1、ANSI/ANS-40.37-2009mobile low-level radioactivewaste processing systemsANSI/ANS-40.37-2009ANSI/ANS-40.37-2009American National StandardMobile Low-Level RadioactiveWaste Processing SystemsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-40
2、.37Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved November 20, 2009by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe principles of openn
3、ess and due process have been followed in the approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under procedures of the Standards Committee ofthe American Nuclear Society; these procedures are accredited by t
4、he Amer-ican National Standards Institute, Inc., as meeting the criteria for AmericanNational Standards. The consensus committee that approved the standardwas balanced to ensure that competent, concerned, and varied interests havehad an opportunity to participate.An American National Standard is int
5、ended to aid industry, consumers, gov-ernmental agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notpreclude anyone from manufacturing, marketing, purchasing, or using prod-ucts, processes, or procedures not c
6、onforming to the standard.By publication of this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The content of this standard reflects acceptable practice at the time ofits approval and publication. Changes
7、, if any, occurring through developmentsin the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures. Users of this standardare cautioned to determine the vali
8、dity of copies in their possession and toestablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individual or by any ad hoc group of individuals.Requests for interpretation should be sent to the Standards Dep
9、artment atSociety Headquarters. Action will be taken to provide appropriate response inaccordance with established procedures that ensure consensus on theinterpretation.Comments on this standard are encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Ke
10、nsington AvenueLa Grange Park, Illinois 60526 USACopyright 2009 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-40.37-2009 with permission of the publisher,the American Nuclear Socie
11、ty.” Reproduction prohibited under copyright conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis Foreword is not a part of American National Standard “Mobile Low-Level Radio-active Waste Processing Systems,” ANSI0ANS-40.3
12、7-2009.!A key aspect for the further development of nuclear technology is the effectivemanagement of low-level radioactive wastesLLWs! generated during the facilityoperation. Fundamental to the effective management of radioactive wastes is thedesign, construction, and operation of radioactive waste
13、processing systems. Thisstandard was originally issued in 1993 in response to interest in the use ofmobile radioactive waste processing systems that could be transported fromfacility to facility, retained in service at a facility for an extended period of timeor quickly replaced by alternate treatme
14、nt technology. In 2001, the U.S. NuclearRegulatory Commission NRC! cited this standard for mobile treatment systemsin Rev. 2 of Regulatory Guide 1.143 RG 1.143!. The NRC also granted designrelief in Rev. 2 of RG 1.143 when it allowed Power Piping ANSI0ASME B31.1!versus Process Piping ANSI0ASME B31.3
15、! to be used for radioactive wastesystems.Unfortunately, this standard failed to be reaffirmed in 2003. This standard isbeing reissued to incorporate the design relief granted by the NRC in 2001 andto service continued operation at nuclear facilities and new nuclear facilityconstruction.It is the pu
16、rpose of this standard to provide requirements for the design and op-eration of the mobile low-level radioactive waste processingMRWP! system. It isthe intent of this standard to identify a basis for establishing uniform practicesand minimum requirements for the design, fabrication, and operation of
17、 MRWPsystems as applied to nuclear facility operations e.g., power plants, institutions,and laboratories that generate wastes approved for disposal at 10 CFR 61 LLWdisposal sites!. This standards scope does not address systems used to processwaste from nuclear facilities that potentially contain fis
18、sile material in sufficientquantities to require controls to avoid criticality; i.e., ANSI0ANS-40.37-2009 re-quirements do not address wastes containing quantities of fissile or long-lived ra-dionuclides that are classified as high-level or transuranic radioactive waste atypicalof NRC-licensed comme
19、rcial facilities and beyond the scope of 10 CFR 61. Systemsapplicable to non-low-level waste that use this standard might have to meet ad-ditional requirements beyond the scope of this standard. This standard addressesthe technical practices and requirements necessary for radioactive waste process-i
20、ng operations while maintaining consideration for reducing radiation exposuresto the environment, the public, and facility operating personnel.This standard might reference documents and other standards that have beensuperseded or withdrawn at the time the standard is applied. A statement hasbeen in
21、cluded in the references section that provides guidance on the use ofreferences.This standard does not incorporate the concepts of generating risk-informedinsights, performance-based requirements, or a graded approach to quality as-surance. The user is advised that one or more of these techniques co
22、uld enhancethe application of this standard.This standard was prepared by Working Group ANS-40.37 of the StandardsCommittee of the American Nuclear Society, whose membership at the time ofthe standards approval was as follows:C. C. Miller Chair!, Pacific Gas it terminates at the inter-face where pro
23、cessed waste or secondary waste,or both, is either returned to the facility orremoved from the facility, or both.2!This standard refers throughout to vendors,system users, facility operators, and owners;however, these references are not intendedto assign specific responsibilities of theseparties for
24、 compliance with the requirementsof this standard. These references are forconvenience and are based on typical respon-sibilities of these parties. It is recognizedthat the facility owner or operating licenseholder, or both, is ultimately responsible forcompliance with these requirements. Thebody of
25、 this standard identifies both require-ments and recommendations0guidelines forsystems.3!2 Definitions2.1 LimitationsThe definitions that follow are of a restrictivenature for the purpose of this standard.2.2 Glossary of termscompactible solid waste: Solid waste thatcan be compressed by applying ext
26、ernal pres-sure less than 1000 psi.dry, combustible solid waste: Solid waste,including materials that contain incidentalamounts of drainable liquids, that can be eas-ily oxidized by conventional incinerationtechniques.dry, noncombustible solid waste: Solid wastethat cannot be easily oxidized by conv
27、entionalincineration techniques.gaseous waste: The waste streams of noncon-densable fluids that are radioactively contam-inated with gases, condensable vapors, entrainedliquids, or particles.interface requirements: Requirements per-taining to all the connections facilitating allmass and energy flow
28、to and from an MRWPsystem. Also included are health, safety, andchemistry support requirements.liquid radioactive waste: Aqueous wastesand0or other fluids containing radioactive ma-terials that result from the operation of a nu-clear facility. Radioactive contaminated wateris the predominant volumet
29、ric waste form gen-erated by nuclear facilities, but liquid radio-active waste can include other liquids or be1!Numbers in brackets refer to corresponding numbers in Sec. 14, “References.”2!Standards concerning permanent systems for processing radioactive waste are identified in Appendix A andare sp
30、ecifically referenced in this standard where applicable.3!Appendix B provides guidelines that are intended to be helpful to users who are designing and evaluatingMRWP systems, interfacing MRWP systems for application at a facility, and designing facilities to interfacewith MRWP systems.1aqueous solu
31、tions containing a combination ofchemical species.low-level radioactive waste (LLW): Radio-active waste that is not classified as eitherhigh-level radioactive waste, transuranic waste,spent nuclear fuel, or by-product materialura-nium or thorium tailings and waste! as definedin Section IIe 2! of the
32、 Atomic Energy Act of1954, as amended 1# and not greater thanclass C concentration limits as defined under10 CFR 61 2#.mixed waste: Low-level radioactive waste thatis co-contaminated with hazardous waste asdefined in 40 CFR 261 3#, 40 CFR 262 4#, and40 CFR 268 5#.mobile low-level radioactive waste p
33、rocess-ing (MRWP) system: Any radioactive wasteprocessing system or component that is de-signed to be transportable and that is not con-sidered permanently installed as used inRegulatory Guide 1.143 RG 1.143!, “DesignGuidance for Radioactive Waste ManagementSystems, Structures, and Components Instal
34、ledin Light-Water-Cooled Nuclear Power Plants,”Rev. 2 6#.noncompactible solid waste: Solid waste thatcannot be compressed by applying external pres-sure less than 1000 psi. The 1000 psi value isbased on current technology.!nuclear facility: Any facility that, as a resultof its operation, generates w
35、aste material con-taining or potentially containing radioactive ma-terials. This includes, but is not limited to,nuclear power plants, hospitals, fuel fabrica-tion facilities, fuel reprocessing facilities, radio-active waste disposal facilities, industrialfacilities, and research facilities.oily rad
36、ioactive waste: Liquid and slurrywastes that contain more than 5% oil, grease,and other immiscible organic liquids4!by weightand radioactive materials resulting from theoperation of a nuclear facility.process control program: A systematic pro-cedure for providing reasonable assurance thatthe final w
37、aste form is in accordance with dis-posal facility acceptance criteria.radioactivematerials:Radioactive fissionprod-ucts, activation products, and concentrated nat-urally occurring radioactive substances.raw wastes: Waste as received by an MRWPsystem.safe operation, safety: Actions and activitiestha
38、t pose no immediate hazard to the public orfacility personnel. This specifically excludes“safety related” as detailed in 10 CFR 50 8#.secondary waste: Waste generated as a by-product from operation of the MRWP, or sepa-rated from the raw waste, which must behandled, processed, and disposed of in acc
39、or-dance with local and federal regulations e.g.,concentrates, wet waste, dry active waste, andtoxic chemicals!.shall, should, may: The word “shall” is usedto denote a requirement; the word “should” isused to denote a recommendation; and the word“may” is used to denote permission, neither arequireme
40、nt nor a recommendation.slurry waste: Liquid radioactive waste of highinsoluble-solids content greater than 0.1% sol-ids by weight!. For example, bead resin is trans-ferred with a high enough water-to-resin ratioand linear velocity to keep the resin suspendedcreating a slurry stream.solid radioactiv
41、e waste: Wastes in a physi-cally solid form containing radioactive materi-als that result from the operation of a nuclearfacility. Solid wastes can be radioactive due toneutron activation or surface contamination, orboth.temporary: A system, subsystem, or compo-nent whose design, construction, or in
42、tent isnot of a permanent nature with respect to fa-cility license design.ultimate disposal: Placement of radioactivewaste in a disposal facility with no intention ofremoving the waste, e.g., disposal at a shallowland burial facility licensed in accordance with10 CFR 61 2#.wet waste: Waste media con
43、taining apprecia-ble amounts greater than 1 vol %! of free liq-uid, for example, spent bead or powdered resin,filter sludge, and cartridge filters.4!For guidance, see EPA Procedure SW-846 7#.American National Standard ANSI0ANS-40.37-200923 ObjectivesThis standard establishes minimum require-ments fo
44、r the design, fabrication, installationfor use, and operation of MRWP systems toachieve the performance, safety, and opera-tional objectives specified in this section.3.1 Performance objectivesThe MRWP system shall be designed, con-structed, and operated in accordance with therequirements of this st
45、andard, but not neces-sarily with its recommendations. The mobilesystems used for processing radioactive wasteshall be designed and fabricated such that theyare capable of being operated in a manner thatcomplies with the requirements in this section.The MRWP systems shall be designed to1! receive ra
46、w wastes;2! condition and process such wastes;3! handle and contain any secondary wastesfor appropriate disposition.Waste packaged for disposal shall be accept-able for ultimate disposal. Acceptability for ul-timate disposal may be demonstrated throughthe use of a Process Control Program.The basic s
47、ystem design objectives shall be to1! minimize the overall packaged waste prod-uct volume that results from the systemsoperation;2! minimize the quantity of secondary wastegenerated by the system;3! provide for ease of system installation,maintenance, decontamination, and demobi-lization;4! provide
48、for reliable, safe, and flexible sys-tem operation while maintaining radiationexposure to operating personnel and the pub-lic via radioactive effluents “as low as is rea-sonably achievable” ALARA!.5!3.2 Safety objectivesThe MRWP system shall be designed, fabri-cated, installed, and operated so that
49、the conse-quences of a single active component failure oroperator error will not result in an uncontrolledrelease of radioactive materials to the environ-ment. For radioactive waste systems, the U.S.Nuclear Regulatory Commission NRC! has de-termined that the allowable consequences of op-eration shall result in a discharge of liquidmaterial off-site with a concentration less thanthose in 10 CFR 2010#and a discharge of liquidand gaseous material off-site having a dose thatmeets the limits of 10 CFR 20.1301 11#.3.3 Operating objectivesThe MRWP system shall
