1、Designation: E 1281 89 (Reapproved 2005)Standard Guide forNuclear Facility Decommissioning Plans1This standard is issued under the fixed designation E 1281; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revision.
2、 A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) 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 decommissionin
3、g. As part of this program, 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 cont
4、ent of the decommissioning plan.1. Scope1.1 This guide applies to decommissioning plans for anynuclear facility whose operation was (is) governed by NuclearRegulatory Commission (NRC) or Agreement State license, orunder Department of Energy (DOE) orders.1.2 The guide applies to the preparation and c
5、ontent 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 U.S. NRC, nor are other nuclear facilities which
6、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 nomenclature with respect to DOE, DOD, oragreement
7、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 the user of this standard to establish appro-pri
8、ate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2E 1034 Specification for Nuclear Facility Transient WorkerRecordsE 1167 Guide for Radiation Protection Program for Decom-missioning OperationsE 1168 Guid
9、e for Radiological Protection Training forNuclear Facility Workers2.2 Code of Federal Regulations:310 CFR 19 Notices, Instructions and Reports to Workers;Inspections10 CFR 20 Standards for Protection Against Radiation10 CFR 30 Rules of General Applicability to DomesticLicensing of Byproduct Material
10、10 CFR 40 Domestic Licensing of Source Material10 CFR 50 Domestic Licensing of Production and Utiliza-tion Facilities10 CFR 51 Licensing and Regulatory Policy and Proce-dures for Environmental Protection10 CFR 70 Domestic Licensing of Special Nuclear Material10 CFR 71 Packaging of Radioactive Materi
11、al for Trans-port and Transportation of Radioactive Materials UnderCertain Conditions10 CFR 73 Physical Protection Requirements10 CFR 140 Financial Protection Requirements10 CFR 150 Exemption and Continued Regulatory Author-ity in Agreement States Under Section 27410 CFR 170 Fees and Facilities and
12、Material Licenses andOther Regulatory Services Under the Atomic Energy Actof 1954, as Amended40 CFR 190 Environmental Radiation Protection Standardsfor Nuclear Power Operations40 CFR 191 Environmental Radiation Protection Standardsfor Management and Disposal of Spent Nuclear Fuel,1This guide is unde
13、r 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 and Components.Current edition approved Aug. 1, 2005. Published August 2005. Origin
14、allyapproved in 1989. Last previous edition approved in 1996 as E 1281-89(1996)e1.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary pag
15、e onthe ASTM website.3Available from Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.High Level Waste and Transuranic Waste40 CFR 192 Health and Enviro
16、nmental Protection forUranium and Thorium Mill Tailings49 CFR 170 Hazardous Materials RegulationsDOT to1902.3 Nuclear Regulatory Commission Standards:4NRC Regulatory Guide 1.86, Termination of OperatingLicenses for Nuclear Power PlantsNUREG-1727 NMSS Decommissioning Standard ReviewPlan (NRC 2000)Reg
17、ulatory Guide 1.179 Standard Format and Content forLicense Termination Plans for Nuclear Power Reactors(NRC 1999)2.4 Department of Energy Standard:5DOE Order 5820.2 Radioactive Waste Management, Chap-ter V, Decontamination and Decommissioning of SurplusFacilities3. Terminology3.1 Definitions of Term
18、s 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 facility for unrestricted useand termination of any applicable license(s).3.1.2 decontamination, nthose activities emplo
19、yed to re-duce the levels of (radioactive) contamination in or on struc-tures, equipment, materials, and personnel.3.1.3 dismantlement, nthe alternative in which the equip-ment, structures, and portions of a facility and site containingradioactive contaminants are removed or decontaminated to alevel
20、 that permits the property to be released for unrestricteduse shortly after cessation of operations.3.1.4 entombment, nconsists of placing the facility intoprotective storage. Initial entombment activities consist ofremoving the balance of plant contaminated components,systems, and structures from t
21、he site and sealing all theremaining contaminated and activated plant components andsystems within the entombment boundary. This structure pro-vides for containment of the entire radioactive inventoryremaining on site during the entombment period. Other initialactivities would consist of processing
22、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 radioactive decay tounrestricted use levels or by dismantlement to unrestricted uselevels. If dismantlement were selected
23、 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 it, processing and removalof any remaining solid and liquid radioactive wastes, andrestoring/releasing the site for u
24、nrestricted use.3.1.5 nuclear facility, na facility whose operations in-volve (or involved) radioactive materials in such form orquantity that a radiological hazard potentially exists to theemployees or the general public. Included are facilities that are(or were) used to produce, process, or store
25、radioactivematerials. Some examples are nuclear reactors (power, test, orresearch), fuel fabrication plants, fuel reprocessing plants,uranium/thorium mills, UF-6 production and enrichmentplants, radiochemical laboratories, and radioactive waste dis-posal sites.3.1.6 safe storage, nconsists of placin
26、g and maintainingthe facility in protective storage. Initial safe storage operationswould consist of general plant decontamination activities,radiation surveys, the processing and removal of radioactivewaste materials, securing a possession-only license, and theimplementation of security, surveillan
27、ce, and maintenanceplans 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 entombment, exceptthat there would be more systems remove
28、d 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, examined, and addressed.4.2 In applying the guidance
29、 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 decommissioning plans can befound in such references as N
30、UREG-1727 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 Handbook.64.3 This decommissioning plan will be de
31、veloped 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 decommissioning plan will be met should beprepared
32、. Some of the documents or implementation plans thatmay be required to support the overall decommissioningprogram include an engineering plan; a cost, schedule, andfinancing plan; a field implementation plan; a health and safetyplan; a quality assurance plan (for example, Guide E 1167); anemergency
33、plan; an environmental report; a radiological pro-tection plan; and a physical security plan. These implementa-tion plans shall be separate from and consistent with thedecommissioning plan.5. Elements of the Decommissioning Plan5.1 The plan should identify and describe the major ele-ments of the dec
34、ommissioning program. These elements4Available from Nuclear Regulatory Commission, Public Document Room,1717 H St., N.W., Washington, DC 20555.5Available from Dept. of Energy, National Technical Information Service, U.S.Dept. of Commerce, Springfield, VA 22161.6Taboas, A. L., Moghissi, A. A., and La
35、Guardia, T. S., Eds., ASME, Three ParkAve., New York, NY, 2004.E 1281 89 (2005)2should be addressed in their approximate chronological orderand should be expanded to provide descriptive information anddetails.5.2 The following are provided as typical decommissioningelements for some types of nuclear
36、 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 general information andan indication of the scope of effort required for decommission-ing. This description should include the initi
37、al construction andlicensing history, the operating record, and a summary of alloperating events that could affect decommissioning activities(such as spills or releases of radioactive or contaminatedmaterials).6. Characterization6.1 A description of the entire nuclear facility to be decom-missioned
38、should be provided including results of a radiationsurvey prior to initiation of other decommissioning activities.Site characteristics that should be addressed include topogra-phy, soils and geology, hydrology, seismology, demography,and meteorology. Specific details such as those found in safetyana
39、lysis reports may be provided in appendices or by refer-ence. Plant characteristics that should be addressed include ageneral plant description, a plant structures description, and aplant systems description. Radiological and hazardous materialcharacteristics of the nuclear facility shall be include
40、d as well.The radionuclide inventory for the facility should be presentedwith all of the major contributors identified and quantified.Environmental radiological characteristics of the site should bediscussed.7. Program Objectives7.1 The objective(s) of the decommissioning programshould be stated con
41、cisely. The selected or proposed decom-missioning alternative (dismantlement, safe storage followedby dismantlement, or entombment to unrestricted use levels)shall be included as a minimum.7.2 A qualitative description of any interim status of thefacility should be provided when applicable, that is,
42、 when thesafe storage or entombment alternatives are selected, and whena surveillance/maintenance period is proposed for the facility.7.3 Cleanup criteria should be stated herein, such as NRCRegulatory Guide 1.86, or other specific federal and staterequirements. Termination survey requirements shoul
43、d 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/mainte
44、nance program will not be neces-sary.8. Program Management and Administration8.1 The decommissioning plan should include a descriptionof the organization and responsibilities with respect to theoverall program. The discussion should address the decommis-sioning project team, decommissioning manpower
45、; workerhealth and safety training (for example, Specification E 1034and Guide E 1168); and the use, control, and management ofsubcontractors. When safe storage or entombment alternativesare selected, then the organization and responsibilities structurefor the protected storage and delayed dismantle
46、ment phases ofthe program should be provided as well.9. Program Schedule and Cost9.1 Major Milestone ScheduleThe plan should includedecommissioning schedule information. Identification of majordecommissioning phase start and finish dates as well as majordecommissioning task milestones should be addr
47、essed. Afigure or chart as well as a written explanation should beprovided. A logic diagram may be included to depict thesequence of activities.9.2 Cost EstimateA summary of the detailed, site-specificdecommissioning cost estimate should be provided. A copy ofthe detailed cost estimate may be refere
48、nced or provided as anappendix.10. Decommissioning Activities10.1 The plan should address the major activities of thedecommissioning program. A typical list of decommissioningactivities is presented in Appendix X1.10.2 The plan should include a concise description of howthese major activities will b
49、e carried out in a manner thatprotects the worker and public health and safety. Persons ororganizations responsible for each activity should be desig-nated.11. Facility Modification11.1 The plan should identify major additions to the facilityin support of decommissioning operations. Changes to thefacility resulting from decommissioning activities (such asremoval of structures and systems) need not be addressedherein.11.2 Examples of major facility modifications to be identi-fied include additions of a waste processing facility, a wastestaging/storage facility, a water cleanup
