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

U.S. NUCLEAR REGULATORY COMMISSION July 1978

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REGULATORY GUIDE.

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.143 DESIGN GUIDANCE FOR RADIOACTIVE WASTE MANAGEMENT SYSTEMS, STRUCTURES, AND

COMPONENTS INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER PLANTS

A. INTRODUCTION

classification and quality assurance provisions for radioactive waste management systems, structures, Paragraph (a) of k 50.34, "Contents of applica- and components. Further, it describes provisions for tions; technical information," of 10 CFR Part 50,

controlling releases of liquids containing radioactive

"Domestic Licensing of Production and Utilization materials, e.g., spills or tank overflows, from all Facilities," requires that each application for a con- plant systems outside reactor containalog.

struction permit include a preliminary safety analysis report. Part of the information required is a prelimi- B. DISCU ,$Sll3I *.

nary design of-the facility, including among other things the principal design criteria for the facility. One aspect of nuclear. 0o l -cration is [he Appendix A, "General Design Criteria for Nuclear control and manage geous. and solid g,

Power Plants," to 10 CFR Part 50 establishes radioactive wast g' crated as a byprod- minimum requirements for the principal design uct of nuclear . ,ose of this guide is to criteria for water-cooled nuclear power plants. provide i ma d eria that will provide rea- sonable St components and structures Criterion I, "Quality Standards and Records," of use the. ive waste management and steam A'ppendix A requires that structures, systems, and components important to safety be designed, fabri- en' b down systems are designed. con- c dh,'stalled, and tested on a level commensu- cated, erected, and tested to quality standards com- he need to protect the health and safety of mensurate with the importance to safety of the s pu lic and plant operating personnel. It sets forth function to be performed. Criterion 2, "Design ses o m nimum staff recommendations and is not intended for Protection Against Natural Phenome,: " -

to prohibit the implementation of more rigorous de- pendix A requires, among other thin "t st st P

tures. systems. and components impo" t to fety sign considerations, codes, standards, or quality as- be designed to withstand the effect ,ural surance measures.

phenomena such as earthquakes without lo- f capa- Working Group ANS-55, Radioactive Waste Sys- bility to perform their ,4,t* functions and that the tems, of Subcommittee ANS-50, Nuclear Power design bases for these truc~rs, systems, and com- Plant System Engineering, of the American Nuclear ponents reflect thhi1p' ce "the safety functions Society Standards Committee has developed stand- to be perform t.c¶-eri060, "Control of Releases ards that establish requirements and provide recom- of RadioapiivlMate~ils to the Environment-," of mendations for the design, construction, and per- Appen A rAA irs tsat the nuclear power unit de- formance of BWR (ANSI N197-1976) and PWR

sign in ma' control suitably the release of (ANSI N199-1976) liquid radioactive waste process- radioactiv naterials in gaseous and liquid effluents ing systems. Standards for gaseous and solid radioac- and to handi# radioactive solid waste produced during tive waste processing systems are being developed.

normal reactor operation, including anticipated opera- tional occurrences. I Radioactive waste, as used in this guide. means those liq- uids. gases, or solids containing radioactive materials thatl hy

.This guide furnishes design guidance acceptable to design or operating practice will be processed prior itt final dis- the NRC staff relating to seismic and quality group 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 issuedin the followmngten 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. Producft Methods and solutions different from those set Out in the guides will be acce't. 2. Research and Test Reactors 7. Trarrsaotlation able if they provide a basis for the findingst requiite to the issuance at continuance 3. Fuels and Materials Facilities 8. Occupational Health of a permit at license by the Commission. 4. Environmental and Siting 9.

tO.

Antitrusl Re.,ew Generat

5.Vleteritsalnd Piasti Pratect'On are encouraged at all Comments and suggestionr% for irrlprovements in these guides times, and guides will be"revised, as appropriate, to accommodate comments and Reu its for single Copies 01 issued guides iwhtch may be lsi'tuwceet orfoJtiltQ'

r to reflect nevs informatlon or experience. Howsever, commentst 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, wil 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 with I.1. 1 These systems should he designed and regard to the specific requirements of the radioactive tested to requirements set forth in the codes and waste processing system than are presented in this guide. It is expected that these standards will be en- dorsed separately to be used in conjunction with this standards listed in Table I supplemented by the provi- sions in I. 1.2 and in regulatory position 4 of this guide.

0

guide or that reference to applicable sections ma-- be I. .2 Materials for pressure-retaining compo- used in future revisions to this guide.

For the purpose of this guide. the radwaste systems nents should conform to the requirements of the spec- ifications for materials listed in Section 1I of the I

are considered to begin at the interface valve(s) in ASME Boiler and Pressure Vessel Code.- except that each line from other systems provided for collecting wastes that may contain radioactive materials and to malleable, wrought. or cast iron materials and plastic pipe should not be used. Materials should be compat-

4 include related instrumentation and control systems. ible with the chemical. physical. and radioactive en- The radwaste system terminates at the point of con- vironment of specific applications. Manufacturers'

trolled discharge to the environment. at the point of material certificates of compliance with material recycle back to storage for reuse in the reactor, or at specifications. such as those contained in the codes the point of storage of packaged solid wastes prior to referenced in Table I . may he provided in lieu of cer- shipment offsite to a licensed burial ground. The tified material test reports.

steam generator blowdown system begins at, but does

1.1 .3 Foundations and walls of structures that not include, the outermost containment isolation valve on the blowdown line. It terminates at the point house the liquid radwaste system should be designed to the seismic criteria described in regulatory position of controlled discharge to the environment, at the point of interface with other liquid systems, or at the 5 of this guide to a height sufficient to contain the maximum liquid inventory expected to be in the point of recycle back to the secondary systems. Ex- building.

cept as noted, this guide does not apply to the reactor water cleanup system, the condensate cleanup sys- I. I.4 Equipment and components used to col- tent. the chemical and volume control system, the lect. process, and store liquid radioactive waste need reactor coolant and auxiliary building equipment not be designed to the seismic criteria given in regu- drain tanks, the sumps and floor drains provided for. latory position 5 of this guide.

collecting liquid wastes, the boron recovery system.

equipment used to prepare solid waste solidification 1.2 All tanks located outside reactor containment agents, the building ventilation systems (heating. and containing radioactive materials in liquids should ventilating, and air conditioning). or the chemical be designed to prevent uncontrolled releases of fume hood exhaust systems. radioactive materials due to spillage (in buildings or from outdoor tanks). The following design features The design and construction of radioactive waste should be included for tanks that may contain management and steam generator blowdown systems radioactive materials:

should provide assurance that radiation exposures to operating personnel and to the general public are as 1.2.1 All tanks inside and outside the plant. in- low as is reasonably achievable. One aspect of this cluding the condensate storage tanks, should have consideration is ensuring that these systems are de- provisions to monitor liquid levels.. Potential over- signed to quality standards that enhance system relia- flow conditions should actuate alarms both locally bility. operability, and availability. In development and in the control room.

of this design guidance. the NRC staff has considered designs and concepts submitted in license applica- 1.2.2 All tank overflows and drains and sample tions and resulting operating system histories. It has lines should be routed to the liquid radwaste treat- also been guided by industry practices and the cost of ment system.-

design features, taking into account the potential im- 1.2.3 Indoor tanks should have curbs or elevated pact on the health and safety of operating personnel thresholds with floor drains routed to the liquid rad- and the general public. 3 waste treatment system.

1.2.4 The design should include provisions to prevent leakage from entering unmonitored systems

C. REGULATORY POSITION

and ductwork in the area.

1. Systems Handling Radioactive Materials in Liquids

2 Copies may he obtained from the American Society of I.1 The liquid radwaste treatment system includ- Mechanical Engineers. United Engineering Center. 345 East 47th Street. New York. New York 10017.

ing the steam generator blowdown system Retention by an intermediate sump or drain tank designed downstream of the second containment isolation valve should meet the following criteria:

for handling radioactive materials and having provisions for muting 1o the liquid radwaste system is acceptable. 0

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1.2.5 Outdoor tanks should have a dike or reten- t. 1 The system should be designed and tested I3.

tion pond capable of preventing runoff in the event of t) the requirements set forth in the codes and stand-

'a tank overflow and should have provisions for sam- ards listed in Table I supplemented by the provisions pling collected liquids and routing them to the liquid noted in 3.1.2 and in regulatory position 4 of this radwaste treatment system. guide.

3.1 .2 Materials for pressure-retaining conmpo-

2. Gaseous Radwasie Systems nents should conform to the requirements of the spec-

2. I The gaseous radwaste treatment system 4 should ifications for materials listed in Section II of the meet the following criteria: ASME Boiler and Pressure Vessel Code- except that tualleable. wrought. or cast iron materials and plastic

2. I.I The systemns should he designed and tested pipe should not be used. Materials shoulh be compalt- to requirements set forth in the codes and standards ible with the chemical. physical, and radioactive en- listed in Table I supplemented by the provisions vironment of specific applications. NIanufacturers"

noted in 2.1.2 and in regulatory position 4 of this material certificates of cotmpliarnce with material guide. specifications. such ats those contained in the codes

2.1.2 Materials for pressure-retaining compo- referenced in Table I , tna. vbe provided in lieu of cer- nents should conform to the requirements of the spec- tified materials test reports.

ifications for materials listed in Section II of the 3.1.3 Foundations and adjacent walls of struc- ASME Boiler and Pressure Vessel Code 2 except that lures that house the solid radwaste system should be malleable. wrought.. or cast iron materials and plastic designed to the seismic criteria given in regulatory pipe should not be used. Materials should he compat- position 5 of this guide to a heighl sufficient to conl- ible with the chemical, physical, and radioactive en- cain the maximum liquid inventory expected to be in vironment of specific applications. Manufacturers the building.

material certificates of compliance with material specifications, such ais those contained in the codes 3.1.4 Equipment and components used to col- referenced in Table I, may be provided in lieu of cer- lect, process. or store solid radwasles need not be de- tified materials test reports, signed to seismic criteria given in regulatory position

5 of this guide.

2.1.3 Those portions of the gaseous radwaste treatment system that are intended to store or delay the release of gaseous radioactive waste. including 4. Additional Design, Construction, and Testing portions of structures housing these systems. should Criteria be designed to the seismic design criteria given in In addition to the requirements inherent in the regulatory position 5 of this guide. For the systems codes and standards listed in Table I, the following that normally operate at pressures above 1.5 atmos- criteria, as a minimum, should be implemented for pheres (absolute). these criteria should apply to isola- components and systems considered in this guide:

tion valves, equipment. interconnecting piping. and components located between the upstream and 4.1 The quality assurance provisions described in downstream valves used to isolate these components regulatory position 6 of this guide should be applied.

from the rest of the system (e.g.. waste gas storage tanks in the PWR) and to the building housing this 4.2 Process piping systems include the first root equipment. For systems that operate near ambient valve on sample and instrument lines. Pressure- pressure and retain gases on charcoal adsorbers. these retaining components of process syslems should use criteria should apply to the tank support elements welded construction to the maximum practicable ex- (e.g.. charcoal delay tanks in a BWR) and the build- tent. Flanged joints or suitable rapid disconnect fit- tings should be used only where maintenance or op- ing housing the tanks.

erational requirements clearly indicate that such con-

3. Solid Radwaste System struction is preferable. Screwed connections in which threads provide the only seal should not be used ex-

3.1 The solid radwaste system consists of slurry cept for instrumentation connections where welded waste collection and settling tanks, spent resin stor- connections are not suitable. Process lines should not age tanks, phase separators, and components and be less than 3/4 inch (nominal I.D.). Screwed con- subsystems used to solidify radwastes prior to offsite nections backed up by seil welding, mechanical shipment. The solid radwaste handling and treatment joints, or socket welding may be used on lines 3/4 system should meet the following criteria: inch or larger but less than 2-1/2 inches (nominal I.D.). For lines 2-1/2 inches and above, pipe welds

" For a RWR this includes the system provided for treatment should be of the butt-joint type. Nonconsumable of normal offgas releases from the main condenser vacuum sys- backing rings should not be used in lines carrying re- tem beginning at the point of discharge from the condenser air

0 removal equipment; for a PWR this includes the system provided for the treatment of gases stripped front the primary coolant.

sins or other particulate material. All welding con- stituting the pressure boundary of pressure-retaining

1.143-3

components should be performed in accordance with 5.1.3 The construction and inspection require- ASME Boiler and Pressure Vessel Code Section IX.-2 ments for the support elements should comply with

4.3 Piping systems should be hydrostatically tested in (heir entirety except at atmospheric tank connec- tions where no isolation valves exist. Pressure testing those stipulated in AISC or ACI Codes as appro- priate.

5.2 Buildings Flousing Radwaste Systems

.1 should be performed on as large a portion of the in-

5.2.1 Input motion at the foundation of the place systems as practicable. Testing of piping sys- building housing the radwaste systems should be de- tems should be. performed in accordance with appli- fined. This motion should bedefined by normalizing cable ASME or ANSI codes, but in no case at less the Regulator)y Guide 1.60 spectra to the maximum than 75 psig. The test pressure should be held for a minimum of 30 minutes with no leakage indicated. ground acceleration selected for the plant OBE. A

simplified analysis should be performed to determine

4.4 Testing provisions should be incorporated to appropriate seismic loads and floor response spectra enable periodic evaluation of the operability and re- pertinent to the location of the system, i.e., an analy- quired functional performance of active components sis of the building by a several-degrees-of-freedom of the system. mathematical model and the use of an approximate method to generate the floor response spectra for

5. Seismic Design for Radwaste Management radwaste systems and the seismic loads for the build- Systems and Structures Housing Radwaste ings. No time history analysis is required.

Management Systems 5.2.2 The simplified method for determining

5.1 Gaseous Radwaste Management Systems' seismic loads for the building consists of (a) calculat- ing the first several modal frequencies and participa-

5. 1.1 For the evaluation of the gaseous radwaste tion factors for the building. (b) determining modal system described in regulatory position 2.1.3. a seismic loads using regulatory position 5.2.1 input simplified seismic analysis procedure to determine spectra, and (c) combining modal seismic loads in seismic loads may be used. The simplified procedure one of the ways described in Regulatory Guide 1.92.

consists of considering the system as a single- "Combining Modal Responses and Spatial Compo- degree-of-freedom system and picking up a seismic nents in Seismic Response Analysis.'"

response value from applicable flnor response spectra, after the fundamental frequct-c. of the sys- 5.2.3 With regard to generation of floor re- tem. is determined. The floor response spectra should sponse spectra for radwaste systems, simplified be obtained analytically (regulatory position 5.2)

from the application of the Regulatory Guide 1.60 de- methods that give approximate floor response spectra without need for performing a time history analysis 0

sign response spectra normalized to the maximum may be used.

ground acceleration for the operating basis earth- 5.2.4 The load factors and load combinations to quake (OBE), as established in the application, at the be used for the building should be those given in foundation of the building housing the gaseous rad- ACI 349-76 1 as endorsed in Regulatory Guide 1. 142.

waste system. More detailed guidance can be found The allowable stresses for steel components should in Regulatory Guide 1.122, "Development of Floor be those given in the AISC Manual. (See regulatory Design Response Spectra for Seismic Design of position 5.1.2.)

Floor-Supported Equipment or Components."

5. 1.2 The allowable stresses to be used for steel 5.2.5 The construction and inspection require- system support elements should be those given in ments for the building elements should comply with

.Specification for the Design, Fabrication and Erec- those stipulated in the AISC or ACi Code as appro- 4 tion of Structural Steel fot Buildings," adopted in priate.

February 1969.' The one-third allowable stress in- 5.2.6 The foundation media of structures hous- crease provisions f6r combinations involving earth- ing the radwaste systems should be selected and de- I

quake loads, indicated in Section 1.5.6 of the specifi- signed to prevent liquefaction from the effects of the cation* should be included. For design of concrete maximum ground acceleration selected for the plant structures, use of ACI 349-761 as endorsed in Regu- OBE.

latory Guide 1.142, "Safety-Related Concrete Struc- tures for Nuclear Power Plants (Other Than Reactor 5.3 In lieu of the criteria and procedures defined Vessels and Containments),'" is acceptable. above, optional shield structures constructed around and supporting the radwaste systems may be erected to protect the radwaste systems from effects of hous-

5 For those systems that require seismic capabilities, as indi- ing structural failure. If this option is adopted, the cated in regulatory position 2.1.3.

' Copies may be obtained from the American Institute of Steel ' Copies may be obtained from the American Concrete Insti- Construction, Inc., 101 Park Avenue, New York, New York tute, P.O. Box 19150, Redford Station. Delroit, Michigan t017. 48219.

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procedures described in. regulatory position 5.2 need "4.2.3.2 System Constructor only be applied to the shield structures while treating I.9

-(0I) Inspection. In addition to required code the rest of the housing structures as non-seismic Category I. inspections a program for inspection of activities af- fecting quality shall be established and executed by.

or for. the organization performing the activity to ver-

6. Quality Assurance for Radwaste Management ify conformance with the documented instructions.

Systenms procedures, and drawings for accomplishing the ac- Since the impact of these systems on safety is lim- tivity. This shall include the visual inspection of ited, a quality assurance program corresponding to components prior to installation for confornmance with the full extent of Appendix B to 10 CFR Part 50 is procurement documents and the visual inspection of not required. However. to ensure that systems will items and systems following installation, cleanness perform their intended function. a quality assurance and passivation (where applied).

program sufficient to ensure that all design. construc- tion. and testing provisions are met should be estab- "'(2) Inspection. Test and Operating Status.

lished and documented. The following quality ass'ur- Measures should be established to provide for the ance program is acceptable to the NRC staff. It is identification of items which have satisfactorily reprinted by permission of the American Nuclear So- passed required inspections and tests.

ciety from ANSI N199-1976, "Liquid Radioactive Waste Processing System for Pressurized Water -(3) Identification and Corrective Action for Reactor Plants...s Items of Nonconformance. Measures should he estab- lishe't #o identify items of nonconformance with re-

"4.2.3 Quality Control. The design, procure- gard to the requirements of the procuremcntit docu- ment. fabrication and construction activities shall ments or applicable codes and standards and to iden- conform to the quality control provisions of the codes tifv the action taken to correct such items.

and standards specified herein. In addition, or where not covered by the referenced codes and standards.

In Section 4.2.3.2(3). *ilems of nonconf'ormance"

the following quality control features shall be estab- should 5e interpreted to include failut.1 , 111:-afunc- lished. tions, deficiencies, deviations, and defective material

"4.2.3.1 System Designer and Procurer and equipment.

"(I) Design and Procurement Document Sufficient records should be maintained to furnish Control-Design and procurement documents shall be evidence that the measures identified above are being independently verified for cotiformance to the re- implemented. The records should include results of quirements of this standard by individual(s) within reviews and inspections and should be identifiable the design organization who are not the originators of and retrievable.

the document. Changes to these documents shall be verified or controlled to maintain conformance to this standard. *

D. IMPLEMENTATION

"(2) Control of Purchased Material. Equip- The purpose of this section is to provide informa- ment and Services-Measures to ensure that suppliers tion to applicants regarding the NRC staff"s plans for of material, equipment and construction services are using this regulatory guide.

capable of supplying these items to the quality speci- fied in the procurement documents shall be estab- This guide reflects current NRC staff practice.

lished. This may be done by an evaluation or a sur- Therefore, except in those cases in which the appli- vey of the suppliers' products and facilities. cant proposes an acceptable alternative method for

"(3) Instructions shall be provided in pro- complying with specified portions of the Commis- curement documents to control the handling, storage, sion's regulations. the method described herein is shipping and preservation of material and equipment being and will continue to be used in evaluation of to prevent damage. deterioration or reduction of submittals in connection with applications for operat- cleanness. ing licenses, construction permits, or amendments thereto until this guide is revised as a result of K Copies may he obtained from American Nuclear Society. suggestions from the public or additional staff

555 North Kensington Avenue. L.a Grange Park, Illinois 60525. review.

0

1.143-5

TABLE 1 EQUIPMENT CODES

FIQUI PMENT CODES

"'elder Detsigni and Qualification Inspection and Testing

'ahr ica Iio)n M~aterials' and Procedures Prcssutie Vesisel ASMI- Code ASME Code ASME Code ASNME Code Sc*tion VIII\ I)v I Section II Section IX SectionVIll. D)iv. I

-\SME'

ASME Code: ASNIIE Co'de AS\IE Code,Section III. Clam, 3. kr Section II Section IX sect ion Ill.

0-Ini VSphri'Ianks API 6501. or CiGas 3. or API 650.

A.W\VWA 1I)- I W..

or AWWA D-I1002 AS.ME' Scctioh III. ASMI" code: A.SMIE Code ASME Codc' Section Ill.

Class 3. or API 620' Section II Section IX Cklss 3. or API 6202

.\S.IE Code ASMNE Code ASNII: Code ASNSMI F Code Section VIII, Div. I Section II Section IX Seclton VIII. Div. I

AN.I TE.MA

Ili ping.- and V'alve.- ANSI t131.1 AS'IM an AS.ME Co'de ANSI 1331. 1 ASME Code Section IX

Section II

AS.IE Code ASNIF Code ASMEN

Stantjdard Section II or Section IX Section Ill Manufacturers (a.s required) Clans 3: or Standard Hydraulic Insltimue

0

IFih..i .Io fLIII11:,:Cd 11II%l~ic l o nkma -% ! '.CL,01Ill 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~mid A.t\lhIIF ciI r' .mitdM31061 iit! ~ c.Alll'fC

i. i..n Ole ktsInmi.hiw% hinwtSm1ifice crtei imgof ,'

itw i It t)r i 10 CIrcPr.0 r iitr ~ rd I. 143-6