Regulatory Guide 1.143: Difference between revisions

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{{Adams
{{Adams
| number = ML013100305
| number = ML13350A262
| issue date = 11/30/2001
| issue date = 07/31/1978
| title = (Revision 2), Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants
| title = Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants, for Comment
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/RES
Line 9: Line 9:
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Graves H L (301)415-5880
| contact person =  
| case reference number = DG-1100
| document report number = RG-1.143
| document report number = RG-1.143, Revision 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 28
| page count = 6
}}
}}
{{#Wiki_filter:Regulatory guides are issued to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific partsof the NRC's  regulations, techniques used by the staff in evaluating specific problems or postulated accidents, and data needed by the NRC staff in its review ofapplications for permits and licenses.  Regulatory guides are not substitutes for regulations, and compliance with them is not required.  Methods and solutions differentfrom those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by theCommission.This guide was issued after consideration of comments received from the public.  Comments and suggestions for improvements in these guides are encouragedat all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience.  Written comments may be submittedto the Rules and Directives Branch, ADM, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.  Regulatory guides are issued in ten broad divisions:  1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting;5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review; and 10, General. Single copies of regulatory guides (which may be reproduced) may be obtained free of charge by writing the Distribution Services Section, U.S. Nuclear RegulatoryCommission, Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to DISTRIBUTION@NRC.GOV.  Electronic copies of this guide and other recentlyissued guides are available on the internet at NRC's home page at <
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
WWW.NRC.GOV> in the Reference Library under Regulatory Guides.  This guide is also in theElectronic Reading Room through NRC's home page, Accession Number ML013100305.U.S. NUCLEAR REGULATORY COMMISSION               Revision 2November 2001 REGULATORY
COMMISSION
GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 1.143(Draft was issued as DG-1100)DESIGN GUIDANCE FOR RADIOACTIVE WASTE MANAGEMENTSYSTEMS, STRUCTURES, AND COMPONENTS INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER PLANTS
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==
==A. INTRODUCTION==
This regulatory guide has been revised to provide guidance to licensees and applicants on methodsacceptable to the staff for complying with the NRC's regulations in the design, construction, installation, and testing the structures, systems, and components of radioactive waste management facilities in light- water-reactor nuclear power plants. In 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," &sect; 50.34,"Contents of Applications; Technical Information," requires that each application for a construction permit include a preliminary safety analysis report. Part of the information required is related to quality assurance and the preliminary design of the facility, including, among other things, the principal design criteria for the facility. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 establishes overall quality assurance requirements for structures, systems, and components important to safety.  Appendix A, ''General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 establishes minimum requirements for the principal design criteria for light-water-cooled nuclear power plants.Criterion 1, "Quality Standards and Records,'' of Appendix A requires that structures, systems, andcomponents important to safety be designed, fabricated, erected, and tested to quality standards  
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.
1 Adams et al, "Re-evaluation of Regulatory Guidance Provided in  Regulatory Guides 1.142 and 1.142," NUREG/CR-5733,August 1999.  Copies are available at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC
20402-9328 (telephone (202)512-1800); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161; (telephone (703)487-4650; <http://www.ntis.gov/ordernow>.  Copies are available for inspectionor copying for a fee from the NRC Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDR's mailing address is USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or (800)397-4209; fax (301)415-3548; email is PDR@NRC.GOV.


1.143-2commensurate with the importance to safety of the safety function to be performed and that aquality assurance program be established and implemented in order to provide adequate assurance that these structures, systems, and components will satisfactorily perform their safety function.  Criterion 2, "Design Bases for Protection Against Natural Phenomena," of Appendix Arequires, among other things, that structures, systems, and components important to safety be designed to withstand the effects of natural phenomena such as earthquakes, tornados, or flooding without loss of capability to perform their safety functions.  The design bases for these structures, systems, and components are to reflect the importance of the safety functions 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&#xb6;-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.


Appendix S, "Earthquake Engineering Criteria for Nuclear Power Plants," of 10 CFR Part 50
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.
states general design requirements for the implementation of General Design Criterion 2.


Criterion 60, "Control of Releases of Radioactive Materials to the Environment,'' of Appendix A
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.
requires that the nuclear power unit design include means to suitably control the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid waste produced during normal reactor operation, including anticipated operational occurrences.  The release of radioactive materials from external man-induced events and design basis accidents must


also be controlled.This regulatory guide is being revised to provide design guidance acceptable to the NRCstaff in regard to natural phenomena hazards, internal and external man-induced hazards, and quality group classification and quality assurance provisions for radioactive waste management systems, structures, and components.
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.


1  Further, it describes provisions for mitigating design basisaccidents and controlling releases of liquids containing radioactive materials, e.g., spills or tank overflows, from all plant systems outside reactor containment. Licensees and applicants may propose means other than those specified by the provisionsof the Regulatory Position of this guide for meeting applicable regulations.  No new requirements are being imposed by this regulatory guide.  Implementation of this guidance by licensees will be on a strictly voluntary basis.The information collections contained in this regulatory guide are covered by therequirements in 10 CFR Part 50, which were approved by the Office Management and Budget, approval number 3150-0011. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not
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.


required to respond to, the information collection.
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


2 Radioactive waste, as used in this guide, means liquids, gases, or solids that contain radioactive materials that by design oroperating practice will be processed prior to final disposition.
====n. USNRC REGULATORY ====
GUIDES Comment% should be sent to the Secretay of the Co.mmnin.


3Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.
US. Nutii t-q., Regulatory Guides are issued to describe and make available to khe Public method, latory Commission.


4Copies of sections of NUREG 0800 are available by email to DISTRIBUTION@NRC.GOV or by fax to (301)415-2289.
Waihington, D.C. 20555. Attention Docketnrg.


1.143-3
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.


==B. DISCUSSION==
Regulatory Guide: are not slubstitutes for regul-tlions, and compliance with them is not required.
One aspect of nuclear power plant operation is the control and management of liquid,gaseous, and solid radioactive waste
2 (radwaste) generated as a byproduct of nuclear power.  Thepurpose of this guide is to provide information and criteria that will provide reasonable assurance that components and structures used in the radioactive waste management and steam generator blowdown systems are designed, constructed, installed, and tested on a level commensurate with the need to protect the health and safety of the public and plant operating personnel.  It sets forth minimum staff recommendations and is not intended to prohibit the implementation of more rigorous design considerations, codes, standards, or quality assurance measures.ANSI/ANS Standards 55.1-1992, "Solid Radioactive Waste Processing System for LightWater Cooled Reactor Plants,"
3 55.4-1993, "Gaseous Radioactive Waste Processing Systems forLight Water Plants,"
3 and 55.6-1993, "Liquid Radioactive Waste Processing Systems for LightWater Reactor Plants,"
3 have been reviewed for applicability to this guide.  These ANSI/ANSStandards provide a wider range of guidance than that provided in Sections 11.2, "Liquid Waste Management System"; 11.3, "Gaseous Waste Management System"; and 11.4, "Solid Waste Management System," of Chapter 11, "Radioactive Waste Management," of NUREG-0800,
"Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants."
4  Asappropriate, guidance from the ANSI/ANS standards has been incorporated by reference. For the purposes of this guide, the radwaste systems are considered to begin at the interfacevalves 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 controlled discharge to the environment, at the point of recycle to the primary or secondary water system storage tanks, or at the point of storage of packaged solid


wastes.The steam generator blowdown system begins at, but does not include, the outermostcontainment isolation valve on the blowdown line. It terminates at the point of controlled discharge to the environment, at that point of interface with other liquid systems, or at the point of recycle back to the secondary system. For design purposes, portions of radwaste systems that interface with other systems are considered to be in the system with more rigorous requirements.Except as noted, this guide does not apply to the reactor water cleanup system, thecondensate cleanup system, 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), instrumentation and  
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
5 Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street,New York, NY 10017.
3. Fuels and Materials Facilities
8. Occupational Health of a permit at license by the Commission.


1.143-4sampling systems beyond the first root valve, or the chemical fume hood exhaust systems. Inaddition, this guide does not apply to the main condenser circulating or component cooling water systems, the spent fuel handing and storage systems, or the fuel pool water cleanup system.The design and construction of radioactive waste management and steam generatorblowdown 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 designed to quality standards that enhance system reliability, operability, and availability.  In developing this design guidance, the NRC staff has considered designs and concepts submitted in license applications and resulting operating system histories.  It has also been guided by industry practices and the cost of design features, taking into account the potential impact on the health and safety of operating personnel and the general public.
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.


==C. REGULATORY POSITION==
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.
1.SYSTEMS HANDLING RADIOACTIVE MATERIALS IN LIQUIDS
1.1Liquid Radwaste Treatment SystemThe liquid radwaste treatment system, including the steam generator blowdown system,downstream of the outer-most containment isolation valve should meet the following criteria.


1.1.1The structures, systems, and components (SSCs) of the liquid radwaste treatmentsystem should be designed and tested to requirements set forth in the codes and standards listed in Table 1 of this guide, supplemented by Regulatory Positions 1.1.2 and 1.1.3 of this guide.
evalual ing the need lor an early revision.


1.1.2Materials for pressure-retaining components, excluding HVAC duct and fireprotection piping, should conform to the requirements of the specifications for materials listed in Section II of the ASME Boiler and Pressure Vessel Code, 5 except that malleable, wrought, or cast iron materials and plastic pipe should not be used. Materials should be compatible with the chemical, physical, and radioactive environment of specific applications during normal conditions and anticipated operational occurrences. Manufacturers' material certificates of compliance with
Washlington, D.C. ?M055. Attentiton D..ectot.


material specifications such as those contained in the codes referenced in the materials column of Table 1 may be provided in lieu of certified material test reports.
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.


1.1.3Foundations and walls of structures that house the liquid radwaste system should bedesigned to the natural phenomena and internal and external man-induced hazards criteria described in Regulatory Position 6 of this guide to a height sufficient to contain the maximum liquid inventory expected to be in the building.
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.


1.143-51.2SSCs Outside Containment that Contain Radioactive LiquidsAll SSCs located outside the reactor containment that contain radioactive materials inliquid form should be classified as described in Regulatory Position 5 and designed in accordance with Regulatory Position 6.  In addition, any such component should be designed to prevent uncontrolled releases of radioactive materials caused by spillage in buildings or from outdoor components.  The following design features should be included for such components and should meet the criteria contained in Sections 5.2, 5.3, and 5.4 of ANSI/ANS 55.1-1992.
One aspect of this consideration is ensuring that these systems are de-signed to quality standards that enhance system relia-bility. operability, and availability.


1.2.1.All tanks inside and outside the plant, including the condensate storage tanks,should have provisions to monitor liquid levels.  Designated high-liquid-level conditions should actuate alarms both locally and in the control room.
In development of this design guidance.


1.2.2.All radwaste tanks, overflows, drains, and sample lines should be routed to theliquid radwaste treatment system.  Retention by an intermediate sump or drain tank that is designed for handling radioactive materials and that has provisions for routing to the liquid radwaste system is acceptable.
the NRC staff has considered designs and concepts submitted in license applica-tions and resulting operating system histories.


1.2.3.Indoor radwaste tanks should have curbs or elevated thresholds with floor drainsrouted to the liquid radwaste treatment system. Retention by an intermediate sump or drain tank that is designed for handling radioactive materials and that has provisions for routing to the liquid radwaste system is acceptable.
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.


1.2.4.The design should include provisions to prevent leakage from entering unmonitoredand nonradioactive systems and ductwork in the area.
physical.


1.2.5.Outdoor tanks should have a dike or retention pond capable of preventing runoff inthe event of a tank overflow and should have provisions for sampling collected liquids and routing them to the liquid radwaste treatment system.2.GASEOUS RADWASTE SYSTEMSFor a BWR, the gaseous radwaste system includes the system provided for treatment ofnormal offgas releases from the main condenser vacuum system beginning at the point of discharge from the condenser air removal equipment; for a PWR the gaseous radwaste system includes the system provided for the treatment of gases stripped from the primary coolant.
and radioactive en-vironment of specific applications.


2.1The SSCs of the gaseous radwaste treatment system should be designed and testedto requirements set forth in the codes and standards listed in Table 1 supplemented by Regulatory Positions 2.2 and 2.3 of this guide.
Manufacturers'
material certificates of compliance with material specifications.


2.2Materials for pressure-retaining components, excluding HVAC duct and fireprotection piping, should conform to the requirements of the specifications for materials listed in Section II of the ASME Boiler and Pressure Vessel Code, except that malleable, wrought, or cast
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.


iron materials and plastic pipe should not be used. Materials should be compatible with the
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.
1.143-6chemical, physical, and radioactive environment of specific applications during normal conditionsand anticipated operational occurrences. If the potential for an explosive mixture of hydrogen and oxygen exists, adequate provisions should be made to preclude buildup of explosive mixtures, or the system should be designed to withstand the effects of an explosion. Manufacturers' material certificates of compliance with material specifications such as those contained in the codes referenced in the materials column of Table 1 may be provided in lieu of certified materials test


reports.2.3The portions of the gaseous radwaste treatment system that are intended to store ordelay the release of gaseous radioactive waste, including portions of structures housing these systems, should be classified as described in Regulatory Position 5 and designed in accordance with Regulatory Position 6.3.SOLID RADWASTE SYSTEMThe solid radwaste system consists of slurry waste collection and settling tanks, spent resinstorage tanks, phase separators, and components and subsystems used to dewater or solidify radwastes prior to storage or offsite shipment.
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.


3.1The SSCs of the solid radwaste treatment system should be designed and tested tothe requirements set forth in the codes and standards listed in Table 1 supplemented by Regulatory Positions 3.2 and 3.3 of this guide.
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.


3.2Materials for pressure-retaining components, excluding HVAC duct and fireprotection piping, should conform to the requirements of the specifications for materials listed in Section II of the ASME Boiler and Pressure Vessel Code, except that malleable, wrought, or cast
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.


iron materials and plastic pipe should not be used. Materials should be compatible with the chemical, physical, and radioactive environment of specific applications during normal conditions and anticipated operational occurrences. Manufacturers' material certificates of compliance with
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.


material specifications such as those contained in the codes referenced in the materials column of Table 1 may be provided in lieu of certified materials test reports.
For systems that operate near ambient pressure and retain gases on charcoal adsorbers.


3.3Foundations and adjacent walls of structures that house the solid radwaste systemshould be designed to the natural phenomena and internal and external man-induced hazards guidance given in Regulatory Position 6 of this guide to a height sufficient to contain the maximum liquid inventory expected to be in the building.
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.


3.4 Equipment and components used to collect, process, or store solid radwastes neednot be designed to the seismic guidance in Regulatory Position 6 of this guide.4.ADDITIONAL DESIGN, CONSTRUCTION, AND TESTINGIn addition to the requirements inherent in the codes and standards listed in Table 1, thefollowing, as a minimum, should be applicable to SSCs listed in Regulatory Position 6 of this guide.
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.


1.143-7 4.1Radioactive waste management SSCs should be designed to control leakage andfacilitate access, operation, inspection, testing, and maintenance in order to maintain radiation exposures to operating and maintenance personnel as low as is reasonably achievable. Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," provides guidance that is acceptable to the NRC staff on this subject.
wrought. or cast iron materials and plastic pipe should not be used. Materials shoulh be compalt-ible with the chemical.


4.2The quality assurance provisions described in Regulatory Position 7 of this guide should be applied.
physical, and radioactive en-vironment of specific applications.


4.3Pressure-retaining components of process systems should use welded constructionto the maximum practicable extent.  Process systems include the first root valve on sample and instrument lines.  Flanged joints or suitable rapid-disconnect fittings should be used only where maintenance or operational requirements clearly indicate such construction is preferable.  Screwed connections in which threads provide the only seal should not be used except for instrumentation and cast pump body drain and vent connections where welded connections are not suitable.
NIanufacturers" material certificates of cotmpliarnce with material specifications.


Process lines should not be less than 3/4 inch (nominal). Screwed connections backed up by seal welding, mechanical joints, or socket welding may be used on lines 3/4 inches or larger but less than 2-1/2 inches. For lines 2-1/2 inches and above, pipe welds should be of the butt-joint type.
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.


Nonconsumable backing rings should not be used in lines carrying resins or other particulate material.  All welding constituting the pressure boundary of pressure-retaining components should be performed in accordance with ASME Boiler and Pressure Vessel Code Section IX.
Screwed connections in which threads provide the only seal should not be used ex-cept for instrumentation connections where welded connections are not suitable.


4.4Piping systems should be hydrostatically tested in their entirety except (1) atatmospheric tanks where no isolation valves exist, (2) when such testing would damage equipment, and (3) when such testing could seriously interfere with other system or component testing. For (2) and (3), pneumatic testing should be performed.  Pressure testing should be performed on as large a portion of the in-place systems as practicable. Testing of piping systems should be performed in accordance with applicable ASME or ANSI codes listed in Table 1.
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.


4.5Inspection and testing provisions should be incorporated to enable periodicevaluation of the operability and required functional performance of active components of the system.5.CLASSIFICATION OF RADWASTE SYSTEMS FOR DESIG
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.


==N. PURPOSE==
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.
SThere are three safety classes, or classifications, for radwaste management facilities:  RW-IIa (High Hazard), RW-IIb (Hazardous), and RW-IIc (Non-Safety).
1  RW-IIa is the most stringentclass and RW-IIc is the least stringent.  These classifications were developed primarily for natural phenomena and man-induced hazard design.  The radiological release criteria (500 millirem at the unprotected area boundary and 5 rem to facility personnel within the protected boundary) was selected to be consistent with the criteria of 10 CFR Part 20, "Standards for Protection Against Radiation." This safety classification is applied to SSCs as follows.


5.1For a given structure housing radwaste processing systems or components, if thetotal design basis unmitigated radiological release (considering the maximum inventory) at the
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.
1.143-8boundary of the unprotected area is greater than 500 millirem per year or the maximumunmitigated exposure to site personnel within the protected area is greater than 5 rem per year, the external structures are classified as RW-IIa.


5.2For a given structure housing radwaste processing systems or components, if thetotal design basis unmitigated radiological release (considering the maximum inventory) at the boundary of the unprotected area is less than 500 millirem per year and the maximum unmitigated exposure to site personnel within the protected area is less than 5 rem per year, the external structure is classified as RWE-IIb.5.3Any systems or components in a RW-IIa facility (see Regulatory Position 5.1) thatstore, process, or handle radioactive waste in excess of the A
of the sys-tem. is determined.
1 quantities given in Appendix A,"Determination of A
1 and A 2," to 10 CFR Part 71, "Packaging and Transportation of RadioactiveMaterial," are classified as RW-IIa.  These systems or components that process radioactive waste in excess of the A
2 quantities but less than the A
1 quantities given in Appendix A to 10 CFR Part71 are classified as RW-IIb.  All other components are classified as RW-IIc.  This classification may be modified for specific radwaste components.


5.4Any systems or components in a RW-IIb structure (see Regulatory Position 5.2)that are used to store or process specified radioactive waste in excess of the A
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.
1 quantities given inAppendix A to 10 CFR Part 71 are classified as RW-IIb.  All other systems or components are classified as RW-IIc.The unprotected area boundary mentioned in Regulatory Position 5.1 is shown in Figure 1. A flowchart of the Safety Classification Process is shown in Figure 2. The classifications discussed in Regulatory Positions 5.1 through 5.4 are not intended to apply to radwaste storage facilities if they do not contain any systems or components that exceed the quantities specified in Regulatory Positions 5.1 through 5.4.6.NATURAL PHENOMENA AND MAN-INDUCED HAZARDS DESIGN FORRADWASTE MANAGEMENT SYSTEMS AND STRUCTURES
6.1General Design CriteriaSolid, liquid, and gaseous radwaste SSCs described in Regulatory Positions 1, 2, and 3 fornatural phenomena and internal and external man-induced hazards should be evaluated as put forth


in this position.
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.


6.1.1.The natural phenomena and internal and external man-induced hazards demanddefinitions are as given in Table 2.
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.


6.1.2.The natural phenomena and internal and external man-induced hazards design loadcombinations are as given in Table 3.
However. to ensure that systems will perform their intended function.


1.143-9 6.1.3.The natural phenomena and internal and external man-induced hazards should meetcapacity criteria in Table 4.
a quality assurance program sufficient to ensure that all design. construc-tion. and testing provisions are met should be estab-lished and documented.


6.1.4.The acceptability evaluation should be based on the requirements of the codes andstandards given in Table 1, using the capacity criteria in Table 4.6.2Buildings Housing Radwaste Systems
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
6.2.1Regardless of its safety classification, the foundation and walls up to the spill heightof the building housing the radwaste systems should be designed to the criteria of Tables 1, 2, 3, and 4.For classifications RW-IIb and RW-IIc, all SSCs should be designed at least for seismicbase shear requirements of the Standard Uniform Building Code(UBC), 1997.  The guidance of Volume 2 of the UBC 1997 and American Society of Civil Engineers ASCE 7-95, "Minimum Design Loads for Buildings and Other Structures," should be used as noted in Table 2 of this regulatory guide.
"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.


6.2.2. In lieu of the criteria and procedures referenced in this Regulatory Position 6,optional shield structures constructed around and supporting the radwaste systems may be erected to protect the radwaste systems from the effects of failure of the housing structure.  If this option is adopted, Regulatory Position 6.2.1 need only be applied to the shield structures.7.QUALITY ASSURANCE FOR RADWASTE MANAGEMENT SYSTEMSSince the impact of these systems on safety is limited, the extent of control required byAppendix B to 10 CFR Part 50 is similarly limited.  To ensure that systems will perform their intended functions, a quality assurance program sufficient to ensure that all design, construction, and testing provisions are met should be established and documented.  A quality assurance program acceptable to the NRC staff is presented in ANSI/ANS-55.6-1993, "Liquid Radioactive Waste Processing System for Pressurized Water Reactor Plants."Section 4.3, "Quality Assurance," of ANSI/ANS 55.6-1993 provides quality assuranceguidance that is acceptable to the NRC staff for the system designer and procurer and for the system constructor.  The design, procurement, fabrication, and construction activities should conform to the quality control provisions of the codes and standards specified in Table 1 of this guide.  In addition, or when not covered by the referenced codes and standards, sufficient records should be maintained to furnish evidence that quality assurance measures are being implemented.
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.


The records should include results of reviews and inspections and should be identifiable and retrievable.
Changes to these documents shall be verified or controlled to maintain conformance to this standard."(2) Control of Purchased Material.


1.143-10
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.


==D. IMPLEMENTATION==
"(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.
The purpose of this section is to provide information to licensees and applicants regardingthe NRC staff's plans for using this regulatory guide.  Except in those cases in which the applicant proposes an acceptable alternative method forcomplying with the specified portions of the NRC's regulations, the method described in this guide reflecting public comments will be used in the evaluation of an applicant's design, construction, installation, and testing of radioactive waste management facilities, and in the evaluation of structures, systems, and components in light-water-cooled nuclear power plants.


Current licensees may, at their option, comply with the guidance in this regulatory guide.
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.


Table 1 -  Codes and Standards for the Design of SSC in Radwaste Facilities
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.
1  ComponentDesign and ConstructionMaterialsWelding Inspection and TestingStructures - ConcreteACI-318 or ACI 3492,3,4ACI-318 or ACI 349ACI-318 or ACI 349ACI-318 or ACI 349Structures-Steel (Hot Rolled)AISC-ASD or AISC LFRD or AISCN-690(S327) 2,4ASTM-A36AWS-D1.1AISC Standards and AWS
StandardsStructures-Steel (Cold Formed)AISI SG-673ASTM-A500AWS-D1.3, D9.1AISC Standards and AWS
StandardsPiping and ValvesANSI/ASME B31.3 5,6ASME-Sec. II
7ASME, Sec. IXANSI/ASME B31.3Atmospheric Tanks API-650ASME Sec. IIASME, Sec. IXAPI-620
Tanks (0-15 psig)API-620ASME Sec. IIASME, Sec. IXAPI-650
Pressure Vessels and Tanks (>15psig)ASME BPVC Div. 1 or Div. 2ASME Sec. IIASME, Sec. IXASME Section VIII, Div. 1 or 2PumpsAPI-610;  API-674;  API-675; ASME BPVC Section VIII, Div. 1 or Div. 2 ASTM A571-
84(1997) or ASME
Sec. IIASME, Sec. IXASME BPVC Code Section III, Class 3
8Heat ExchangersTEMA STD, 8th Edition; ASMEBPVC Section VIII Div. 1 or Div. 2ASTM B359-98 orASME Sec. IIASME, Sec. IXASME Section VIII, Div. 1 or 2HVAC SystemsSMACNA Stds. 6,9ASTM F856-97ASTM C1290-00AWS-D1.1, D1.3, D9.1SMACNA StdsConduit and Cable TraysNEMA TC2-1998NEMA VE1-1998ASTM B633-98,  A123/A123M-01


NEMA TC2, VE1AWS-D1.1, D1.3, D9.1 NEMA TC2-1998,NEMA VE1-1998Fire Protection SystemsNFPA-136,10 ;  NFPA-14ASTM-A795AWS-D1.1, D1.3, D9.1, D10.9NFPA-13Flexible Hoses and HoseConnections for MRWP
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.
11ANSI/ANS-40.37ANSI/ANS-40.37ANSI/ANS-40.37ANSI/ANS-40.37Footnotes for Table 1:1 For a comprehensive lists of codes and standards referenced in Tables 1-4, see Appendix A to this regulatory guide.


2 Applicable to structure enclosing or supporting pressurized gaseous waste or liquid waste systems up to spill height. Also  applicable to solid waste facilityfoundations slab and connected wall or column  sections up to a height of 10 feet.
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.


3 Appropriate load combinations and capacity criteria for component designs are specified in Table 3 of this regulatory guide.4Class RW-IIa Structures are to use ACI-349 and/or AISC N-690(S327) as applicable.
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.


5Class RW-IIa and RW-IIb Piping Systems are to  be designed as category "M" systems.
Sufficient records should be maintained to furnish evidence that the measures identified above are being implemented.


6Classes RW-IIa, RW-IIb, and RW-IIc are discussed in Regulatory Position 5 of this regulatory guide.
The records should include results of reviews and inspections and should be identifiable and retrievable.


7 ASME BPVC Section II required for Pressure Retaining Components.
*


8 ASME Code Stamp, material traceability, and the quality assurance criteria of ASME BPVC, Section III, Div. 1, Article NCA are not required.  Therefore,these components are not classified as ASME Code Class 3.9Class RW-IIa and RW-IIb HVAC systems are to use SMACNA "Seismic Restraint Manual Guides for Mechanical Systems."
==D. IMPLEMENTATION==
10Class RW-IIa and RW-IIb Fire Protection Systems are to be designed to NFPA-13, Section 4-14.4.3.
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.
 
11 Flexible hoses should only be used in conjunction with Moblie Radwaste Processing Systems (MRWP).
1.143-13Table 2 - Natural Phenomena and Internal/External Man-Induced Hazard Design Criteria for Safety ClassificationLoadingClassification RW-IIa(High Hazard)
RW-IIb (Hazardous)
RW-IIc(Non-Safety)EarthquakeOBE or 1/2 SSEASCE 7-95, Category III
1or UBC 97, Category 2
2ASCE 7-95, Category II
1 UBC-97, Category 4
2 WindASCE 7-95, Category III
1ASCE 7-95, Category III
1ASCE 7-95, Category II
1 TornadoANS 2.3 at a Probability of 1 x
10-5 /yr or three-fifths of Criteriain Regulatory Guide 1.76, Table 1. Not RequiredNot Required Tornado Missilefrom SRP Section 3.5A.75  lbs, 3 in. nominaldiameter sch. 40 pipe.
 
Maximum velocity 0.4 x max. wind speed horizontal and 0.28 times max. wind speed vertical direction.
 
3B. Automobile wt. 4000 lbswith frontal area of 20.0 sq.
 
ft. traveling horizontally at
0.2 times maximum wind speed horizontally and 0.14 times maximum wind speed up to a height of 35 ft above grade.4Not RequiredNot Required Flood Regulatory Guide 1.59, one-half of the PMF.
 
5ASCE 7-95ASCE 7-95Precipitation (6)(Rain, Snow)ANS 2.8 at probability of 1 x
10-3/yr or Regulatory Guide1.59, one-half precipitation specific for the PMF.
 
5ASCE 7-95, Category III
1ASCE 7-95, Category II
1Accidental Explosion Fixed FacilityTo be evaluated on a case-by-case basis, plant-specific definition.Not RequiredNot RequiredAccidental Explosion Transportation VehicleSee Regulatory Guide 1.91.Not RequiredNot RequiredMalevolent  VehicleAssaultRegulatory Guide 5.68 or plant-specific definition.Not RequiredNot RequiredSmall Aircraft CrashPlant-specific definitionNot Required Not RequiredFootnotes for Table 2:1 ASCE 7-95, Table 1-1.4 Impact-type missile.2 UBC-97, Table 16-k.5PMF = Probable Maximum Flood.
 
3 Penetrating-type missile.4 Resistance to lightening strike should also be included in the design.
 
1.143-14Table 3 - Design Load CombinationsSystem, Structure,Component (SSC)Service  LevelsSSC Safety Class RW - IIaRW- IIbRW- IIcExternal Structures(Concrete, Steel, Component Support Structures
1)External Conduits andCable TraysA (Normal)D + L + T
oD + L + T oD + L + T oB (Severe; Upset)D + L + T
oD + L + T o + E oD + L + T o + W + RD + L + T o + FD + L + TbD + L + T o + E'oD + L + T o + W + RD + L + T o + FD + L + TbD + L + T o + E"oD + L + T o + W + RD + L + T o + FD  (Abnormal Extreme;Faulted)D + L + T o + W tD + L + T o + V mD + L + T o + A cD + L + T a + A DD + L + T a + ANot requiredNot requiredInternal Structures(Concrete, Steel Component Support Structures
1)Internal Conduit and CableTraysA  (Normal)D + L + T
oD + L + T oD + L + T oB  (Severe, Upset)D + L + T
bD + L + T o + E oD + L + T o + FD + L + T bD + L + T o + E oD + L + T o + FD + L + T bD + L + T o + E oD + L + T o + FD  (Abnormal Extreme;Faulted)D + L + T a + A DD + L + T a + AN/RN/RPressure RetainingComponents
2 (Piping,Valves, Pressure Vessels, Atmosphere, Tanks, 0-15 psig Tanks, Pumps Heat Exchangers)
HVAC Systems Fire Protection SystemsA (Normal)P
d + D + D m T o P d + D + D M T o P d + D + D m T oB (Severe, Upset)P
o + D + D m + E o P o + D + D m + W + RP + D + D m + F T b P o + D + D m + E o P o + D + D m + W + RP + D + D m + F T b P o + D + D m + E o P o + D + D m + W + RP + D + D m + F T bD (Abnormal, Extreme Faulted)P + D + D m + W t P o + D + D m + Y m P o + D + D m + A c P a + D + D m + A D P a + D + D m + A N/RN/RNomenclature
:D=Dead LoadsW
t=Tornado Loads Including Missile EffectsL=Live loadsV
m=Malevolent Vehicle Assault Loads T o=Normal Operating Thermal Expansion LoadsA
c=Aircraft Crash Loads T b=Upset Thermal Expansion LoadsA
D=Design Basis Accident Loads T a=Accident Thermal LoadsA=Other Accident Loads E o=OBE or 1/2 SSE Seismic LoadsP
d=Design Pressure E'o=Seismic Loads per Table 2  For RW-IIb ComponentsP
b=Maximum Upset Pressure E"o=Seismic Loads per Table 2 For RW-IIc ComponentsP
o=Normal Operating PressureW=Wind Load P
a=Applicable Accident PressureR=Precipitation Loads (Rain, Snow)D
M=Design Mechanical LoadsF=Flood LoadingsFootnotes:1 Component support structures include supporting elements for piping, tanks, vessels pumps, heat exchangers, conduits, cabletrays, HVAC systems, fire protection systems, etc.2 For most pressure-retaining components, primary and secondary stresses are evaluated separately to separate criteria.  Thedesign code of record is the controlling document in the establishment of the primary and secondary stress combination and evaluation methods.
 
1.143-15Table 4 - SSC Design Capacity CriteriaCode or StandardServiceLevelCapacity CriteriaRW-IIaRW-IIbRW-IIcACI-349A, B, DLoad Factors and CapacityCriteria per ACI-349 as modified by Regulatory Guide 1.142N/AN/AACI-318A, B, DLoad Factors and capacity criteriaper ACI-349 as modified by Regulatory Guide 1.142.  All other design per ACI-318 criteriaLoad factors and capacitycriteria per ACI-349 as modified by Regulatory Guide 1.142.  All other design per ACI-318 criteria.Load factors and capacitycriteria per ACI-349 as modified by Guide 1.142.
 
All other design per ACI-
318 criteria.AISC-N690ACapacity criteria Table Q 1.5.7.1for normal loads.Capacity criteria Table Q1.5.7.1 for normal loads.Capacity criteria Table Q1.5.7.1 for normal loadsBCapacity criteria 1.33 times thatfor Level A loadsCapacity criteria 1.33times that for Level A
loadsCapacity criteria 1.33times that for Level A
loadsDCapacity criteria per TableQ.1.5.7.1 for Abnormal Extreme LoadsN/RN/RAISC-ASDACapacity Criteria per"Specification for Structural Steel Buildings Allowable Stress Design and Plastic Design, Part
5,"chapters A-MCapacity Criteria per"Specification for Structural Steel Buildings Allowable Stress Design and Plastic Design, Part
5,"chapters A-MCapacity Criteria per"Specification for Structural Steel Buildings Allowable Stress Design and Plastic Design, Part
5,"chapters A-MBCapacity Criteria 1.33 timesthat for Level A loads.Capacity Criteria 1.33times that for level A
loads.Capacity Criteria 1.33times that for level A
loads.DCapacity Criteria per"Specification for Structural Steel Buildings Allowable Stress Design and Plastic Design, Part 5,"chapters A
 
and NN/RN/R
1.143-16Table 4 - SSC Design Capacity Criteria (continued)Code or StandardServiceLevelCapacity CriteriaRW-IIaRW-IIbRW-IIcAISC LRFDA,B,DLoad factors and capacitiesper LRFD specifications for structural steel buildings.Not requiredNot requiredAISI CFSDMACapacity criteria per"Specification for the Design of Cold Formed Steel Structural Members"Capacity criteria per"Specification for the Design of Cold Formed Steel Structural Members"Capacity criteria per"Specification for the Design of Cold Formed Steel Structural Members"BCapacity criteria 1.33 timesLevel ACapacity criteria 1.33times Level ACapacity criteria 1.33times Level ADCapacity criteria 1.6 timesLevel ANot requiredNot requiredANSI/ASME B31.3AB31.3 Design Load CapacitiesB31.3 Design Load CapacitiesB31.3 Design Load CapacitiesBB31.3 Occasional Load CapacitiesB31.3 Occasional Load CapacitiesB31.3 Occasional Load CapacitiesD1.8 Times B31.3 OccasionalLoad CapacitiesNot requiredNot requiredASME BPVC,Section VIII, Div. 1 or Div. 2 AASME  BPVC, Section VIII,Div. 1 or Div. 2 Design
 
Capacities ASME  BPVC, SectionVIII, Div. 1 or Div. 2 Design Capacities ASME  BPVC, SectionVIII, Div. 1 or Div. 2 Design Capacities BCapacity criteria 1.2 TimesLevel A criteriaCapacity criteria 1.2Times Level A criteriaCapacity criteria 1.2Times Level A criteriaDCapacity criteria 1.8 timesLevel A criteriaNot requiredNot requiredSMACNA Stds.(1)ASMACNA Design CriteriaSMACNA Design CriteriaSMACNA Design CriteriaBSMACNA Design CriteriaSMACNA Design CriteriaSMACNA Design Criteria D1.  Duct support members tomeet capacity criteria for AISI
SG-673 or AISC-ASD for Level D Loads.
 
2.  Ducting stresses to be less than the material yield stress and limited to 2/3 critical buckling. Not requiredNot requiredNFPA-13 1ANFPA Design CriteriaNFPA Design CriteriaNFPA Design Criteria Table 4 - SSC Design Capacity Criteria (continued)Code or StandardServiceLevelCapacity CriteriaRW-IIaRW-IIbRW-IIc
1.143-17BNFPA Design Criteria forEarthquake and Wind LoadsNFPA Design Criteriafor Earthquake and Wind LoadsNFPA Design Criteriafor Earthquake and Wind LoadsD3.  Support members to meetcapacity criteria for AISI SG-
673 or AISC-ASD for Level D Loads
4.  Piping Stresses to meet the B31.3 Level D Capacity
 
CriteriaN/RN/RANSI/NEMA STDS(Cable Trays/Conduit)AANSI/NEMA Design Criteriafor Normal LoadsANSI/NEMA DesignCriteria for Normal LoadsANSI/NEMA DesignCriteria for Normal LoadsBANSI/NEMA Design Criteriafor Wind and Seismic LoadsANSI/NEMA DesignCriteria for Wind and Seismic LoadsANSI/NEMA DesignCriteria for Wind and Seismic LoadsD5.  Support members to meetcapacity criteria for AISI-
CFSDM or AISC-ASD for Level D Load
6.  Trays and members to meet the capacity criteria for AISI-CFSDM for Level D
LoadsNot requiredNot requiredPumps(API Series Stds)AFor Design Criteria, API 610, API 674, API 675For Design Criteria, API 610, API 674, API
 
675For Design Criteria, API 610, API 674, API
 
675BASME QME-1 1997ASME QME-1 1997ASME QME-1 1997 DASME QME-1 1997Not requiredNot requiredTanksAAPI-620, API-650API-620, API-650API-620, API-650BCapacity Criteria per ASME-BPVC - Section III, NC-3800,
NC-3900 for Level B loads.
 
All other Design per API
 
Criteria.Capacity Criteria perASME-BPVC -
Section III, NC-3800,
NC-3900 for Level B
 
loads.    All other Design per API
 
Criteria.Capacity Criteria perASME-BPVC - Section III, NC-3800, NC-3900
for Level B loads.  All other Design per API
 
Criteria.
 
Table 4 - SSC Design Capacity Criteria (continued)Code or StandardServiceLevelCapacity CriteriaRW-IIaRW-IIbRW-IIc
1.143-18DCapacity Criteria per ASME-BPVC - Section III, NC-3800,
NC-3900 Level D Loads.  All other Design per API Criteria.Not requiredNot requiredFootnotes for Table 4:1  For Level A and B Loads, the Design Criteria is primarily a "design by rule" approach versus a specific analysis criteria.
 
1.143-19                                                    Site Boundary or                                                    Boundary of the Owner Controlled            (Unprotected) Area Access Control
 
Radwaste Facility                        Protected Area                                      Boundary                                                      Unprotected (Secured Area)                                               
  AreaFigure 1 - Informational Schematic Describing Protected and Unprotected Areas Admin Bldg
1.143-20Is theUnmitigated Release@ the Protected Area Boundary > 500mrem or Unmitigated ExposureFor Site PersonnelInside the Protected Area > 5 rem?ClassifyOverall Facilityas RW IIaClassifyOverall Facilityas RW IIbDoes the SubjectSSC Contain RadioacitiveQuantites> A1 ?Classify SSCas RW IIaDoes the SubjectSSC Contain RadioacitiveQuantites> A2 ?Classify SSCas RW IIbClassify SSCas RW IIcDoes the SubjectSSC ContainRadioacitiveQuantites> A1 ?Classify SSCas RW IIbClassify SSCas RW IIcYES NOYESNOYESNOYESNOEvaluate SSCin the FacilityEvaluate SSCin the FacilityFigure 2 - Flowchart of Safety Classification ProcessAppendix A
1.143-21INDUSTRY CODES AND STANDARDSAmerican Concrete Institute, ACI-318, "Building Code Requirements for Reinforced Concrete"(ACI 318-89, Revised 1999), 1999.American Concrete Institute, ACI-349, "Code Requirements for Nuclear Safety RelatedConcrete Structures," 1997.American Institute of Steel Construction, N690 (S327), "Nuclear Facilities, Steel Safety-RelatedStructures For Design and Fabrication," 1984.American Institute of Steel Construction, "Manual of Steel Construction Load and ResistanceFactor Design," Volumes I and II, 2 nd Edition, 1994.American Institute of Steel Construction, "Specifications for Structural Steel Buildings, Manual of Steel Construction," 2nd Edition, 1995.American Institute of Steel Construction, "Specifications for Structural Steel Buildings,Allowable Stress Design and Plastic Design, Manual of Steel Construction," 9th Edition, 1993.American Iron and Steel Institute, SG-673,  "Specification for the Design of Cold-Formed SteelStructural Members," August 1986 with December 1989 Addendum.American Nuclear Society, "Standard for Estimating Tornado and Extreme Wind Characteristicsat Nuclear Power Sites, ANSI/ANS 2.3-1983.American Nuclear Society, "Determining Design Basis Flooding at Power Reactor Sites,ANSI/ANS 2.8-1992.American Nuclear Society, "Mobile Radioactive Waste Processing Systems,"  ANSI/ANS 40.37-
1993.American Nuclear Society, "Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants," ANSI/ANS-55.1-1992.American Nuclear Society, "Gaseous Radioactive Waste Processing Systems for Light WaterReactor Plants," ANSI/ANS-55.4-1993.American Nuclear Society, "Liquid Radioactive Waste Processing System for Light WaterReactor Plants,"  ANSI/ANS 55.6-1993.American Petroleum Institute, 610, "Centrifugal Pumps for Petroleum, Heavy Duty Chemical,and Gas Industry Services," 1995.
 
1.143-22American Petroleum Institute, 620, "Design and Construction of Large, Welded, Low-PressureStorage Tanks, 1990.American Petroleum Institute, 650, "Welded Steel Tanks for Oil Storage," 1998.
 
American Petroleum Institute, 674, "Positive Displacement Pumps-Reciprocating," 1995.
 
American Petroleum Institute, 675, "Positive Displacement Pumps-Controlled Volume," 1994.
 
American Society of Civil Engineers, 7-95, "Minimum Design Loads for Buildings and OtherStructures," 1995.American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II,"Material Specification," 1999.American Society of Mechanical Engineers, Boildr and Pressure Vessel Code, Section III,"Rules for Construction of Nuclear Power Plant Components, Division 1, Subsection ND Class
3 Components, July 1998 with July 1999 Addenda.American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section VIII,"Pressure Vessels," 1999.American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section VIII,"Rules for Construction of Pressure Vessel, Division 1," July 1998 with July 1999 Addenda.American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section VIII,"Rules for Construction of Pressure Vessel, Division 2, Alternative Rules," July 1998 with July
 
1999 Addenda.American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section IX,"Welding and Brazing Qualification," 1999. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, B31.3, "ProcessPiping," 1999.American Society of Mechanical Engineers, QME-1-1997, "Qualification of Active MechanicalEquipment Used in Nuclear Power Plants," December 31, 1997.American Society for Testing & Materials, A36-00, "Standard Specification for Carbon Structural Steel," 2000.American Society for Testing & Materials, A123/A123M-01, "Standard Specification for Zinc(Hot-Dip Galvanized) Coatings on Iron and Steel Products," 2001.
 
1.143-23American Society for Testing & Materials, A500-99, "Standard Specification for Cold-FormedWelded and Seamless Carbon Steel Structural Tubing in Rounds and Shapes," 1999.American Society for Testing & Materials, A571-84 (1997, "Standard Specification forAustenitic Ductile Iron Castings for Pressure-Containing Parts Suitable for Low-Temperature
 
Service," 1997.American Society for Testing & Materials, A795-97, "Standard Specification for Black and Hot-Dipped Zinc-Coated Welded and Seamless Steel Pipe for Fire Protection Use," 1997.American Society for Testing & Materials, B359-98, "Standard Specification for Copper andCopper-Alloy Seamless Condenser and Heat Exchanger Tubes With Integral Fins," 1998.American Society for Testing & Materials, B633-98, "Standard Specification forElectrodeposited Coatings of Zinc on Iron and Steel," 1998.American Society for Testing & Materials, C1290-00, "Standard Specification for FlexibleFibrous Glass Blanket Insulation Used to Externally Insulate HVAC Ducts," 2000.American Society for Testing & Materials, F856-97, "Standard Practice for MechanicalSymbols, Shipboard Heating, Ventilation, and Air Conditioning (HVAC)," 1997.American Welding Society, D1.1, "Structural Welding Code-Steel," 17 th Edition, 2000.American Welding Society, D1.3, "Structural Welding Code-Sheet Steel," 1998.
 
American Welding Society, D9.1, "Sheet Metal Welding Code," 1990.
 
American Welding Society, D10.9, "Specification for Qualification of Welding Procedures andWelders for Piping and Tubing," 1980.International Conference of Building Officials, "Uniform Building Code," 1997.
 
National Electrical Manufacturers Association, Publication Number TC2, "Electrical PolyvinylChloride(PVC) Tubing and Conduit," 1998.
 
National Electrical Manufacturers Association, Publication Number VE1, "Metal Cable TraySystems," 1996.National Fire Protection Association, NFPA 13, "Installation of Sprinkler Systems," 1999.
 
National Fire Protection Association, NFPA 14, "Standard for the Installation of Standpipe FireProtection, Private Hydrant, and Hose Systems," 2000.
 
Sheet Metal and Air Conditioners Contractor National Association, "Seismic Restraint ManualGuides for Mechanical Systems," 2 nd Edition, 1998.
 
1.143-24Standard Uniform Building Code, International Conference of Building Officials, 1997.Tubular Exchanger Manufacturers Association, "Standards of the Tubular ExchangerManufacturers Association, Eighth Edition," 2000.The Codes and Standards are available from:  American Concrete Institute (ACI), Box 19150, Redford Station, Detroit, MI 48219.
 
American Institute of Steel Construction (AISC), One E. Wacker Drive, Suite 3100, Chicago, IL
60601-2001.American Iron and Steel Institute (AISI),1101 17 th Street, NW, Washington, DC 20036.American Nuclear Society (ANS), 555 N. Kensington Avenue, La Grange Park, IL 60525.
 
American Petroleum Institute (API), 1220 L Street, NW, Washington, DC 20005.
 
American Society of Mechanical Engineers (ASME), 345 East 47 th Street, New York, NY 10017.American Society for Testing & Materials (ASTM), 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959. American Welding Society (AWS), 550 NW LeJeune Road, Miami, FL 33126.
 
International Conference of Building Officials, 5360 Workman Mill Road, Whittier, CA  90601-2798.  (www.icbo.org)
National Electrical Manufacturers Association (NEMA), 1300 N. 17 th Street, Rosslyn, VA 22209.National Fire Protection Association (NFPA), Inc., Battery March Park, Quincy, MA 02269.
 
Sheet Metal and Air Conditioners Contractor National Association (SMACNA), 4201 LafayetteCenter Drive, Chantilly, VA 20153-1230. Tubular Exchanger Manufacturers Association (TEMA), 25 N. Broadway, Tarrytown, NY 10591.
 
1.143-25REGULATORY ANALYSIS1. STATEMENT OF PROBLEMRevision 1 of Regulatory Guide 1.143, "Design Guidance for Radioactive WasteManagement Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants," was issued in October 1979.  This guide provided design guidance acceptable to the NRC
staff related to seismic and quality group classification and quality assurance provisions for radioactive waste management structures, systems, 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 containment.  Regulatory Guide 1.143 encompassed the design of buildings, structures, systems, and components and referred to several design and construction codes and standards, such as American National Standards Institute (ANSI)
N197-1976, ANSI N199-1976, American Nuclear Society (ANS) ANS 55.1-1979, ANS 55.4-1979, American Concrete Institute ACI-318-1977, and  American Institute of Steel Construction AISC-
 
1969. These references are now obsolete or have been superseded by newer ANSI and ANSradioactive waste facility design standards.  ANS has since issued  ANS-55.1-92, ANS-55.4-93, and ANS-55.6-93, which are the industry consensus standards currently applicable to the overall design of radioactive waste facilities.  In addition, several other referenced codes such as "Building Code and Commentary," ACI-318-77; or "Specification for the Design, Fabrication and Erection of Structural Steel for Buildings," AISC-1969, have been updated and modified since Revision 1 of Regulatory Guide 1.143 was issued.  Also, there has been increased understanding of, and corresponding changes in relation to, radiation exposure and monitoring and quality assurance needs for the design and construction of radioactive waste facilities and the associated systems, structures, and components. The Operating Basis Earthquake (OBE), as was used in Revision 1 of Regulatory Guide1.143 as the design basis, creates further difficulties.  In 1997, the NRC staff revised 10 CFR
100.23 and added Appendix S to 10 CFR Part 50 that essentially state that, if the review level earthquake (OBE) is defined as less than 1/3 of the safe-shutdown earthquake (SSE), no explicit design analysis for the OBE level earthquake will be required.  In other words, the revised criteria have effectively eliminated the OBE as a design basis seismic event.  In recent staff licensing actions, the Standard (Advanced) Reactor Designs used only a SSE event  as the design basis, consistent with the methodology in the recent revision of 10 CFR 100.23 and the addition of Appendix S to 10 CFR Part 50. Thus, Revision 1 of Regulatory Guide 1.143 was almost not usable for standard reactor designs.The staff maintains that recommendations based on the latest editions of the design andconstruction Standards and Codes mentioned above and references to current quality assurance standards and NRC regulations provide a means to achieve better evaluation of radioactive waste management systems, structures, and components installed in light water-cooled nuclear power
 
plants.
 
1.143-262.OBJECTIVEThe objective of the regulatory action is to update NRC guidance on the design,construction, and quality assurance of radioactive waste management systems, structures, and components installed in light-water-cooled nuclear power plants.3.ALTERNATIVES AND CONSEQUENCES OF PROPOSED ACTION3.1Alternative 1 - Do Not Revise Regulatory Guide 1.143If Regulatory Guide 1.143 were not revised, licensees would continue to rely on the currentversion of Regulatory Guide 1.143 with references from the late 1960s and mid-1970s. The staff acknowledges that many licensees who are presently involved in the design of radioactive waste management systems, structures, and components installed in light-water-cooled nuclear power plants, as a matter of practice, already rely on more recent editions of ANSI and ANS radioactive waste facility design standards and ACI and AISC codes.3.2Alternative 2 - Update Regulatory Guide 1.143The NRC staff has identified the following consequences associated with adopting  Alternative 2.
 
3.2.1  Licensees will use the latest consensus standards available, thereby improving design,evaluation, and quality assurance of radioactive waste management systems, structures, and components.  The staff views the latest standards as improved because they incorporate the latest technology and knowledge on the subject.
 
3.2.2  Regulatory efficiency will be improved by reducing uncertainty as to what isacceptable and by encouraging consistency in the design, evaluation, and quality assurance of radioactive waste management systems, structures, and components.  The benefits to both the NRC
and industry will be to the extent this occurs.  An updated regulatory guide would facilitate NRC
review because licensee submittals should be more predictable and consistent analytically.
 
Similarly, licensee's adherence to the latest consensus standards should benefit licensees by reducing the likelihood for follow-up questions and possible revisions to licensees' plans.
 
3.2.3  An updated regulatory guide could result in cost savings for both the NRC andindustry.  From the NRC's perspective, relative to the baseline, NRC will incur one-time incremental costs to develop the regulatory guide for public comment and to finalize the regulatory guide. However, the NRC should also realize cost savings associated with the review of licensee submittals.  In the staff's view, the continuous and on-going cost savings associated with these


reviews should more than off-set this one-time cost.On balance, it is expected that industry would realize a net savings, as their one-timeincremental cost to review and comment on a revised regulatory guide would be more than
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
1.143-27compensated for by the efficiencies (e.g., reduced follow-up questions and revisions) associated with each licensee submittal.
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.


3.2.4  The use of industry consensus standards that are already being used by licenseeswould enhance the continued use of the guidance contained in ANS-55.1-92, ANS-55.4-93, and ANS-55.6-93, thereby avoiding costs related to a "new" agency-prepared standard. This approach would also comply with the Commission's directive that standards developed by consensus bodies be utilized per Public Law 104-113, "National Technology and Transfer Act of 1995."4.CONCLUSIONBased on this regulatory analysis, it is recommended that the NRC revise Regulatory Guide1.143.  The staff concludes that the proposed action will reduce unnecessary burden on both the NRC and its licensees, and it will result in an improved process for the design, evaluation, and quality assurance of radioactive waste management systems, structures, and components.
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
0 I Fih..i .Io fLIII11:,:Cd
11II%l~ic o l nk ma -% ! '.CL,01 Ill iWird.inic., %kith aippr.priaiv.


Furthermore, the staff sees no adverse effects associated with a revision to Regulatory Guide 1.143.BACKFIT ANALYSISThe regulatory guide does not require a backfit analysis as described in 10 CFR 50.109(c)because it does not impose a new or amended provision in the NRC's rules or a regulatory staff position interpreting the NRC's rules that is either new or different from a previous applicable staff position. In addition, this regulatory guide does not require the modification or addition to systems, structures, components, or design of a facility or the procedures or organization required to design, construct, or operate a facility.  Rather, a licensee or applicant may select a preferred method for achieving compliance with a license or the rules or the orders of the Commission as described in 10
:,IIcIls tif SL'ctjim;
CFR 50.109(a)(7). This regulatory guide provides an opportunity to use industry-developed standards if that is the method preferred by the licensee or applicant.}}
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Revision as of 12:57, 17 September 2018

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)
v • d • e


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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