Regulatory Guide 1.143
| 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 00 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
Paragraph (a) of k 50.34, "Contents of applica-tions; technical information," of 10 CFR Part 50,"Domestic Licensing of Production and Utilization Facilities," requires that each application for a con-struction permit include a preliminary safety analysis report. Part of the information required is a prelimi-nary design of-the facility, including among other things the principal design criteria for the facility.Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 establishes minimum requirements for the principal design criteria for water-cooled nuclear power plants.Criterion I, "Quality Standards and Records," of A'ppendix A requires that structures, systems, and components important to safety be designed, fabri-cated, erected, and tested to quality standards com-mensurate with the importance to safety of the s function to be performed.
Criterion
2, "Design ses for Protection Against Natural Phenome,: " o -pendix A requires, among other thin "t st st P tures. systems. and components impo" t to fety be designed to withstand the effect ,ural phenomena such as earthquakes without lo- f capa-bility to perform their functions and that the design bases for these truc~rs, systems, and com-ponents reflect th hi1p' ce "the safety functions to be perform t. c¶-eri060, "Control of Releases of RadioapiivlMate~ils to the Environment-," of Appen A rAA irs ts at the nuclear power unit de-sign in ma' control suitably the release of radioactiv naterials in gaseous and liquid effluents and to handi# radioactive solid waste produced during normal reactor operation, including anticipated opera-tional occurrences..This guide furnishes design guidance acceptable to the NRC staff relating to seismic and quality group classification and quality assurance provisions for radioactive waste management systems, structures, and components.
Further, it describes provisions for controlling releases of liquids containing radioactive materials, e.g., spills or tank overflows, from all plant systems outside reactor containalog.
B. DISCU ,$Sll3I One aspect of nuclear. 0o l -cration is [he control and manage g, geous. and solid radioactive wast g' crated as a byprod-uct of nuclear .,ose of this guide is to provide i ma d eria that will provide rea-sonable St components and structures use the. ive waste management and steam en' b down systems are designed.
con-c dh,'stalled, and tested on a level commensu-he need to protect the health and safety of pu lic and plant operating personnel.
It sets forth m nimum staff recommendations and is not intended to prohibit the implementation of more rigorous de-sign considerations, codes, standards, or quality as-surance measures.Working Group ANS-55, Radioactive Waste Sys-tems, of Subcommittee ANS-50, Nuclear Power Plant System Engineering, of the American Nuclear Society Standards Committee has developed stand-ards that establish requirements and provide recom-mendations for the design, construction, and per-formance of BWR (ANSI N197-1976)
and PWR (ANSI N199-1976)
liquid radioactive waste process-ing systems. Standards for gaseous and solid radioac-tive waste processing systems are being developed.
I Radioactive waste, as used in this guide. means those liq-uids. gases, or solids containing radioactive materials thatl hy design or operating practice will be processed prior itt final dis-positio
n. USNRC REGULATORY
GUIDES Comment% should be sent to the Secretay of the Co.mmnin.
US. Nutii t-q., Regulatory Guides are issued to describe and make available to khe Public method, latory Commission.
Waihington, D.C. 20555. Attention Docketnrg.
a "'.,r .accepttable to the NRC nuatl of implementing specific parts of the Commission's Branch.regultations, to delineate techniques used by the &talf in evaluating specific problems The guide are issued in the followmng ten broad dniori$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. 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. Antitrusl Re.,ew 5.Vleterits alnd Piasti Pratect'On tO. Generat Comments and suggestionr%
for irrlprovements in these guides are encouraged at all 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 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, wil t 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 regard to the specific requirements of the radioactive 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 guide or that reference to applicable sections ma-- be used in future revisions to this guide.For the purpose of this guide. the radwaste systems are considered to begin at the interface valve(s) in each line from other systems provided for collecting wastes that may contain radioactive materials and to include related instrumentation and control systems.The radwaste system terminates at the point of con-trolled discharge to the environment.
at the point of recycle back to storage for reuse in the reactor, or at the point of storage of packaged solid wastes prior to shipment offsite to a licensed burial ground. The steam generator blowdown system begins at, but does not include, the outermost containment isolation valve on the blowdown line. It terminates at the point of controlled discharge to the environment, at the point of interface with other liquid systems, or at the point of recycle back to the secondary systems. Ex-cept as noted, this guide does not apply to the reactor water cleanup system, the condensate cleanup sys-tent. the chemical and volume control system, the reactor coolant and auxiliary building equipment drain tanks, the sumps and floor drains provided for.collecting liquid wastes, the boron recovery system.equipment used to prepare solid waste solidification agents, the building ventilation systems (heating.ventilating, and air conditioning).
or the chemical fume hood exhaust systems.The design and construction of radioactive waste management and steam generator blowdown systems should provide assurance that radiation exposures to operating personnel and to the general public are as low as is reasonably achievable.
One aspect of this consideration is ensuring that these systems are de-signed to quality standards that enhance system relia-bility. operability, and availability.
In development of this design guidance.
the NRC staff has considered designs and concepts submitted in license applica-tions and resulting operating system histories.
It has also been guided by industry practices and the cost of design features, taking into account the potential im-pact on the health and safety of operating personnel and the general public.C. REGULATORY
POSITION 1. Systems Handling Radioactive Materials in Liquids I.1 The liquid radwaste treatment system includ-ing the steam generator blowdown system downstream of the second containment isolation valve should meet the following criteria: I.1. 1 These systems should he designed and tested to requirements set forth in the codes and standards listed in Table I supplemented by the provi-sions in I. 1.2 and in regulatory position 4 of this guide.I. .2 Materials for pressure-retaining compo-nents should conform to the requirements of the spec-ifications for materials listed in Section 1I of the ASME Boiler and Pressure Vessel Code.- except that malleable, wrought. or cast iron materials and plastic pipe 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 material specifications.
such as those contained in the codes referenced in Table I .may he provided in lieu of cer-tified material test reports.1.1 .3 Foundations and walls of structures that house the liquid radwaste system should be designed to the seismic criteria described in regulatory position 5 of this guide to a height sufficient to contain the maximum liquid inventory expected to be in the building.I. I.4 Equipment and components used to col-lect. process, and store liquid radioactive waste need not be designed to the seismic criteria given in regu-latory position 5 of this guide.1.2 All tanks located outside reactor containment and containing radioactive materials in liquids should be designed to prevent uncontrolled releases of radioactive materials due to spillage (in buildings or from outdoor tanks). The following design features should be included for tanks that may contain radioactive materials:
1.2.1 All tanks inside and outside the plant. in-cluding the condensate storage tanks, should have provisions to monitor liquid levels.. Potential over-flow conditions should actuate alarms both locally and in the control room.1.2.2 All tank overflows and drains and sample lines should be routed to the liquid radwaste treat-ment system.-1.2.3 Indoor tanks should have curbs or elevated thresholds with floor drains routed to the liquid rad-waste treatment system.3 1.2.4 The design should include provisions to prevent leakage from entering unmonitored systems and ductwork in the area.2 Copies may he obtained from the American Society of Mechanical Engineers.
United Engineering Center. 345 East 47th Street. New York. New York 10017.Retention by an intermediate sump or drain tank designed for handling radioactive materials and having provisions for muting 1o the liquid radwaste system is acceptable.
0 I 4 0 1.143-2
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 liquid radwaste treatment system.2. Gaseous Radwasie Systems 2. I The gaseous radwaste treatment system 4 should meet the following criteria: 2. I.I The systemns should he designed and tested to requirements set forth in the codes and standards listed in Table I supplemented by the provisions noted in 2.1.2 and in regulatory position 4 of this guide.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 the ASME Boiler and Pressure Vessel Code 2 except that malleable.
wrought..
or cast iron materials and plastic pipe should not be used. Materials should he compat-ible with the chemical, physical, and radioactive en-vironment of specific applications.
Manufacturers material certificates of compliance with material specifications, such ais those contained in the codes referenced in Table I, may be provided in lieu of cer-tified materials test reports, 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 portions of structures housing these systems. should be designed to the seismic design criteria given in regulatory position 5 of this guide. For the systems that normally operate at pressures above 1.5 atmos-pheres (absolute).
these criteria should apply to isola-tion valves, equipment.
interconnecting piping. and components located between the upstream and downstream valves used to isolate these components from the rest of the system (e.g.. waste gas storage tanks in the PWR) and to the building housing this equipment.
For systems that operate near ambient pressure and retain gases on charcoal adsorbers.
these criteria 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 System 3.1 The solid radwaste system consists of slurry waste collection and settling tanks, spent resin stor-age tanks, phase separators, and components and subsystems used to solidify radwastes prior to offsite shipment.
The solid radwaste handling and treatment system should meet the following criteria: " For a RWR this includes the system provided for treatment of normal offgas releases from the main condenser vacuum sys-tem beginning at the point of discharge from the condenser air removal equipment;
for a PWR this includes the system provided for the treatment of gases stripped front the primary coolant.t. I3. 1 The system should be designed and tested t) the requirements set forth in the codes and stand-ards listed in Table I supplemented by the provisions noted in 3.1.2 and in regulatory position 4 of this guide.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 the ASME Boiler and Pressure Vessel Code- except that tualleable.
wrought. or cast iron materials and plastic pipe 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 material specifications.
such ats those contained in the codes referenced 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 be designed to the seismic criteria given in regulatory position 5 of this guide to a heighl sufficient to conl-cain the maximum liquid inventory expected to be in the 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 position 5 of this guide.4. Additional Design, Construction, and Testing Criteria In addition to the requirements inherent in the codes and standards listed in Table I, the following criteria, as a minimum, should be implemented for components and systems considered in this guide: 4.1 The quality assurance provisions described in regulatory position 6 of this guide should be applied.4.2 Process piping systems include the first root valve on sample and instrument lines. Pressure-retaining components of process syslems should use welded 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 which threads provide the only seal should not be used ex-cept for instrumentation connections where welded connections are not suitable.
Process lines should not be less than 3/4 inch (nominal I.D.). Screwed con-nections backed up by seil welding, mechanical joints, or socket welding may be used on lines 3/4 inch or larger but less than 2-1/2 inches (nominal I.D.). For lines 2-1/2 inches and above, pipe welds should be of the butt-joint type. Nonconsumable backing rings should not be used in lines carrying re-sins or other particulate material.
All welding con-stituting the pressure boundary of pressure-retaining
0 1.143-3 components should be performed in accordance with ASME Boiler and Pressure Vessel Code Section IX.-2 4.3 Piping systems should be hydrostatically tested in (heir entirety except at atmospheric tank connec-tions where no isolation valves exist. Pressure testing should 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 less than 75 psig. The test pressure should be held for a minimum of 30 minutes with no leakage indicated.
4.4 Testing provisions should be incorporated to enable periodic evaluation of the operability and re-quired functional performance of active components of the system.5. Seismic Design for Radwaste Management Systems and Structures Housing Radwaste Management Systems 5.1 Gaseous Radwaste Management Systems'5. 1.1 For the evaluation of the gaseous radwaste system described in regulatory position 2.1.3. a simplified seismic analysis procedure to determine seismic loads may be used. The simplified procedure consists of considering the system as a single-degree-of-freedom system and picking up a seismic response value from applicable flnor response spectra, after the fundamental frequct-c.
of the sys-tem. is determined.
The floor response spectra should be obtained analytically (regulatory position 5.2)from the application of the Regulatory Guide 1.60 de-sign response spectra normalized to the maximum ground acceleration for the operating basis earth-quake (OBE), as established in the application, at the foundation of the building housing the gaseous rad-waste system. More detailed guidance can be found in Regulatory Guide 1.122, "Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components." 5. 1.2 The allowable stresses to be used for steel system support elements should be those given in.Specification for the Design, Fabrication and Erec-tion of Structural Steel fot Buildings," adopted in February 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 concrete structures, use of ACI 349-761 as endorsed in Regu-latory Guide 1.142, "Safety-Related Concrete Struc-tures for Nuclear Power Plants (Other Than Reactor Vessels 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 Steel Construction, Inc., 101 Park Avenue, New York, New York t017.5.1.3 The construction and inspection require-ments for the support elements should comply with those stipulated in AISC or ACI Codes as appro-priate.5.2 Buildings Flousing Radwaste Systems 5.2.1 Input motion at the foundation of the building housing the radwaste systems should be de-fined. This motion should bedefined by normalizing the Regulator)y Guide 1.60 spectra to the maximum ground acceleration selected for the plant OBE. A simplified analysis should be performed to determine appropriate seismic loads and floor response spectra pertinent to the location of the system, i.e., an analy-sis of the building by a several-degrees-of-freedom mathematical model and the use of an approximate method to generate the floor response spectra for radwaste systems and the seismic loads for the build-ings. No time history analysis is required.5.2.2 The simplified method for determining seismic loads for the building consists of (a) calculat-ing the first several modal frequencies and participa- tion factors for the building. (b) determining modal seismic loads using regulatory position 5.2.1 input spectra, and (c) combining modal seismic loads in one 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, simplified methods that give approximate floor response spectra without need for performing a time history analysis may be used.5.2.4 The load factors and load combinations to be used for the building should be those given in ACI 349-76 1 as endorsed in Regulatory Guide 1. 142.The allowable stresses for steel components should be those given in the AISC Manual. (See regulatory position 5.1.2.)5.2.5 The construction and inspection require-ments for the building elements should comply with those 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 the maximum ground acceleration selected for the plant OBE.5.3 In lieu of the criteria and procedures defined above, optional shield structures constructed around and supporting the radwaste systems may be erected to 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, Michigan 48219..1 0 4 I 1.143-4 I.9 procedures described in. regulatory position 5.2 need only be applied to the shield structures while treating the rest of the housing structures as non-seismic Category I.6. Quality Assurance for Radwaste Management Systenms Since the impact of these systems on safety is lim-ited, a quality assurance program corresponding to the full extent of Appendix B to 10 CFR Part 50 is not required.
However. to ensure that systems will perform their intended function.
a quality assurance program 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 is reprinted by permission of the American Nuclear So-ciety from ANSI N199-1976, "Liquid Radioactive Waste Processing System for Pressurized Water Reactor Plants...s
"4.2.3 Quality Control. The design, procure-ment. fabrication and construction activities shall conform to the quality control provisions of the codes and standards specified herein. In addition, or where not 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 Document Control-Design and procurement documents shall be independently verified for cotiformance to the re-quirements of this standard by individual(s)
within the design organization who are not the originators of the document.
Changes to these documents shall be verified or controlled to maintain conformance to this standard."(2) Control of Purchased Material.
Equip-ment and Services-Measures to ensure that suppliers of material, equipment and construction services are capable 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 equipment to prevent damage. deterioration or reduction of cleanness.
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 code 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-ify conformance with the documented instructions.
procedures, and drawings for accomplishing the ac-tivity. This shall include the visual inspection of components prior to installation for confornmance with procurement documents and the visual inspection of items and systems following installation, cleanness and passivation (where applied)."'(2) Inspection.
Test and Operating Status.Measures should be established to provide for the identification of items which have satisfactorily passed required inspections and tests.-(3) Identification and Corrective Action for Items 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 material and equipment.
Sufficient records should be maintained to furnish evidence that the measures identified above are being implemented.
The records should include results of reviews and inspections and should be identifiable and retrievable.
D. IMPLEMENTATION
The purpose of this section is to provide informa-tion to applicants regarding the NRC staff"s plans for using 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 for complying with specified portions of the Commis-sion's regulations.
the method described herein is being and will continue to be used in evaluation of submittals in connection with applications for operat-ing licenses, construction permits, or amendments thereto until this guide is revised as a result of suggestions from the public or additional staff review.0 1.143-5 TABLE 1 EQUIPMENT
CODES FIQUI PMENT CODES Detsigni and'a hr ica Iio)n"'elder Qualification M~aterials'
and Procedures Inspection and Testing Prcssutie Vesisel 0-I ni VSphri 'Ianks Ili ping.- and V'alve.-ASMI- CodeVIII\ I)v I;-\SME'Section III. Clam, 3. kr API 6501. or A.W\VWA 1I) -I W..AS.ME' Scctioh III.Class 3. or API 620'.\S.IE Code Section VIII, Div. I AN.I TE.MA ANSI t131.1 ASME Code Section II ASME Code: Section II ASMI" code: Section II ASMNE Code Section II AS'IM an ASME Code Section II AS.IE Code Section II or Manufacturers Standard ASME Code Section IX ASNIIE Co'de Section IX A.SMIE Code Section IX ASNII: Code Section IX AS.ME Co'de Section IX ASNIF Code Section IX (a.s required)ASNME Code SectionVIll.
D)iv. I AS\IE Code, sect ion Ill.CiGas 3. or API 650.or AWWA D-I1002 ASME Codc' Section Ill.Cklss 3. or API 6202 ASNSMI F Code Seclton VIII. Div. I ANSI 1331. 1 ASMEN Section Ill Clans 3: or Hydraulic Insltimue Stantjdard
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