ASTM E1281-2010 Standard Guide for Nuclear Facility Decommissioning Plans《核设备退役计划标准指南》.pdf

1、Designation: E1281 10Standard 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) or Agreement State license, orunder Department of Energy (DOE) orders.1.2 The guide applies to the preparation and content of thedecommis

5、sioning 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 may come underthe con

6、trol 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 state nuclear facilit

7、ies. 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-priate safety and health

8、 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 Program for Decom-missioning OperationsE1168 Guide for Radiological Prote

9、ction 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 FacilitiesE1893 Guide for Selection and Use of Portable Radiologi-cal Survey

10、Instruments for Performing In Situ RadiologicalAssessments to Support Unrestricted Release from FurtherRegulatory ControlsE2216 Guide for Evaluating Disposal Options for Concretefrom Nuclear Facility DecommissioningE2420 Guide for Post-Deactivation Surveillance and Main-tenance of Radiologically Con

11、taminated FacilitiesE2421 Guide for Preparing Waste Management Plans forDecommissioning Nuclear Facilities2.2 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

12、 DomesticLicensing of Byproduct Material10 CFR 40 Domestic Licensing of Source Material10 CFR 50 Domestic Licensing of Production and Utiliza-tion Facilities10 CFR 51 Environmental Protection Regulations forDomestic Licensing and Related Regulatory Functions10 CFR 61 Licensing Requirements for Land

13、Disposal ofRadioactive Waste1This 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 and Components.Current edition appro

14、ved Oct. 1, 2010. Published November 2010. Originallyapproved in 1989. Last previous edition approved in 2005 as E1281-89(2005). DOI:10.1520/E1281-10.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStand

15、ards volume information, refer to the standards Document Summary page 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 State

16、s.10 CFR 70 Domestic Licensing of Special Nuclear Material10 CFR 71 Packaging and Transportation of RadioactiveMaterials10 CFR 73 Physical Protection of Plants and Materials10 CFR 140 Financial Protection Requirements and Indem-nity Agreements10 CFR 150 Exemption and Continued Regulatory Author-ity

17、in Agreement States Under Section 27410 CFR 170 Fees for Facilities, Materials, Import andExport Licenses and Other Regulatory Services Under theAtomic Energy Act of 1954, as Amended10 CFR 830 Nuclear Safety Rules10 CFR 835 Occupational Radiation Safety29 CFR 1910.120 Hazardous Waste Operations and

18、Emer-gency Response40 CFR 190 Environmental Radiation Protection Standardsfor Nuclear Power Operations40 CFR 191 Environmental Radiation Protection Standardsfor Management and Disposal of Spent Nuclear Fuel,High Level Waste and Transuranic Waste40 CFR 192 Health and Environmental Protection forUrani

19、um and Thorium Mill Tailings40 CFR 260 Land Disposal Restrictions49 CFR 190 and above Hazardous Materials TransportationRegulations2.3 Nuclear Regulatory Commission Standards:4NRC Regulatory Guide 1.86, Termination of OperatingLicenses for Nuclear ReactorsNUREG-1757 Consolidated Decommissioning Guid

20、ance;Volume 1, Decommissioning Process for Material Li-censes; Volume 2, Characterization, Survey and Determi-nation of Radiologial Criteria; Volume 3, Financial Assur-ance, Recordkeeping, and TimelinessNUREG-1575 Multi-Agency Radiation Survey and SiteInvestigation Manual (MARSSIM), Rev 1, August 20

21、00NUREG-2082 Monitoring for Compliance with 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 Support

22、ing Guides and ManualsDOE Order 430.1B Real 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

23、 thatpermit release of the property or facility 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 on struc-tures, equipment, materials, and personnel.3.1.3 dismantlement, nthe

24、alternative in which the equip-ment, structures, and portions of a facility and site containingradioactive contaminants are removed or decontaminated to alevel that permits the property to be released for unrestricteduse shortly after cessation of operations.3.1.4 entombment, nconsists of placing th

25、e facility intoprotective storage. Initial 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 pr

26、o-vides for containment of the entire radioactive 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.D

27、ecommissioning is completed by either radioactive 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 e

28、ntomb-ment structure and materials within 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 in-volve (or involved) radioactive materials in such form orquantity tha

29、t a radiological hazard potentially exists to theemployees or the general public. Included are facilities that are(or were) used to produce, process, or store radioactivematerials. Some examples are nuclear reactors (power, test, orresearch), fuel fabrication plants, fuel reprocessing plants,uranium

30、/thorium mills, UF-6 production and enrichmentplants, radiochemical laboratories, and radioactive waste dis-posal 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

31、,radiation surveys, the processing and removal of radioactivewaste materials, securing a possession-only license, and theimplementation of security, surveillance, and maintenanceplans for the delay period. Decommissioning is completed bydismantling following the protective storage period. The addi-t

32、ional activities initiated after 30 or more years would beessentially the same as those described for entombment, 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 fac

33、ility owner with a greater assurance thatall basic planning elements and requirements have beenidentified, examined, 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 decomm

34、issioning plan.Additional guidance on the planning of decommissioning4Available 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.E1281

35、102projects, and the preparation of decommissioning 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 anA

36、SME publication titled The Decommissioning Handbook.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 implementatio

37、n plan describing how theobjectives of the decommissioning 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 fiel

38、d implementationplan; a health and safety plan (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

39、(10CFR 73). These implementation plans shall 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 chrono

40、logical orderand should be expanded to provide 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 nucle

41、arfacility should be included to provide general 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 decommission

42、ing activities(such as spills or releases of 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 characte

43、ristics that should be addressed include topogra-phy, soils and geology, hydrology, seismology, demography,and meteorology. Specific details such as those found in safetyanalysis reports may be provided in appendices or by refer-ence. Plant characteristics that should be addressed include ageneral p

44、lant description, a plant structures description, and aplant systems description. Radiological and hazardous materialcharacteristics of the nuclear facility shall be included as well.The radionuclide inventory for the facility should be presentedwith all of the major contributors identified and quan

45、tified.Environmental radiological characteristics of the site should bediscussed. Guidance for developing the Characterization Planmay be found in the MARSSIM manual (NUREG-1575) andGuide E1893.7. Program Objectives7.1 The objective(s) of the decommissioning programshould be stated concisely. The se

46、lected 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 description of any interim status of thefacility should be provided when applicable, tha

47、t 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 herein, such as NRCRegulatory Guide 1.86, or other specific federal and staterequirements.

48、 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 th

49、is 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 responsibilities with respect to theoverall program. The discussion should address the decommis-sioning project team, decommissioning manpower; workerhealth and safety training (Specification E1034 and GuideE1168); and the use, control, and management of subcontrac-tors. When safe storage or entombment alternatives are se-lected, then the organization and responsibilities structure for