1、Designation: E1281 15Standard Guide forNuclear Facility Decommissioning Plans1This standard is issued under the fixed designation E1281; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revision. A number in parenth
2、eses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.INTRODUCTIONAs a nuclear facility approaches the end of its operational life, the operator should initiate finalpreparations for decommissioning. As part of this pr
3、ogram, a decommissioning plan should bedeveloped to comply with applicable federal and state requirements and regulations, as well as toprovide generic and detailed information relevant to decommissioning project planning. This standardis a guideline for the preparation and content of the decommissi
4、oning plan.1. Scope1.1 This guide applies to decommissioning plans for anynuclear facility whose operation was (is) governed by NuclearRegulatory Commission (NRC), Agreement State license,under Department of Energy (DOE) orders, or whose operationwas overseen by another federal, state, or local agen
5、cy.1.2 The guide applies to the preparation and content of thedecommissioning plan document itself.1.3 The detailed description and development of implemen-tation plans identified in Section 4 is outside the scope of thisguide.NOTE 1Nuclear facilities operated by the U.S. DOE are not licensedby the
6、U.S. NRC, nor are other nuclear facilities which may come underthe control of the U.S. Department of Defense or individual agreementstates. The references in this guide to licensee, U.S. NRC Regulatoryguides, and Title 10 of the U.S. Code of Federal Regulations are to implyappropriate alternative no
7、menclature with respect to DOE, DOD, oragreement state nuclear facilities. This distinction should not alter thecontent of decommissioning plans for nuclear facilities.1.4 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of
8、 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:2E1034 Specification for Nuclear Facility Transient WorkerRecordsE1167 Guide for Radiation Protection Pro
9、gram for Decom-missioning OperationsE1168 Guide for Radiological Protection Training forNuclear Facility WorkersE1760 Guide for Unrestricted Disposition of Bulk MaterialsContaining Residual Amounts of RadioactivityE1819 Guide for Environmental Monitoring Plans for De-commissioning of Nuclear Facilit
10、iesE1892 Guide for Preparing Characterization Plans for De-commissioning Nuclear FacilitiesE1893 Guide for Selection and Use of Portable RadiologicalSurvey Instruments for Performing In Situ RadiologicalAssessments to Support Unrestricted Release from Fur-ther Regulatory ControlsE2216 Guide for Eval
11、uating Disposal Options for Concretefrom Nuclear Facility DecommissioningE2420 Guide for Post-Deactivation Surveillance and Main-tenance of Radiologically Contaminated FacilitiesE2421 Guide for Preparing Waste Management Plans forDecommissioning Nuclear Facilities2.2 Code of Federal Regulations:310
12、CFR 19 Notices, Instructions and Reports to Workers;Inspections1This guide is under the jurisdiction of Committee E10 on Nuclear Technologyand Applications and is the direct responsibility of Subcommittee E10.03 onRadiological Protection for Decontamination and Decommissioning of NuclearFacilities a
13、nd Components.Current edition approved June 1, 2015. Published July 2015. Originally approvedin 1989. Last previous edition approved in 2010 as E1281-10. DOI: 10.1520/E1281-15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. Fo
14、r 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.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA
15、 19428-2959. United States110 CFR 20 Standards for Protection Against Radiation10 CFR 30 Rules of General Applicability to DomesticLicensing of Byproduct Material10 CFR 40 Domestic Licensing of Source Material10 CFR 50 Domestic Licensing of Production and Utiliza-tion Facilities10 CFR 51 Environment
16、al Protection Regulations for Do-mestic Licensing and Related Regulatory Functions10 CFR 61 Licensing Requirements for Land Disposal ofRadioactive Waste10 CFR 70 Domestic Licensing of Special Nuclear Material10 CFR 71 Packaging and Transportation of RadioactiveMaterials10 CFR 73 Physical Protection
17、of Plants and Materials10 CFR 140 Financial Protection Requirements and Indem-nity Agreements10 CFR 150 Exemption and Continued Regulatory Author-ity in Agreement States Under Section 27410 CFR 170 Fees for Facilities, Materials, Import andExport Licenses and Other Regulatory Services Under theAtomi
18、c Energy Act of 1954, as Amended10 CFR 830 Nuclear Safety Rules10 CFR 835 Occupational Radiation Safety29 CFR 1910.120 Hazardous Waste Operations and Emer-gency Response40 CFR 190 Environmental Radiation Protection Standardsfor Nuclear Power Operations40 CFR 191 Environmental Radiation Protection St
19、andardsfor Management and Disposal of Spent Nuclear Fuel,High Level Waste and Transuranic Waste40 CFR 192 Health and Environmental Protection forUranium and Thorium Mill Tailings40 CFR 260 Land Disposal Restrictions49 CFR 190 and above Hazardous Materials TransportationRegulations2.3 Nuclear Regulat
20、ory Commission Standards:4NRC Regulatory Guide 1.86, Termination of Operating Li-censes for Nuclear ReactorsNUREG-1757 Consolidated Decommissioning Guidance;Volume 1, Decommissioning Process for Material Li-censes; Volume 2, Characterization, Survey and Determi-nation of Radiologial Criteria; Volume
21、 3, FinancialAssurance, Recordkeeping, and TimelinessNUREG-1575 Multi-Agency Radiation Survey and Site In-vestigation Manual (MARSSIM), Rev 1, August 2000NUREG-1575 Supplement 1, Multi-Agency Radiation Sur-vey and Assessment of Materials and Equipment (MAR-SAME)NUREG-2082 Monitoring for Compliance w
22、ith Decommis-sioning Termination Survey CriteriaRegulatory Guide 1.179 Standard Format and Content forLicense Termination Plans for Nuclear Power Reactors(NRC 1999)2.4 Department of Energy Standard:5DOE Order O 435.1-1 “Radioactive Waste Management”and Supporting Guides and ManualsDOE Order 430.1B R
23、eal Property Assess ManagementDOE Guide G430.1-3 Deactivation Implementation Guide3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 decommission, vtto remove a nuclear facility safelyfrom service and reduce residual radioactivity to levels thatpermit release of the property or f
24、acility for unrestricted useand termination of any applicable license(s).3.1.2 decontamination, nthose activities employed to re-duce the levels of (radioactive) contamination in or onstructures, equipment, materials, and personnel.3.1.3 dismantlement, nthe alternative in which theequipment, structu
25、res, and portions of a facility and sitecontaining radioactive contaminants are removed or decon-taminated to a level that permits the property to be released forunrestricted use shortly after cessation of operations.3.1.4 entombment, nconsists of placing the facility intoprotective storage. Initial
26、 entombment activities consist ofremoving the balance of plant contaminated components,systems, and structures from the site and sealing all theremaining contaminated and activated plant components andsystems within the entombment boundary. This structure pro-vides for containment of the entire radi
27、oactive inventoryremaining on site during the entombment period. Other initialactivities would consist of processing and removing radioac-tive waste, securing a possession-only license, and implement-ing security and surveillance plans for the delay period.Decommissioning is completed by either radi
28、oactive decay tounrestricted use levels or by dismantlement to unrestricted uselevels. If dismantlement were selected following entombment,additional activities would be initiated after 30 or more yearsand would consist of radiation surveys, removal of the entomb-ment structure and materials within
29、it, processing and removalof any remaining solid and liquid radioactive wastes, andrestoring/releasing the site for unrestricted use.3.1.5 nuclear facility, na facility whose operations involve(or involved) radioactive materials in such form or quantitythat a radiological hazard potentially exists t
30、o the employees orthe general public. Included are facilities that are (or were)used to produce, process, or store radioactive materials. Someexamples are nuclear reactors (power, test, or research), fuelfabrication plants, fuel reprocessing plants, uranium/thoriummills, UF-6 production and enrichme
31、nt plants, radiochemicallaboratories, and radioactive waste disposal sites.3.1.6 safe storage, nconsists of placing and maintainingthe facility in protective storage. Initial safe storage operationswould consist of general plant decontamination activities,radiation surveys, the processing and remova
32、l of radioactivewaste materials, securing a possession-only license, and theimplementation of security, surveillance, and maintenance4Available from Nuclear Regulatory Commission, Public Document Room,1717 H St., N.W., Washington, DC 20555.5Available from Dept. of Energy, National Technical Informat
33、ion Service, U.S.Dept. of Commerce, Springfield, VA 22161.E1281 152plans for the delay period. Decommissioning is completed bydismantling following the protective storage period. The addi-tional activities initiated after 30 or more years would beessentially the same as those described for entombmen
34、t, exceptthat there would be more systems removed after safe storagethan after entombment.4. Significance and Use4.1 The standardization of decommissioning plans willprovide the nuclear facility owner with a greater assurance thatall basic planning elements and requirements have beenidentified, exam
35、ined, and addressed.4.2 In applying the guidance contained in this standard, thenuclear facility owner will address the significant subject areasnecessary to describe a comprehensive decommissioning plan.Additional guidance on the planning of decommissioningprojects, and the preparation of decommiss
36、ioning plans can befound in such references as NUREG-1757 on decommission-ing standard review plans, and Regulatory Guide 1.179 on theformat and content of license termination plans. Recent newguidance on all aspects of decommissioning is contained in anASME publication titled The Decommissioning Ha
37、ndbook.64.3 This decommissioning plan will be developed to serveas the executive document that describes the objectives of thedecommissioning program and identifies and defines the ele-ments necessary to accomplish the program.4.4 A detailed implementation plan describing how theobjectives of the de
38、commissioning plan will be met should beprepared. Some of the documents or implementation plans thatmay be required to support the overall decommissioningprogram include an engineering plan; a cost, schedule, andfinancing plan (10 CFR 140 and 170); a field implementationplan; a health and safety pla
39、n (29 CFR 1910.120, GuideE1167); a quality assurance plan (10 CFR 50.59 and 10 CFR830.120); an emergency plan; an environmental monitoringplan (Guide E1819); a radiological protection plan (10 CFR 20,10 CFR 835, Guide E1167); and a physical security plan (10CFR 73). These implementation plans shall
40、be separate fromand consistent with the decommissioning plan.5. Elements of the Decommissioning Plan5.1 The plan should identify and describe the major ele-ments of the decommissioning program. These elementsshould be addressed in their approximate chronological orderand should be expanded to provid
41、e descriptive information anddetails.5.2 The following are provided as typical decommissioningelements for some types of nuclear facilities:5.2.1 Facility description,5.2.2 Operating history, and5.2.3 A description of the history of operation at the nuclearfacility should be included to provide gene
42、ral information andan indication of the scope of effort required for decommission-ing. This description should include the initial construction andlicensing history, the operating record, and a summary of alloperating events that could affect decommissioning activities(such as spills or releases of
43、radioactive or contaminatedmaterials).6. Characterization6.1 A description of the entire nuclear facility to be decom-missioned should be provided including results of a radiationsurvey prior to initiation of other decommissioning activities.Site characteristics that should be addressed includetopog
44、raphy, soils and geology, hydrology, seismology,demography, and meteorology. Specific details such as thosefound in safety analysis reports may be provided in appendicesor by reference. Plant characteristics that should be addressedinclude a general plant description, a plant structuresdescription,
45、and a plant systems description. Radiological andhazardous material characteristics of the nuclear facility shallbe included as well. The radionuclide inventory for the facilityshould be presented with all of the major contributors identifiedand quantified. Environmental radiological characteristics
46、 ofthe site should be discussed. Guidance for developing theCharacterization Plan may be found in the MARSSIM manual(NUREG-1575), the MARSAME manual, and Guide E1892.Guidance for selection of appropriate instrumentation forobtaining the radiological data is provided in Guide E1893.7. Program Objecti
47、ves7.1 The objective(s) of the decommissioning programshould be stated concisely. The selected or proposed decom-missioning alternative (dismantlement, safe storage followedby dismantlement, or entombment to unrestricted use levels)shall be included as a minimum (DOE Order 430.1B).7.2 A qualitative
48、description of any interim status of thefacility should be provided when applicable, that is, when thesafe storage or entombment alternatives are selected, and whena surveillance/maintenance period is proposed for the facility(DOE Guide G430.1-1, Guide E2420).7.3 Cleanup criteria should be stated he
49、rein, such as NRCRegulatory Guide 1.86, or other specific federal and staterequirements. Termination survey requirements should be asdetailed in 13.5.7.4 The interim and ultimate desired status of all facilitylicenses should be discussed. For facilities where the unre-stricted release criteria will be achieved without a planned andsignificant delay period, this should be stated. For this case, anongoing surveillance/maintenance program will not be neces-sary.8. Program Management and Administration8.1 The decommissioning plan should include a descriptionof the organization and
