ASTM E1167-1987(2002) Standard Guide for Radiation Protection Program for Decommissioning Operations《停止操作的辐射防护计划》.pdf

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1、Designation: E 1167 87 (Reapproved 2002)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:C 986 Gui

12、de for Developing Training Programs in theNuclear Fuel Cycle2E 181 Test Methods for Detector Calibration and Analysisof Radionuclides3E 1134 Specification for Nuclear Facility Transient WorkerRecords3E 1168 Guide for Radiological Protection Training forNuclear Facility Workers32.2 ANSI Standards:N13

13、.6 Practice for Occupational Radiation ExposureRecords System4N323 Radiation Protection Instrumentation Test and Cali-bration42.3 NRC Document:USNRC Regulatory Guide 8.8 Information Relevant toInsuring that Occupational Radiation Exposure at NuclearPower Stations will be as Low as is Reasonably Achi

14、ev-able5USNRC Regulatory Guide 8.10 Operating Philosophy for1This guide is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applicationsand is the direct responsibility of SubcommitteeE10.03on Radiological Protection for Decontamination and Decommissioning ofNuclear Facilities a

15、nd Components.Current edition approved July 9, 1987. Pub-lished September 1987.2Annual Book of ASTM Standards, Vol 12.01.3Annual Book of ASTM Standards, Vol 12.02.4Available from American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.5Available from Nuclear Regulatory C

16、ommission, Public Document Room,1717 H St. NW, Washington, DC 20555.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.Maintaining Occupational Radiation Exposures as Low asReasonably Achievable5USNRC Regulatory Guide 8.13 Instruction C

17、oncerning Pre-natal Radiation Exposure5USNRC Regulatory Guide 8.15 Acceptable Programs forRespiratory Protection5USNRC Regulatory Guide 8.29 Instruction ConcerningRisk from Occupational Radiation Exposure52.4 DOE Document:DOE/EV/1830-T5 Guide to Reducing Radiation Exposureto as Low as Reasonably Ach

18、ievable (ALARA)62.5 INPO Document:INPO 82-004 General Employee Training72.6 ORP Document:ORP/SID 72-2 Environmental Radioactivity SurveillanceGuide82.7 ICRP Document:ICRP-43 Principles of Monitoring for the Radiation Protec-tion of the Public93. Terminology3.1 Descriptions of Terms Specific to This

19、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 iscertified by the source supplier, as traceable to the NationalRadioactivity Measurements Syste

20、m (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 andtermination of any applicable licenses.3.1.4 decontamination, nthose activities employed to re-duc

21、e 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 facilitiessuch as nuclear reactors or accelerators, where high radiationfluxes have been present,

22、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 equipment or structurescontaining radioactive material (such as internally contami-nated pipes, valves,

23、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 corrosion product depositsfrom the inside of a piping system or the removal of the toplayer of a concr

24、ete 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 decon-tamination intended to reduce the spread of contamination, toreduce the amount of protecti

25、ve clothing required, or to reducethe probability or amount of airborne contamination.3.1.8 decontamination for unrestricted release, ninvolvesreducing radioactive contamination from material, tools, orequipment to levels that satisfy “Radiological Release Criteria”(see section 3.1.18).3.1.9 personn

26、el 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 radiological hazard potentially exists (or existed) to theemployees and the general public.3.1.10.1 Discus

27、sionIncluded 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) Fuel reprocessing plant,(4) Uranium or thorium mill,(5)UF6production plant,(6) Radiochemical labo

28、ratory, 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-niques and procedures to be used to provide sufficient radiationmeasurements to describe the ra

29、diation 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 program.3.1.13.1 DiscussionThe radiation protection plan is anelement of the radiation protection

30、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, nactions applied toa decommissioning project whose intent is to limit the expo-sure of workers,

31、members of the general public, and theenvironment from radiation or radioactive materials, or both,and the written documentation supporting these actions.3.1.16 radiation work procedure, ndocumentation used tospecify protective measures and to specify personnel accessrequirements to radiation or rad

32、ioactive 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

33、 control 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 decommis

34、sioning may bereleased for unrestricted use to the general public.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 30339-3064.8Availabl

35、e from Office of Radiation Programs, 401 M St., SW, Washington, DC20460.9Available from Comitato Nazionale Per LEnergia Nucleare, Rome, Italy.E 116724. Significance and Use4.1 A program based on this guide will provide assurance toall concerned that the appropriate elements of radiation safetyhave b

36、een included to protect workers, the general public, andthe environment in proximity to the 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 radiationprot

37、ection have been addressed.RADIATION PROTECTION PROGRAM5. Radiation Safety Organization and 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 pro

38、ject organization from the individual worker to theproject manager. This description should 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 t

39、heconditions for designation of an RCA, the physical barriers andadministrative methods to 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 Radiat

40、ion Pro-tection Program should include procedures to determine theradiological conditions 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 inc

41、lude anyrestrictions for workers whose physical condition may limitentry into or ability to 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

42、 exist between radiation safety andthe operating function and the importance of high level 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 h

43、istory of the facility (including interviews with past andpresent employees), coupled with 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

44、alpha, beta,gamma, or neutron; the isotopic composition, the physical andchemical form of the radioactive material, and the magnitudeand location of the radiation sources. This information isnecessary for developing the instructions relating to radiationinstrumentation selection, radiation measureme

45、nt techniques,shielding requirements, selection of decontamination methods,contamination control 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 fordet

46、ermining the completion of decommissioning. These crite-ria should be based upon applicable 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

47、 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 projectth

48、at require a radiological survey plan. Surveys generally fallinto three categories: planning surveys, operational surveys,and release surveys. The survey plan for each should includethe description of where the measurements are made, how theyare made (direct measurement or samples), and what is to b

49、emeasured (examples include soil samples, vegetation samples,air samples, surfaces, and bore hole logging). The survey plansshould emphasize any unique features requiring special proce-dures.9.2 An environmental monitoring plan should also be pre-pared to support the decommissioning project. This planshould be an independent document covering the environmen-tal protection program from predecommissioning through un-restricted release of the facility or conclusion of the decom-missioning project. The environmental monitoring plan shouldbecome an integral part of the r