Regulatory Guide 1.143

Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants, for Comment

ML13350A262
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Issue date:	07/31/1978
From:	Office of Nuclear Regulatory Research
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RG-1.143
Download: ML13350A262 (6)

U.S. NUCLEAR REGULATORY COMMISSIONJuly 197800REGULATORY GUIDE.OFFICE OF STANDARDS DEVELOPMENTREGULATORY GUIDE 1.143DESIGN GUIDANCE FOR RADIOACTIVE WASTE MANAGEMENT SYSTEMS, STRUCTURES, ANDCOMPONENTS INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER PLANTSA. INTRODUCTIONParagraph (a) of k 50.34, "Contents of applica-tions; technical information," of 10 CFR Part 50,"Domestic Licensing of Production and UtilizationFacilities," requires that each application for a con-struction permit include a preliminary safety analysisreport. Part of the information required is a prelimi-nary design of-the facility, including among otherthings the principal design criteria for the facility.Appendix A, "General Design Criteria for NuclearPower Plants," to 10 CFR Part 50 establishesminimum requirements for the principal designcriteria for water-cooled nuclear power plants.Criterion I, "Quality Standards and Records," ofA'ppendix A requires that structures, systems, andcomponents important to safety be designed, fabri-cated, erected, and tested to quality standards com-mensurate with the importance to safety of the sfunction to be performed. Criterion 2, "Design sesfor Protection Against Natural Phenome,: " o -pendix A requires, among other thin "t st st Ptures. systems. and components impo" t to fetybe designed to withstand the effect ,uralphenomena such as earthquakes without lo- f capa-bility to perform their functions and that thedesign bases for these truc~rs, systems, and com-ponents reflect th hi1p' ce "the safety functionsto be perform t. c¶-eri060, "Control of Releasesof RadioapiivlMate~ils to the Environment-," ofAppen A rAA irs ts at the nuclear power unit de-sign in ma' control suitably the release ofradioactiv naterials in gaseous and liquid effluentsand to handi# radioactive solid waste produced duringnormal reactor operation, including anticipated opera-tional occurrences..This guide furnishes design guidance acceptable tothe NRC staff relating to seismic and quality groupclassification and quality assurance provisions forradioactive waste management systems, structures,and components. Further, it describes provisions forcontrolling releases of liquids containing radioactivematerials, e.g., spills or tank overflows, from allplant systems outside reactor containalog.B. DISCU ,$Sll3I One aspect of nuclear. 0o l -cration is [hecontrol and manage g, geous. and solidradioactive wast g' crated as a byprod-uct of nuclear .,ose of this guide is toprovide i ma d eria that will provide rea-sonable St components and structuresuse the. ive waste management and steamen' b down systems are designed. con-c dh,'stalled, and tested on a level commensu-he need to protect the health and safety ofpu lic and plant operating personnel. It sets forthm nimum staff recommendations and is not intendedto prohibit the implementation of more rigorous de-sign considerations, codes, standards, or quality as-surance measures.Working Group ANS-55, Radioactive Waste Sys-tems, of Subcommittee ANS-50, Nuclear PowerPlant System Engineering, of the American NuclearSociety Standards Committee has developed stand-ards that establish requirements and provide recom-mendations for the design, construction, and per-formance of BWR (ANSI N197-1976) and PWR(ANSI N199-1976) liquid radioactive waste process-ing systems. Standards for gaseous and solid radioac-tive waste processing systems are being developed.I Radioactive waste, as used in this guide. means those liq-uids. gases, or solids containing radioactive materials thatl hydesign or operating practice will be processed prior itt final dis-position.USNRC REGULATORY GUIDES Comment% should be sent to the Secretay of the Co.mmnin. US. Nutii t-q.,Regulatory Guides are issued to describe and make available to khe Public method, latory Commission. Waihington, D.C. 20555. Attention Docketnrg. a "'.,r .accepttable to the NRC nuatl of implementing specific parts of the Commission's Branch.regultations, to delineate techniques used by the &talf in evaluating specific problems The guide are issued in the followmng ten broad dniori$or postulated accidents, or to Provide guidance to applicants. Regulatory Guide:are not slubstitutes for regul-tlions, and compliance with them is not required. 1. Power Reactors 6. ProducftMethods and solutions different from those set Out in the guides will be acce't. 2. Research and Test Reactors 7. Trarrsaotlationable if they provide a basis for the findingst requiite to the issuance at continuance 3. Fuels and Materials Facilities 8. Occupational Healthof a permit at license by the Commission. 4. Environmental and Siting 9. Antitrusl Re.,ew5.Vleterits alnd Piasti Pratect'On tO. GeneratComments and suggestionr% for irrlprovements in these guides are encouraged at alltimes, and guides will be" revised, as appropriate, to accommodate comments and Reu its for single Copies 01 issued guides iwhtch may be lsi'tuwceet orfoJ r tiltQ'to reflect nevs informatlon or experience. Howsever, comments on this guide.if mini on an automatic dtobution list tfo sinrlle cur.e, of tilt.'re quide% in r.l N,eceived within about t rc, m.nths alter its issuance, wilt be particularty useful in divisionst should be made in writing to the U.S. Nuclear Regtulatory Crniin,,sJw.evalual ing the need lor an early revision. Washlington, D.C. ?M055. Attentiton D..ectot. Division osf Dociument Ciill, These standards provide more detailed guidance withregard to the specific requirements of the radioactivewaste processing system than are presented in thisguide. It is expected that these standards will be en-dorsed separately to be used in conjunction with thisguide or that reference to applicable sections ma-- beused in future revisions to this guide.For the purpose of this guide. the radwaste systemsare considered to begin at the interface valve(s) ineach line from other systems provided for collectingwastes that may contain radioactive materials and toinclude related instrumentation and control systems.The radwaste system terminates at the point of con-trolled discharge to the environment. at the point ofrecycle back to storage for reuse in the reactor, or atthe point of storage of packaged solid wastes prior toshipment offsite to a licensed burial ground. Thesteam generator blowdown system begins at, but doesnot include, the outermost containment isolationvalve on the blowdown line. It terminates at the pointof controlled discharge to the environment, at thepoint of interface with other liquid systems, or at thepoint of recycle back to the secondary systems. Ex-cept as noted, this guide does not apply to the reactorwater cleanup system, the condensate cleanup sys-tent. the chemical and volume control system, thereactor coolant and auxiliary building equipmentdrain tanks, the sumps and floor drains provided for.collecting liquid wastes, the boron recovery system.equipment used to prepare solid waste solidificationagents, the building ventilation systems (heating.ventilating, and air conditioning). or the chemicalfume hood exhaust systems.The design and construction of radioactive wastemanagement and steam generator blowdown systemsshould provide assurance that radiation exposures tooperating personnel and to the general public are aslow as is reasonably achievable. One aspect of thisconsideration is ensuring that these systems are de-signed to quality standards that enhance system relia-bility. operability, and availability. In developmentof this design guidance. the NRC staff has considereddesigns and concepts submitted in license applica-tions and resulting operating system histories. It hasalso been guided by industry practices and the cost ofdesign features, taking into account the potential im-pact on the health and safety of operating personneland the general public.C. REGULATORY POSITION1. Systems Handling Radioactive Materials inLiquidsI.1 The liquid radwaste treatment system includ-ing the steam generator blowdown systemdownstream of the second containment isolationvalve should meet the following criteria:I.1. 1 These systems should he designed andtested to requirements set forth in the codes andstandards listed in Table I supplemented by the provi-sions in I. 1.2 and in regulatory position 4 of thisguide.I. .2 Materials for pressure-retaining compo-nents should conform to the requirements of the spec-ifications for materials listed in Section 1I of theASME Boiler and Pressure Vessel Code.- except thatmalleable, wrought. or cast iron materials and plasticpipe should not be used. Materials should be compat-ible with the chemical. physical. and radioactive en-vironment of specific applications. Manufacturers'material certificates of compliance with materialspecifications. such as those contained in the codesreferenced in Table I .may he provided in lieu of cer-tified material test reports.1.1 .3 Foundations and walls of structures thathouse the liquid radwaste system should be designedto the seismic criteria described in regulatory position5 of this guide to a height sufficient to contain themaximum liquid inventory expected to be in thebuilding.I. I.4 Equipment and components used to col-lect. process, and store liquid radioactive waste neednot be designed to the seismic criteria given in regu-latory position 5 of this guide.1.2 All tanks located outside reactor containmentand containing radioactive materials in liquids shouldbe designed to prevent uncontrolled releases ofradioactive materials due to spillage (in buildings orfrom outdoor tanks). The following design featuresshould be included for tanks that may containradioactive materials:1.2.1 All tanks inside and outside the plant. in-cluding the condensate storage tanks, should haveprovisions to monitor liquid levels.. Potential over-flow conditions should actuate alarms both locallyand in the control room.1.2.2 All tank overflows and drains and samplelines should be routed to the liquid radwaste treat-ment system.-1.2.3 Indoor tanks should have curbs or elevatedthresholds with floor drains routed to the liquid rad-waste treatment system.31.2.4 The design should include provisions toprevent leakage from entering unmonitored systemsand ductwork in the area.2 Copies may he obtained from the American Society ofMechanical Engineers. United Engineering Center. 345 East 47thStreet. New York. New York 10017.Retention by an intermediate sump or drain tank designedfor handling radioactive materials and having provisions formuting 1o the liquid radwaste system is acceptable.0I401.143-2 1.2.5 Outdoor tanks should have a dike or reten-tion pond capable of preventing runoff in the event of'a tank overflow and should have provisions for sam-pling collected liquids and routing them to the liquidradwaste treatment system.2. Gaseous Radwasie Systems2. I The gaseous radwaste treatment system4 shouldmeet the following criteria:2. I.I The systemns should he designed and testedto requirements set forth in the codes and standardslisted in Table I supplemented by the provisionsnoted in 2.1.2 and in regulatory position 4 of thisguide.2.1.2 Materials for pressure-retaining compo-nents should conform to the requirements of the spec-ifications for materials listed in Section II of theASME Boiler and Pressure Vessel Code2 except thatmalleable. wrought.. or cast iron materials and plasticpipe should not be used. Materials should he compat-ible with the chemical, physical, and radioactive en-vironment of specific applications. Manufacturersmaterial certificates of compliance with materialspecifications, such ais those contained in the codesreferenced in Table I, may be provided in lieu of cer-tified materials test reports,2.1.3 Those portions of the gaseous radwastetreatment system that are intended to store or delaythe release of gaseous radioactive waste. includingportions of structures housing these systems. shouldbe designed to the seismic design criteria given inregulatory position 5 of this guide. For the systemsthat normally operate at pressures above 1.5 atmos-pheres (absolute). these criteria should apply to isola-tion valves, equipment. interconnecting piping. andcomponents located between the upstream anddownstream valves used to isolate these componentsfrom the rest of the system (e.g.. waste gas storagetanks in the PWR) and to the building housing thisequipment. For systems that operate near ambientpressure and retain gases on charcoal adsorbers. thesecriteria should apply to the tank support elements(e.g.. charcoal delay tanks in a BWR) and the build-ing housing the tanks.3. Solid Radwaste System3.1 The solid radwaste system consists of slurrywaste collection and settling tanks, spent resin stor-age tanks, phase separators, and components andsubsystems used to solidify radwastes prior to offsiteshipment. The solid radwaste handling and treatmentsystem should meet the following criteria:" For a RWR this includes the system provided for treatmentof normal offgas releases from the main condenser vacuum sys-tem beginning at the point of discharge from the condenser airremoval equipment; for a PWR this includes the system providedfor the treatment of gases stripped front the primary coolant.t. I3. 1 The system should be designed and testedt) the requirements set forth in the codes and stand-ards listed in Table I supplemented by the provisionsnoted in 3.1.2 and in regulatory position 4 of thisguide.3.1 .2 Materials for pressure-retaining conmpo-nents should conform to the requirements of the spec-ifications for materials listed in Section II of theASME Boiler and Pressure Vessel Code- except thattualleable. wrought. or cast iron materials and plasticpipe should not be used. Materials shoulh be compalt-ible with the chemical. physical, and radioactive en-vironment of specific applications. NIanufacturers"material certificates of cotmpliarnce with materialspecifications. such ats those contained in the codesreferenced in Table I , tna. vbe provided in lieu of cer-tified materials test reports.3.1.3 Foundations and adjacent walls of struc-lures that house the solid radwaste system should bedesigned to the seismic criteria given in regulatoryposition 5 of this guide to a heighl sufficient to conl-cain the maximum liquid inventory expected to be inthe building.3.1.4 Equipment and components used to col-lect, process. or store solid radwasles need not be de-signed to seismic criteria given in regulatory position5 of this guide.4. Additional Design, Construction, and TestingCriteriaIn addition to the requirements inherent in thecodes and standards listed in Table I, the followingcriteria, as a minimum, should be implemented forcomponents and systems considered in this guide:4.1 The quality assurance provisions described inregulatory position 6 of this guide should be applied.4.2 Process piping systems include the first rootvalve on sample and instrument lines. Pressure-retaining components of process syslems should usewelded construction to the maximum practicable ex-tent. Flanged joints or suitable rapid disconnect fit-tings should be used only where maintenance or op-erational requirements clearly indicate that such con-struction is preferable. Screwed connections in whichthreads provide the only seal should not be used ex-cept for instrumentation connections where weldedconnections are not suitable. Process lines should notbe less than 3/4 inch (nominal I.D.). Screwed con-nections backed up by seil welding, mechanicaljoints, or socket welding may be used on lines 3/4inch or larger but less than 2-1/2 inches (nominalI.D.). For lines 2-1/2 inches and above, pipe weldsshould be of the butt-joint type. Nonconsumablebacking rings should not be used in lines carrying re-sins or other particulate material. All welding con-stituting the pressure boundary of pressure-retaining01.143-3 components should be performed in accordance withASME Boiler and Pressure Vessel Code Section IX.-24.3 Piping systems should be hydrostatically testedin (heir entirety except at atmospheric tank connec-tions where no isolation valves exist. Pressure testingshould be performed on as large a portion of the in-place systems as practicable. Testing of piping sys-tems should be. performed in accordance with appli-cable ASME or ANSI codes, but in no case at lessthan 75 psig. The test pressure should be held for aminimum of 30 minutes with no leakage indicated.4.4 Testing provisions should be incorporated toenable periodic evaluation of the operability and re-quired functional performance of active componentsof the system.5. Seismic Design for Radwaste ManagementSystems and Structures Housing RadwasteManagement Systems5.1 Gaseous Radwaste Management Systems'5. 1.1 For the evaluation of the gaseous radwastesystem described in regulatory position 2.1.3. asimplified seismic analysis procedure to determineseismic loads may be used. The simplified procedureconsists of considering the system as a single-degree-of-freedom system and picking up a seismicresponse value from applicable flnor responsespectra, after the fundamental frequct-c. of the sys-tem. is determined. The floor response spectra shouldbe obtained analytically (regulatory position 5.2)from the application of the Regulatory Guide 1.60 de-sign response spectra normalized to the maximumground acceleration for the operating basis earth-quake (OBE), as established in the application, at thefoundation of the building housing the gaseous rad-waste system. More detailed guidance can be foundin Regulatory Guide 1.122, "Development of FloorDesign Response Spectra for Seismic Design ofFloor-Supported Equipment or Components."5. 1.2 The allowable stresses to be used for steelsystem support elements should be those given in.Specification for the Design, Fabrication and Erec-tion of Structural Steel fot Buildings," adopted inFebruary 1969.' The one-third allowable stress in-crease provisions f6r combinations involving earth-quake loads, indicated in Section 1.5.6 of the specifi-cation* should be included. For design of concretestructures, use of ACI 349-761 as endorsed in Regu-latory Guide 1.142, "Safety-Related Concrete Struc-tures for Nuclear Power Plants (Other Than ReactorVessels and Containments),'" is acceptable.5 For those systems that require seismic capabilities, as indi-cated in regulatory position 2.1.3.' Copies may be obtained from the American Institute of SteelConstruction, Inc., 101 Park Avenue, New York, New Yorkt017.5.1.3 The construction and inspection require-ments for the support elements should comply withthose stipulated in AISC or ACI Codes as appro-priate.5.2 Buildings Flousing Radwaste Systems5.2.1 Input motion at the foundation of thebuilding housing the radwaste systems should be de-fined. This motion should bedefined by normalizingthe Regulator)y Guide 1.60 spectra to the maximumground acceleration selected for the plant OBE. Asimplified analysis should be performed to determineappropriate seismic loads and floor response spectrapertinent to the location of the system, i.e., an analy-sis of the building by a several-degrees-of-freedommathematical model and the use of an approximatemethod to generate the floor response spectra forradwaste systems and the seismic loads for the build-ings. No time history analysis is required.5.2.2 The simplified method for determiningseismic loads for the building consists of (a) calculat-ing the first several modal frequencies and participa-tion factors for the building. (b) determining modalseismic loads using regulatory position 5.2.1 inputspectra, and (c) combining modal seismic loads inone of the ways described in Regulatory Guide 1.92."Combining Modal Responses and Spatial Compo-nents in Seismic Response Analysis.'"5.2.3 With regard to generation of floor re-sponse spectra for radwaste systems, simplifiedmethods that give approximate floor response spectrawithout need for performing a time history analysismay be used.5.2.4 The load factors and load combinations tobe used for the building should be those given inACI 349-76 1 as endorsed in Regulatory Guide 1. 142.The allowable stresses for steel components shouldbe those given in the AISC Manual. (See regulatoryposition 5.1.2.)5.2.5 The construction and inspection require-ments for the building elements should comply withthose stipulated in the AISC or ACi Code as appro-priate.5.2.6 The foundation media of structures hous-ing the radwaste systems should be selected and de-signed to prevent liquefaction from the effects of themaximum ground acceleration selected for the plantOBE.5.3 In lieu of the criteria and procedures definedabove, optional shield structures constructed aroundand supporting the radwaste systems may be erectedto protect the radwaste systems from effects of hous-ing structural failure. If this option is adopted, the' Copies may be obtained from the American Concrete Insti-tute, P.O. Box 19150, Redford Station. Delroit, Michigan48219..104I1.143-4 I.9procedures described in. regulatory position 5.2 needonly be applied to the shield structures while treatingthe rest of the housing structures as non-seismicCategory I.6. Quality Assurance for Radwaste ManagementSystenmsSince the impact of these systems on safety is lim-ited, a quality assurance program corresponding tothe full extent of Appendix B to 10 CFR Part 50 isnot required. However. to ensure that systems willperform their intended function. a quality assuranceprogram sufficient to ensure that all design. construc-tion. and testing provisions are met should be estab-lished and documented. The following quality ass'ur-ance program is acceptable to the NRC staff. It isreprinted by permission of the American Nuclear So-ciety from ANSI N199-1976, "Liquid RadioactiveWaste Processing System for Pressurized WaterReactor Plants...s"4.2.3 Quality Control. The design, procure-ment. fabrication and construction activities shallconform to the quality control provisions of the codesand standards specified herein. In addition, or wherenot covered by the referenced codes and standards.the following quality control features shall be estab-lished."4.2.3.1 System Designer and Procurer"(I) Design and Procurement DocumentControl-Design and procurement documents shall beindependently verified for cotiformance to the re-quirements of this standard by individual(s) withinthe design organization who are not the originators ofthe document. Changes to these documents shall beverified or controlled to maintain conformance to thisstandard."(2) Control of Purchased Material. Equip-ment and Services-Measures to ensure that suppliersof material, equipment and construction services arecapable of supplying these items to the quality speci-fied in the procurement documents shall be estab-lished. This may be done by an evaluation or a sur-vey of the suppliers' products and facilities."(3) Instructions shall be provided in pro-curement documents to control the handling, storage,shipping and preservation of material and equipmentto prevent damage. deterioration or reduction ofcleanness.K Copies may he obtained from American Nuclear Society.555 North Kensington Avenue. L.a Grange Park, Illinois 60525."4.2.3.2 System Constructor-(0I) Inspection. In addition to required codeinspections a program for inspection of activities af-fecting quality shall be established and executed by.or for. the organization performing the activity to ver-ify conformance with the documented instructions.procedures, and drawings for accomplishing the ac-tivity. This shall include the visual inspection ofcomponents prior to installation for confornmance withprocurement documents and the visual inspection ofitems and systems following installation, cleannessand passivation (where applied)."'(2) Inspection. Test and Operating Status.Measures should be established to provide for theidentification of items which have satisfactorilypassed required inspections and tests.-(3) Identification and Corrective Action forItems of Nonconformance. Measures should he estab-lishe't #o identify items of nonconformance with re-gard to the requirements of the procuremcntit docu-ments or applicable codes and standards and to iden-tifv the action taken to correct such items.In Section 4.2.3.2(3). *ilems of nonconf'ormance"should 5e interpreted to include failut.1 , 111:- afunc-tions, deficiencies, deviations, and defective materialand equipment.Sufficient records should be maintained to furnishevidence that the measures identified above are beingimplemented. The records should include results ofreviews and inspections and should be identifiableand retrievable.* D. IMPLEMENTATIONThe purpose of this section is to provide informa-tion to applicants regarding the NRC staff"s plans forusing this regulatory guide.This guide reflects current NRC staff practice.Therefore, except in those cases in which the appli-cant proposes an acceptable alternative method forcomplying with specified portions of the Commis-sion's regulations. the method described herein isbeing and will continue to be used in evaluation ofsubmittals in connection with applications for operat-ing licenses, construction permits, or amendmentsthereto until this guide is revised as a result ofsuggestions from the public or additional staffreview.01.143-5 TABLE 1EQUIPMENT CODESFIQUI PMENTCODESDetsigni and'a hr ica Iio)n"'elderQualificationM~aterials' and ProceduresInspectionand TestingPrcssutie Vesisel0-I ni VSphri 'IanksIli ping.- and V'alve.-ASMI- CodeVIII\ I)v I;-\SME'Section III. Clam, 3. krAPI 6501. orA.W\VWA 1I) -I W..AS.ME' Scctioh III.Class 3. or API 620'.\S.IE CodeSection VIII, Div. IAN.I TE.MAANSI t131.1ASME CodeSection IIASME Code:Section IIASMI" code:Section IIASMNE CodeSection IIAS'IM anASME CodeSection IIAS.IE CodeSection II orManufacturersStandardASME CodeSection IXASNIIE Co'deSection IXA.SMIE CodeSection IXASNII: CodeSection IXAS.ME Co'deSection IXASNIF CodeSection IX(a.s required)ASNME CodeSectionVIll. D)iv. IAS\IE Code,sect ion Ill.CiGas 3. or API 650.or AWWA D-I1002ASME Codc' Section Ill.Cklss 3. or API 6202ASNSMI F CodeSeclton VIII. Div. IANSI 1331. 1ASMENSection IllClans 3: orHydraulic InsltimueStantjdard0I Fih..i .Io fLIII11:,:Cd 11II%l~ic o l nk ma -% ! '.CL,01 Ill iWird.inic., %kith aippr.priaiv. :,IIcIls tif SL'ctjim; 10. ...SNst Bo~iler and t'res.urc.\S.\tt (*odc. lo~r app. c~zit..ti:, uliei loaitiie miilltme uit. rI'i ~r~ )ii OCRt'r 1 r ihr~midA.t\lhIIF ciI r' .mitd iit! M31061 ~ c 'fC .Alll i .i..n Ole ktsInmi.hiw% hinwtSm1ifice crtei of img itw i ,' It i t)r 10 CIrcPr.0 r iitr ~ rdI. 143-6