ASTM_C_1010_-_83_1992e1.pdf

Designation:C 1010 83(Reapproved 1992)e1Standard Guide forAcceptance,Checkout,and Pre-Operational Testing of aNuclear Fuels Reprocessing Facility1This standard is issued under the fixed designation C 1010;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 parentheses indicates the year of last reapproval.Asuperscript epsilon(e)indicates an editorial change since the last revision or reapproval.e1NOTESection 10,Keywords,was added editorially in November 1992.1.Scope1.1 This guide sets forth those criteria necessary for theacceptance,checkout,and pre-operational testing of a nuclearfuels reprocessing facility.1.2 This guide is specifically applicable to a nuclear fuelsreprocessing facility employing the Purex process;however,alarge portion of this guide is also applicable to other facilitiesemploying different processes.1.3 This guide provides recommendations for procedurepreparation,acceptance criteria following construction,train-ing,component and systems tests,and final integrated testing.These procedures2when utilized in accordance with theprescribed quality assurance(QA)requirements should providepermanent QA records.1.4 This guide deals primarily with the mainline aqueous/organic(Purex)sections of a nuclear fuels reprocessing facility.Operations such as fuel receipt,headend(shearing and disso-lution),plutonium conversion,waste immobilization,and oth-ers of this nature are not included.1.5 This standard does not purport to address all of thesafety problems,if any,associated with its use.It is theresponsibility of 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 Documents2.1ANSI Standard:N15.19 Volume Calibration Techniques for Nuclear Mate-rials Controls33.Significance and Use3.1 Most reprocessing facilities in existence today in theUnited States were designed to use the Purex solvent extractionprocess,in either mixer settlers,pulsed columns,or centrifugalcontactors to recover,purify,and separate uranium and pluto-nium from spent reactor fuel.The complexity of these plantsand the nature of the material to be handled dictate the need fora comprehensive testing,evaluation,and documentation pro-gram following the turnover from construction through hotstartup of a facility.The testing,evaluation,and documentationprogram must be tailored to meet applicable state and federalregulations.3.2 The test program starts during the design and construc-tion phases with approval of detail designs,specifications,construction procedures,and actual construction activities innew facilities and during the pre-planning stages for the restartof mothballed or partially shutdown facilities.An engineeringstaff must be assembled to establish the overall testing programand to prepare the necessary,written test programs andprocedures.Early in the planning stages,a training programmust be instituted to provide trained personnel for every phaseof the startup.3.3 Procedures for acceptance,checkout,and preparationfor operation of reprocessing facilities are the primary subjectof this guide and should be written in such a manner as toprovide permanent,documented records of the test and trainingprograms and their results.Since the plant is complex,asequential testing program must be devised to test individualcomponents,then individual systems,and finally,the entireplant as an integrated unit.This approach assures that all itemsin the plant are adequately tested.4.Procedure Preparation4.1 The planning for a smooth takeover and operation of thefacility can only be accomplished by the development of a setof procedures(checkout,operations,administrative,etc.).These procedures will provide the assurance that all portions ofthe facility have been evaluated to the appropriate standard.Take care in setting up the format for these procedures so thatthey define the goals that are to be achieved,the limits withinwhich the results are acceptable,and the approvals required foracceptance.4.2 Divide the facility into small segments for procedurepreparation.These segments shall follow the normal processsystem breakdown of the facility,as well as general facility1This guide is under the jurisdiction ofASTM Committee C-26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved Dec.30,1983.Published July 1984.2Quality Assurance Programs should maintain the design intent of ANSIN46.211,Quality Assurance Requirements for the Design of Nuclear Fuel Repro-cessing Facilities,and be conducted in accordance with ANSI N46.2,QualityAssurance Program Requirements for Post Reactor Nuclear Fuel Cycle Facilities.3Available from American National Standards Institute,11 W.42nd St.,13thFloor,New York,NY 10036.1AMERICAN SOCIETY FOR TESTING AND MATERIALS100 Barr Harbor Dr.,West Conshohocken,PA 1