.5Available from Nuclear Regulatory Commission, Pub

34、lic Document Room,1717 H St. NW, Washington, DC 20555.6Available from Department of Energy, National Technical Information Service,U.S. Dept. of Commerce, Springfield, VA 22161.7Available from Institute of Nuclear Power Operations, 1100 Circle, 75Parkway, Atlanta, GA 30339-3064.8Available from Offic

35、e of Radiation Programs, 401 M St., SW, Washington, DC20460.9Available from Comitato Nazionale Per LEnergia Nucleare, Rome, Italy.E 1167 87 (2008)23.1.16 radiation work procedure, ndocumentation used tospecify protective measures and to specify personnel accessrequirements to radiation or radioactiv

36、e materials, or both.3.1.16.1 DiscussionControl may be achieved through useof a single document such as a Radiation Work Permit, whichspecifies the protective measures for particular work tasks, or itmay be achieved through application of generic procedures andinstructions.3.1.17 radiological contro

37、l areas (RCA), narea of anuclear facility or area being decommissioned where access iscontrolled for purposes of radiological protection.3.1.18 radiological release criteria, nlevels of residualradioactivity at the completion of a decommissioning activitybelow which the object of the decommissioning

38、 may bereleased for unrestricted use to the general public.4. Significance and Use4.1 A program based on this guide will provide assurance toall concerned that the appropriate elements of radiation safetyhave been included to protect workers, the general public, andthe environment in proximity to th

39、e decommissioning activi-ties.4.2 Implementation of such a program will provide assur-ance to those agencies responsible for review or audit of thedecommissioning project that the requirements for radiationprotection have been addressed.RADIATION PROTECTION PROGRAM5. Radiation Safety Organization an

40、d Responsibilities5.1 The radiation protection plan should include a descrip-tion of the radiological protection organization and the radia-tion safety responsibilities of each level of the decommission-ing project organization from the individual worker to theproject manager. This description shoul

41、d show the radiationsafety organization interfaces and reporting responsibilities atall levels of the project (see Note 2).6. Radiological Control Areas (RCA)6.1 The Radiation Protection Program should define theconditions for designation of an RCA, the physical barriers andadministrative methods to

42、 control the spread of radioactivematerial, and the requirements to restrict personnel access forpurposes of radiation exposure control. Access to these areasshall require a radiation work procedure. The Radiation Pro-tection Program should include procedures to determine theradiological conditions

43、within the area, that identify the anti-contamination clothing, dosimetry, and respiratory protectionrequired for RCA entry and that define the limitations forworking within the RCA. These procedures should include anyrestrictions for workers whose physical condition may limitentry into or ability t

44、o operate within an RCA. The proceduresshould describe the requirements for egress and checkout fromthe RCA.NOTE 2USNRC Regulatory Guides 8.8 and 8.10 provide guidance ondescribing the relationships that should exist between radiation safety andthe operating function and the importance of high level

45、 managementsupport of the radiation safety program.7. Sources and Types of Radiation7.1 The radiation sources, to be encountered during decom-missioning activities, shall be defined. Reviews of the operat-ing history of the facility (including interviews with past andpresent employees), coupled with

46、 nuclear analysis and detailedradiological characterization surveys (see Section 9), should beused to provide this information. This description of radiationsources should include the type of radiation such as alpha, beta,gamma, or neutron; the isotopic composition, the physical andchemical form of

47、the radioactive material, and the magnitudeand location of the radiation sources. This information isnecessary for developing the instructions relating to radiationinstrumentation selection, radiation measurement techniques,shielding requirements, selection of decontamination methods,contamination c

48、ontrol methods, and personnel dosimetry sys-tems.8. Radiological Release Criteria8.1 The radiation protection plan should include a discus-sion of the radiological criteria that will be used as the basis fordetermining the completion of decommissioning. These crite-ria should be based upon applicabl

49、e limits for unrestrictedrelease. Decontamination for unrestricted release, if needed,should consider the specific radionuclides present, the materialcontaminated such as soil or facility, and the potential end usesof the item or area being decontaminated. The development ofthe criteria should consider the type of measurement to beperformed, such as surface versus volume, and the medium tobe measured, such as air or water.9. Radiological Survey Plans9.1 There are many phases of a decommissioning projectthat require a radiological survey plan. Surveys generally