1、Designation: E1167 87 (Reapproved 2008)E1167 15Standard Guide forRadiation Protection Program for DecommissioningOperations1This standard is issued under the fixed designation E1167; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision,
2、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. Scope1.1 This guide provides instruction to the individual charged with the responsibility for developing and imple
3、menting theradiation protection program for decommissioning operations.1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both theradiological engineering and radiation safety aspects of the decommissioning project.1.3 This guide pres
4、ents a description of those elements that should be addressed in a specific radiation protection plan for eachdecommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that executethe intent of the plan.1.4 This guide applies to the development
5、 of radiation protection programs established to control exposures to radiation andradioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existingradiation protection programs as they may pertain to decommissioning workers, members
6、of the general public and theenvironment by describing the basic elements of a radiation protection program for decommissioning operations.1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of adecommissioning activity are attained wi
7、thin the radiological limits and restrictions imposed by applicable governing andregulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment.This guide should be used for developing the documentation that defines the intent and impl
8、ementation of the radiation protectionprogram for a specific decommissioning project.1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed andmaintained such that it satisfies all applicable Quality Assurance requirements developed f
9、or the decommissioning project.NOTE 1If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in thedevelopment of the Radiation Protection Program for the decommissioning site.1.7 This guide does not address the subjects of
10、emergency preparedness, safeguards, accountability, waste handling, storage, andtransportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes aprogram in and of itself from program definition through implementation.1.8 This standard does
11、 not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatorylimitations prior to use.2. Referenced Documents2.1 ASTM Standar
12、ds:2E181 Test Methods for Detector Calibration and Analysis of RadionuclidesE1134 Specification for Source-Separated Steel Cans (Withdrawn 2001)3E1168 Guide for Radiological Protection Training for Nuclear Facility Workers1 This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Techno
13、logy and Applicationsand is the direct responsibility of Subcommittee E10.03 onRadiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.Current edition approved Jan. 1, 2008Jan. 1, 2015. Published February 2008January 2015. Last previous edition approved i
14、n 20022008 as D116787(02).87(08). DOI:10.1520/E1167-87R08.10.1520/E1167-15.2 For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at serviceastm.org. For Annual Book of ASTM Standardsvolume information, refer to the standards Document Summary page on the
15、 ASTM website.3 The last approved version of this historical standard is referenced on www.astm.org.This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Becauseit may not be technicall
16、y possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current versionof the standard as published by ASTM is to be considered the official document.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C7
17、00, West Conshohocken, PA 19428-2959. United States1E1893 Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ RadiologicalAssessments to Support Unrestricted Release from Further Regulatory Controls2.2 ANSI Standards:ANSI N13.6 Practice for Occupational Rad
18、iation Exposure Records System4ANSI N323AN323AB American National Standard for Radiation Protection Instrumentation Test and Calibration:Calibration,Portable Survey Instruments4ANSI N323B Radiation Protection Instrumentation Test and Calibration, Portable Survey Instrumentation for Near BackgroundOp
19、eration2.3 NRC Documents:USNRC Regulatory Guide 8.8 Information Relevant to Insuring that Occupational Radiation Exposure at Nuclear PowerStations will be as Low as is Reasonably Achievable5USNRC Regulatory Guide 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as Re
20、asonablyAchievable5USNRC Regulatory Guide 8.13 Instruction Concerning Prenatal Radiation Exposure5USNRC Regulatory Guide 8.15 Acceptable Programs for Respiratory Protection5USNRC Regulatory Guide 8.29 Instruction Concerning Risk from Occupational Radiation Exposure52.4 DOE Document:DOE/EV/1830-T5 Gu
21、ide to Reducing Radiation Exposure to as Low as Reasonably Achievable (ALARA)6DOE/IG G-10CFR835/E1 Implementation Guide, Instrument Calibration for Portable Survey InstrumentsDOE Standard 1070-94 Guidelines for Evaluation of Nuclear Facility Training Programs2.5 INPO Document:INPO 82-004 General Emp
22、loyee Training72.6 USEPA Document:U.S. Environmental Protection Agency (EPA), 1972 Environmental Radioactivity Surveillance Guide, ORP/SID 72-282.7 ICRP Document:ICRP Publication 43 Principles of Monitoring for the Radiation Protection of the Public; Annals of the ICRP Volume 15/1,December 198493. T
23、erminology3.1 Definitions of Terms Specific to This Standard:3.1.1 audit, nformal systematic examination to verify adequate implementation.3.1.2 certified radioactivity standard source, ncalibrated radioactive source, with stated accuracy, whose calibration iscertified by the source supplier, as tra
24、ceable to the National Radioactivity Measurements System (see Test Methods E181).3.1.3 decommission, vtto remove nuclear facilities safely from service and reduce residual radioactivity to a level that permitsrelease of the property for unrestricted use and termination of any applicable licenses.3.1
25、.4 decontamination, nthose activities employed to reduce the levels of (radioactive) contamination in or on structures,equipment, materials and personnel. Five levels of decontamination are defined as follows:3.1.5 decontamination for decommissioning, nat facilities such as nuclear reactors or accel
26、erators, where high radiation fluxeshave been present, structural materials may have become radioactive through activation. Removal of such radioactive material(such as a reactor vessel or internals) constitutes “decontamination.” Removal of intact equipment or structures containingradioactive mater
27、ial (such as internally contaminated 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 use of chemicalsto dissolve radioactive corrosion product deposits from the inside of a
28、piping system or the removal of the top layer of a concretefloor into which contaminants had been embedded and had become a part of the concrete matrix.3.1.7 decontamination supporting radiological protection, nthis category includes the“ housekeeping” type of decontamina-tion intended to reduce the
29、 spread of contamination, to reduce the amount of protective clothing required, or to reduce theprobability or amount of airborne contamination.3.1.8 decontamination for unrestricted release, ninvolves reducing radioactive contamination from material, tools, orequipment to levels that satisfy “Radio
30、logical Release Criteria” (see section 3.1.18).3.1.9 personnel decontamination, nremoval of radioactive material from workers.4 Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http:/www.ansi.org.5 Available from Nuclear Regulatory Commissio
31、n, Public Document Room, 1717 H St. NW, Washington, DC 20555.6 Available from Department of Energy, National Technical Information Service, U.S. Dept. of Commerce, Springfield, VA 22161.7 Available from Institute of Nuclear Power Operations, 1100 Circle, 75 Parkway, Atlanta, GA 30339-3064.8 Availabl
32、e from Office of Radiation Programs, 401 M St., SW, Washington, DC 20460.9 Available from Comitato Nazionale Per LEnergia Nucleare, Rome, Italy.E1167 1523.1.10 nuclear facility, nfacility whose operations involve (or involved) radioactive materials in such form and quantity thata radiological hazard
33、 potentially exists (or existed) to the employees and the general public.3.1.10.1 DiscussionIncluded are facilities that are (or were) 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 re
34、processing plant,(4) Uranium or thorium mill,(5) UF6 production plant,(6) Radiochemical laboratory, and(7) Radioactive waste processing or disposal site, or both.3.1.11 review, ncritical evaluation to ensure inclusion of appropriate principles.3.1.12 survey plan, ndocument that describes the techniq
35、ues and procedures to be used to provide sufficient radiationmeasurements to describe the radiation source present within a predefined area.3.1.13 radiation protection plan, ndocument developed for a specific decommissioning project that describes the goals andintent of the radiation protection prog
36、ram.3.1.13.1 DiscussionThe radiation protection plan is an element of the radiation protection program and shall become an integral part of thedecommissioning plan.3.1.14 radiation protection procedures, n documents used to implement the radiation protection plan.3.1.15 Radiation Protection Program,
37、 nactions applied to a decommissioning project whose intent is to limit the exposure ofworkers, members of the general public, and the environment from radiation or radioactive materials, or both, and the writtendocumentation supporting these actions.3.1.16 radiation work procedure, ndocumentation u
38、sed to specify protective measures and to specify personnel accessrequirements to radiation or radioactive materials, or both.3.1.16.1 DiscussionControl may be achieved through use of a single document such as a Radiation Work Permit, which specifies the protectivemeasures for particular work tasks,
39、 or it may be achieved through application of generic procedures and instructions.3.1.17 radiological control areas (RCA), n area of a nuclear facility or area being decommissioned where access is controlledfor purposes of radiological protection.3.1.18 radiological release criteria, n levels of res
40、idual radioactivity at the completion of a decommissioning activity belowwhich the object of the decommissioning may be released for unrestricted use to the general public.4. Significance and Use4.1 Aprogram based on this guide will provide assurance to all concerned that the appropriate elements of
41、 radiation safety havebeen included to protect workers, the general public, and the environment in proximity to the decommissioning activities.4.2 Implementation of such a program will provide assurance to those agencies responsible for review or audit of thedecommissioning project that the requirem
42、ents for radiation protection have been addressed.RADIATION PROTECTION PROGRAM5. Radiation Safety Organization and Responsibilities5.1 The radiation protection plan should include a description of the radiological protection organization and the radiation safetyresponsibilities of each level of the
43、decommissioning project organization from the individual worker to the project manager. Thisdescription should show the radiation safety organization interfaces and reporting responsibilities at all levels of the project (seeNote 2).6. Radiological Control Areas (RCA)6.1 The Radiation Protection Pro
44、gram should define the conditions for designation of an RCA, the physical barriers andadministrative methods to control the spread of radioactive material, and the requirements to restrict personnel access for purposesE1167 153of radiation exposure control. Access to these areas shall require a radi
45、ation work procedure. The Radiation Protection Programshould include procedures to determine the radiological conditions within the area, that identify the anti-contamination clothing,dosimetry, and respiratory protection required for RCA entry and that define the limitations for working within the
46、RCA. Theseprocedures should include any restrictions for workers whose physical condition may limit entry into or ability to operate withinan RCA. The procedures should describe the requirements for egress and checkout from the RCA.NOTE 2USNRC Regulatory Guides 8.8 and 8.10 provide guidance on descr
47、ibing the relationships that should exist between radiation safety and theoperating function and the importance of high level management support of the radiation safety program.7. Sources and Types of Radiation7.1 The radiation sources, to be encountered during decommissioning activities, shall be d
48、efined. Reviews of the operatinghistory of the facility (including interviews with past and present employees), coupled with nuclear analysis and detailedradiological characterization surveys (see Section 9), should be used to provide this information. This description of radiationsources should inc
49、lude the type of radiation such as alpha, beta, gamma, or neutron; the isotopic composition, the physical andchemical form of the radioactive material, and the magnitude and location of the radiation sources. This information is necessaryfor developing the instructions relating to radiation instrumentation selection, radiation measurement techniques, shieldingrequirements, selection of decontamination methods, contamination control methods, and personnel dosimetry systems.8. Radiological Release Criteria8.1 The radiation protection plan should include a
