Regulatory Guide 1.140: Difference between revisions

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{{Adams
{{Adams
| number = ML16070A277
| number = ML13350A263
| issue date = 08/31/2016
| issue date = 03/31/1978
| title = Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
| title = Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/RES
Line 9: Line 9:
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Burton S C
| contact person =  
| case reference number = RG 1.140, Rev. 3
| document report number = RG-1.140
| document report number = DG-1280
| package number = ML16068A291
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 19
| page count = 8
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
August 2016OFFICE OF NUCLEAR REGULATORY RESEARCH
COMMISSION
Revision 3 REGULATORY GUIDE
March 1978)REGULATORY  
  Technical Lead Jerome Bettle Written suggestions regarding this guide or development of new guides may be submitted through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html.  Electronic copies of this RG, previous versions of this guide, and other recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory guide is also available through the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML16070A277. The regulatory analysis may be found in ADAMS under Accession No. ML16082A538 and the staff responses to the public comments on DG-1280 may be found under ADAMS Accession No. ML16070A279.
GUIDE OFFICE OF STANDARDS
 
DEVELOPMENT
REGULATORY GUIDE 1.140 (Draft was issued as DG-1280, dated June 2012)
REGULATORY
DESIGN, INSPECTION, AND TESTING CRITERIA FOR AIR FILTRATION AND ADSORPTION UNITS OF NORMAL ATMOSPHERE CLEANUP SYSTEMS IN
GUIDE 1.140 DESIGN, TESTING, AND MAINTENANCE
LIGHT-WATER-COOLED NUCLEAR POWER PLANTS  
CRITERIA FOR NORMAL VENTILATION
EXHAUST SYSTEM AIR FILTRATION  
AND ADSORPTION  
UNITS OF LIGHT-WATER-COOLED  
NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
Purpose This regulatory guide (RG) describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable to implement regulatory requirements with regard to the design, inspection, and testing of normal atmosphere cleanup systems for controlling releases of airborne radioactive materials to the environment during normal operations, including anticipated operational occurrences
General Design Criteria 60 and 61 of Appendix A,"General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," require that filtering systems be included in the nuclear power unit design to control suitably the release of radioactive materials in gase-ous effluents during normal reactor operation, includ-ing anticipated operational occurrences and fuel stor-age and handling operations.
. This guide applies to all types of nuclear power plants that use water as the primary means of cooling.


Applicability This RG applies to all holders of and applicants for operating licenses for nuclear power reactors under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities" (Ref. 1), and all holders of and applicants for a power reactor combined license, standard design approval, or manufacturing license under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants" (Ref 2).  
In addition, §§50.34a,"Design objectives for equipment to control releases of radioactive material in effluents-nuclear power reactors," and 50.36a, "Technical specifications on effluents from nuclear power reactors," of 10 CFR Part 50 require that means be employed to ensure that release of radioactive material to unrestricted are, during normal reactor. operation, including  operational occurrences, is kept as low as i sea: sonably achievable.
Applicable Regulations
* Title 10, of the Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities" (10 CFR Part 50) and the associated appendices establish the requirements and design criteria for atmospheric cleanup systems.


o 10 CFR 50.34a and 50.36a, which relate to information that must be provided by applicants regarding how radioactive dose in effluents will be maintained as low as reasonably achievable (ALARA).  
Appendix I, "Numerical Guides for C Ob tives and Limiting Conditions for Oper .on tol eet the Criterion
'As Low As Is Reasonabl le'for Radioactive Material in Light-Water-Coo ed Nu-clear Power Reactor Effluents," to 10 CFR Part 50 provides guidance and n al values for design objectives to help appl t and holders of, licenses for nuclear we ant feet the require-ments of §§50.34 .Appendix I requires that each light- er-co d nuclear power reactor unit not exce an ua ose design objective of 15 mrem to a n ny individual in an unre-stricted area all exposure pathways from airborne radioactive io and particulate releases.


RG 1.140, Rev. 3, Page 2 o 10 CFR Part 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," which provides numerical guidance on design objectives for light-water-cooled nuclear power reactors to meet the requirements that radioactive material in effluents released to unrestricted areas be kept as low as is reasonably achievable.
Appendix I also requires that additional radwaste equipment be provided if the equipment has reasonably demon-strated technology and the cost-benefit ratio is favor-able.This guide presents methods ac j able to the NRC staff for implementing the Conxizition's regulations in 10 CFR Part 50 and in nl 'ndi $.A and I to 10 CFR Part 50 with regard to'b, desi,' testing, and maintenance criteria fo and adsorption units installed in thvqiOe, vation exhaust sys-tems of light-watepoo ed ch 5 lear power plants. This guide applies onlf-4.iCIosphere cleanup systems de-signed to co r dioactive materials during normal plant ptioi -'including anticipated opera-tional r d and addresses the atmosphere cleanup , including the various components a in the normal operating environment., e does not apply to postaccident
4e -dsafety-feature atmosphere cleanup sys-' at are designed to mitigate the consequences postulated accidents.


* 10 CFR 20.1406, "Minimization of contaminati on" (Ref. 3), which requires licensees, to the extent practical, to conduct operations to minimize the introduction of residual radioactivity into the site, including the subsurface, and requires app licants to describe in their applications how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive wast
Regulatory Guide 1.52, Oh ". esign, Testing, and Maintenance Criteria for Post-.accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants," pro-vides guidance for these systems.
 
====e. Related Guidance ====
* Regulatory Guide 1.52, "Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants" (Ref. 4), provides guidance for the engineered safety feature (ESF) systems.
 
* RG 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Reactor Power Plants" (Ref. 5), describes systems handling of radioactive materials in liquids, gaseous and solid collection systems that include construction of structures.
 
* RG 4.21, "Minimization of Contamination and Radioactive Waste Generation: Life Cycle Planning" (Ref. 6), gives guidance for design of facilities to minimize contamination of the facility and the environment, and to minimize the generation of waste.
 
* NUREG-0800 "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (Ref. 7), gives NRC review criteria for meeting the requirements of nuclear power plants. Purpose of Regulatory Guides The NRC issues RGs to describe to the public met hods that the staff considers acceptable for use in implementing specific parts of the agency's regulat ions, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations and compliance with them is not required. Methods and solutions that differ from those set forth in regulator y guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
 
Paper Reduction Act This RG contains and references information collections covered by 10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget (OMB), control numbers 3150-0011 and 3150-0151.
 
Public Protection Notification RG 1.140, Rev. 3, Page 3 The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.
 
RG 1.140, Rev. 3, Page 4


==B. DISCUSSION==
==B. DISCUSSION==
Reason for Revision This revision of the guide (Revision 3) addresses changes to the referenced industry standards, which provide comprehensive test and inspection requirements. Specifically, this guide is revised to address changes to the referenced industry standards since the NRC issued Revision 2 of RG 1.140 in June 2001. The American Society of Mechanical Engineers (ASME) Committee on Nuclear Air and Gas Treatment (CONAGT) revised and expanded the scope of equipment covered by ASME-AG-1, "Code on Nuclear Air and Gas Treatment" (Ref. 8), which the staff previously endorsed in RG 1.140. The revision to ASME-AG-1b consolidated some requirements from ASME-N509, "Nuclear Power Plant Air Cleaning Units and Components" (Ref. 9); ASME-N510, "Testing of Nuclear Air-Treatment Systems" (Ref. 10); and other documents previously endorsed by the staff in RG 1.140. In addition, CONAGT developed and published a new standard, ASME N511-2007, "Inservi ce Testing of Nuclear Air Treatment, Heating Ventilation and Air Conditioning Systems" (Ref. 11). 
Particulate filtration and radioiodine adsorption units are included in the design of the ventilation exhaust systems of light-water-coolc I nuclear power plants to reduce the quantities of raCractive mate-rials in gaseous effluents released fron. building or containment atmospheres during normal operation.
Background 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criterion (GDC) 60, "Control of Releases of Radioactive Materials to the Environment," requires in part, that a facility's design include the means to control the release of radioactive materials in gaseous effluents. In addition, GDC 61, "Fuel Storage and Handling and Radioactivity Control," requires in part, that fuel storage and handling, radioactive waste, and other systems which may contain radioactivity are designed with appropriate containment, confinement, and filtering systems. Title 10 CFR 50.34a, "Design Objectives for Equipment To Control Releases of Radioactive Material in Effluents-Nuclear Power Reactors," and 10 CFR 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," requires in part, that means be employed to ensure that the release of radioactive material to unrestricted areas during normal reactor operation, including during expected operational occurrences, is kept as low as reasonably achievable.  10 CFR 50.34a and 50.36a provide guidance and numerical values for design objectives to help applicants for new reactors and nuclear power plant license holders meet the requirements of 10 CFR Part 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion 'As Low As Is Reasonably Achiev able' (ALARA) for Radioactive Material in Light-Water- Cooled Nuclear Power Reactor Effluents." In addition to complying with the design objectives and ALARA provisions, Section II.D of Appendix I requires that additional radwaste equipment of reasonably demonstrated technology be installed if it results in a reduction of population doses within a 50-mile (80-km) radius from the power plant when added to the system in order of diminishing favorable cost-benefit return. The requirements of this Paragraph D need not be complied with by persons who have filed applications for construction permits which were docketed on or after January 2, 1971, and prior to June 4, 1976, if the radwaste systems and equipment described in the preliminary or final safety analysis report and amendments satisfy the Guides on Design Objectives for Light-Water-Cooled Nuclear Power Reactors proposed in the Concluding Statement of Position of the Regulatory Staff in Docket-RM-50-2 dated February 20, 1974, pp. 25-30, reproduced in the Annex to this Appendix I. The design of the normal atmosphere cleanup systems of light-water-cooled nuclear power plants includes particulate filtration and radioiodine adsorption units to reduce the quantities of radioactive materials in gaseous effluents released from primary containment or auxiliary building atmospheres during normal operations, including anticipated operational occurrences. These systems operate to meet the "as low as reasonably achievable" requirement s of 10 CFR 50.34a and
10 CFR 50.36a. Auxiliary RG 1.140, Rev. 3, Page 5 buildings can include those referred to as the secondary containment building, turbine building, radwaste building, and fuel handling building. Normal atmospheric cleanup systems are generally designed to operate continuously under normal environmental conditions, such as inlet radioiodine activity levels up to 37 millibecquerels per cubic centimeter (16.4 picocuries per cubic inch), relative humidity up to 100 percent, temperatures up to
52 degrees Celsius
(125 degrees Fahrenheit), and normal atmospheric pressure. System design, inspection, and testing anticipates the buildup of radioactive particulates and radioiodine and minimizes consequential degradation of system performance. The ambient environment both within and surrounding the facility may affect the performance of the normal atmosphere cleanup systems. Industrial contaminants and pollutants, as well as temperature and relative humidity, contribute to the aging and weathering of filters and adsorbers and reduce their reliability. Components of the normal atmosphere cleanup systems are designed for reliable performance under the expected operating conditions. Initial and inservice testing and proper maintenance are also primary factors in ensuring system reliability. Component and system design support and facilitate testing, inspection, and maintenance through built-in layout and accessibility features.
 
Section FF of ASME AG-1b-2009, provides the terminology and describes the characteristics of adsorbent media.  The only adsorbent media discussed in this RG is impregnated activated carbon because it is used nearly to the exclusion of all others by NRC licensees.  In addition to filtration systems used to treat exhausts from containment and auxiliary building atmospheres, cleanup systems are also used to treat process streams from power cycle waste offgas systems. These systems treat radioactive process and effluent streams characterized by the presence of noble gases, radioiodines, and mixtures of hydrogen and oxygen gases. These systems also operate to meet the "as low as reasonably achievable" requirements of 10 CFR 50.34a and 10 CFR 50.36a. The design of treatment systems used in power cycle waste offgas systems are characterized by the presence of hydrogen recombiners, compressors, delay tanks or vessels either empty or containing large amounts of activated carbon (e.g., hundreds of kilograms or thousands of pounds in PWRs or tens of thousands of kilograms/pounds in BWRs).  Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety guides and standards constituting a high level of safety for protecting people and the environment. IAEA safety guides present international good practices and increasingly reflects best practices to help users striving to achieve high levels of safety. Pertinent to this regulatory guide, IAEA Safety Guide NS-G-1.10, "Design of Reactor Containment Systems for Nuclear Power Plants" (Ref. 12), addresses the requirements of management of radionuclides leaking through a cont ainment of Nuclear Power Plants. Additionally, IAEA Safety Guide NS-G-2.7, "Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants" (Ref. 13), provides recommendations as to how to develop radiation protection programs. IAEA Safety Standard SSR-2/1, "Safety of Nuclear Power Plants: Design" (Ref. 14), addresses controlling the release of radioactive gases into the environment. The NRC has an interest in facilitating the harmonization of standards used domestically and internationally. This RG is consistent with the recommendations and guidance in the IAEA Safety Guides NS-G-1.10, NG-G-2.7 and SSR-2/1.
 
RG 1.140, Rev. 3, Page 6 Documents Discussed in Staff Regulatory Guidance This RG endorses the use of one or more codes or standards developed by external organizations, and other third party guidance documents. These codes, standards a nd third party guidance documents may contain references to other codes, standards or third party guidance documents ("secondary references"). If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in a RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a met hod acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a RG, then the secondary reference is neither a legally-binding requirement nor a "generic" NRC approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.
 
RG 1.140, Rev. 3, Page 7 C. STAFF REGULATORY GUIDANCE This section describes the methods and approves for use industry guidance, with clarifications or exceptions, which the NRC staff considers acceptable to implement regulatory requirements with regard to the design, inspection, and testing of normal atmosphere cleanup systems for controlling releases of airborne radioactive materials to the environment during normal operations, including anticipated operational occurrences. 1. General Design and Testing Criteria American Society of Mechanical Engineers code, ASME AG-1-2009, including 2010 Addenda 1a and 2011 Addenda 1b (i.e., ASME AG-1b-2009), and ASME N511-2007, provides guidance that is acceptable to the NRC staff for the design, construction, acceptance testing, quality assurance, and inservice testing of normal atmosphere cleanup systems and components. Normal atmosphere cleanup systems designed to ASME N509-2002 (Reaffirmed 2008), (or its earlier versions), and tested to ASME N510-2007, (or its earlier versions), are also considered adequate to protect public health and safety. 2. Environmental Design Criteria a. Design of normal atmosphere cleanup systems should be based on the anticipated range of operating parameters of temperature, pressure, relative humidity, and radiation levels during normal plant operations, including anticipated operational occurrences.
 
b. Normal atmosphere cleanup system operation should not degrade the operation or capability of any safety system required to operate after a design-basis accident.
 
c. Design of normal atmosphere cleanup systems should consider any reasonably expected significant contaminants, such as chemicals, dusts, or other particulate matter that could degrade the systems operation or capability.
 
d. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above environmental design criteria are deemed applicable, but should be evaluated and applied taking into consideration the system's specific design features. 3. System Design Criteria Normal atmospheric cleanup systems should be designed in accordance with ASME AG-1b-2009 as modified and supplemented by the following:
a. Normal atmosphere cleanup systems need not be redundant or designed to seismic Category I requirements, but they should consist of at least the following components:
(1) high-efficiency particulate air (HEPA) filters upstream of adsorbers;
(2) iodine adsorbers (typically impregnated activated carbon), if iodine removal from the airstream is anticipated;
(3) fans;  (4) interspersed ducts, dampers, and instrumentation;
 
RG 1.140, Rev. 3, Page 8
(5) prefilters upstream of HEPA filters, if needed to reduce particulate loading of the HEPA filters and achieve an acceptable service life;
(6) postfilters downstream of adsorbers, if needed to retain carbon fines; and
(7) heating elements or cooling coils, or both, if necessary to control humidity before filtration.
 
b. The volumetric airflow rate of a single filtration unit should be limited to 850 cubic meters (30,000 cubic feet) per minute unless reliable in-place testing can be assured. If a higher flow capacity is needed, consider a system design with multiple, parallel units.
 
c. Normal atmosphere cleanup systems should be provided with instrumentation recommended in Section IA of ASME AG-1b-2009 for monitoring and alarming
 
pertinent airflow rates and pressure drops.


d. Normal atmosphere cleanup systems design should limit personnel radiation exposure by incorporation of features that facilitate inspection, testing, and maintenance consistent with the guidance of RG 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable" (Ref. 15).
including anticipated operational occurrences.
e. Outdoor air intake openings should be equipped with louvers, grills, screens, or similar protective devices to minimize the adverse effects of high winds, rain, snow, ice, and other debris on system operation. Outdoor air intake openings should be located to minimize the effects of onsite sources of contaminants, such as diesel generator exhaust.


System design should consider potential airborne contaminants from offsite sources, such as nearby industrial facility discharges of dusts, combustion particulates and gases, dust storms, or salt spray particulate from nearby oceans or bays.
All such cleanup systems should be designed to operate continuously under normal environmental conditions.


f. Normal atmosphere cleanup system housings and ductwork should be designed to limit system total leakage rate, as defined in Article SA-4500 of ASME AG-1b-2009. Duct and housing leak tests should be performed consistent with Section TA of ASME AG-1b-2009. g. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above system design criteria are deemed applicable, but should be evaluated and applied taking into consideration the system's specific design features. 4. Component Design Criteria and Qualification Testing Components of normal atmosphere cleanup systems should be designed, constructed, and tested in accordance with Division II of ASME AG-1b-2009, as modified and supplemented by the following:
In this guide, cleanup systems that should operate to meet the "as low as is reasonably achievable" guidelines of Appendix I to 10 CFR Part 50 inside the primary containment (recirculating units) are desig-USNRC REGULATORY
a. Prefilters should be designed, constructed, and tested consistent with Sections FB or FJ of ASME AG-1b-2009.
GUIDES Comments should be sent to the Secretary of the Comm muon.US.Nucl.ae Rq.u Regulatory Guides we Issued to desculbe and Make Mvailalit to the public methods latore Commitsion.


b. Air heaters should be designed, constructed, and tested consistent with Section CA of ASME AG-1b-2009.
Washinto,.
O.C. 20?655. Attention Oocketng And  somptablit to the NRC staff of implementing specifi t pant of the Commision's Barnch.rtelatlint.


RG 1.140, Rev. 3, Page 9 c. HEPA filters should be designed, constructed, and tested cons istent with Sections FC of ASME AG-1b-2009. HEPA filters should be compatible with the chemical and physical composition and physical conditions of the air stream. Each HEPA filter should be tested for penetration of a challenge aerosol, such as dioctyl phthalate or 4-centistoke poly- alpha olephin, in accordance with Section TA of ASME AG-1b-2009.
to used by the staff In evaluating sp"tific Problems The guides we issued in the following ten broad dowsont Or postulated aicidents, or to provide it. epplieants.


d. HEPA and Type II adsorber cell mounting frames should be designed and constructed in accordance with Section FG of ASME AG-1b-2009.
Regulatory Guides are not sibstilutes for rsguilaions.


e. Filter and adsorber sections should be a rranged in accordance with Section HA of ASME AG-1b-2009.
and compliance with them is not required.


f. Filter housings, including floors and doors, and electrical conduits, drains, and other piping installed inside filter housings should be designed and constructed in accordance with Section HA of ASME AG-1b-2009.
I. Power Reactors 6. Products Methods end tOlutions different from thaw set out In the guitde will be Accept, 2. Researh and Test Reactors 7. Tranivootaton able if they provide a bash for the flndings requilte to the istuance or continuance
3. Fuels and Malrial Facilities
8. Occupational Health of a permit or Wiants@ b the CoenmIthlon.


g. If the relative humidity of the atmosphere entering the air cleanup system can be expected to exceed 70 percent during normal operation, the design should include heaters or cooling coils, or both, to maintain relative humidity at or below 70 percent to ensure adsorption unit efficiency. Heaters should be designed, constructed, and tested in accordance with Section CA of ASME AG-1b-2009.
4. Envirorinelnwtal and Sltilfg 9. Antitrust Reviyn, 5. Materiatls"d Plant Proteclion t0. General Commrents nd ugguestions for in thee guides ame encouraged it all timaes and guides will be revised, as appropriate, to accommodate commenti enfd Reouitsi for single copties of isstue guies iwhitch may :)e reuoducied or for tulace.to reflect new Informationt or eaperience.


h. Adsorber cells should be designed, constructed, and tested in accordance with Section FD for Type II or Section FE for Type III or Section FH of ASME AG-1b-2009 for Type IV adsorber cells.
Holwever, comnments On this guideif ment on an didtitiuon Ist tor ,sngie cosmse of tulqge quide in sspecific ,ohniesd within about t!wo monhst after Its Issuance.


(1) Design of an adsorber section should co nsider possible iodine desorption and adsorbent autoignition that may result from radioactivity-induced heat in the adsorbent and concomitant temperature rise. If needed, prevention and mitigation features could include low-flow air or inert gas bleed, cooling coils, cleanup unit isolation, or water sprays.
will be iParticularly useful in divisiont be madIe in writing to the US. Nuclear Regutaooiy Commission, evetuetlne the need for an teialy revition.


(2) If a water-based fire suppression or prevention (cooling) system is installed in a normal atmosphere cleanup system housing, it should be designed for manual actuation unless a reasonable possibility ex ists that iodine desorption and adsorbent autoignition could occur in the housing. If autoignition is a reasonable possibility, the fire suppression system should have both manual and automatic actuation. The fire suppression system should use open spray nozzles of sufficient size, number, and location to provide complete coverage over the entire surface of the combustible filter/adsorber media. The fire system should be hard piped and supplied with a reliable source of water of adequate pressure and flow. Location of the water supply manual actuation device should be remote from the cleanup system housing and consistent with the guidance of RG 8.8. Reliable mechanical or electrical detection devices sensing temperature, smoke, carbon monoxide, or other indications of fire ignition should be included in the system for manual and automatic actuation methods. Monitoring indicators for these detector outputs should be remote from the system housings and consistent with the guidance of RG 8.8 and support the manual actuation capability. Cross-zoning of detectors may be used for automatic actuation.
Washington, D.C. 2055. Attention.


RG 1.140, Rev. 3, Page 10
Oirector. of Oocument Cunt,ot nated as "primary systems." Primary systems gener-ally include a containment cleanup system (kidney filtration system). Systems that operate outside pri-mary containment are designated as "secondary sys-tems." Secondary systems generally include cleanup systems installed in the ventilation exhaust systems for the reactor building, turbine building, radwaste building, auxiliary building, mechanical vacuum pump, main condenser air ejector, and any other re-lease points that may contain particulates and gaseous radioiodine species. In some instances, filtration equipment installed in a postaccident hydrogen purge exhaust system may be designed to the recom-mendations of this guide, e.g., where a removal effi-ciency of 90% or less for radioiodine species is suffi-cient for the hydrogen purge exhaust system when the sum of the calculated loss-of-coolant accident (LOCA) dose and the post-LOCA
(3) For portions of atmospheric clean up systems and power cycle off gas systems (such as filter housings, delay tanks or beds, and low-points in ductwork), the design should consider features to collect and drain accumulated water from various sources. The presence and accumulation of water within portions of these systems may be attributed to condensation and from water-based fire suppression systems, when triggered. The design should provide the means to collect and route water to the appropriate radioactive waste management system given that the water would entrain radioactive materials present in such systems.
hydrogen purge dose is less than the guideline values of 10 CFR Part 100.Normal environmental conditions that these atmos-phere cleanup systems should withstand are inlet concentrations of radioactive iodine in the range of l0-6 to 10-13 j-Ci/cm 3 , relative humidity of the in-fluent stream up to 100%, temperatures of the in-fluent stream up to 125*F (52'C), and atmospheric pressure.


(4) The design of water collection systems and drains should consider the requirements of 10 CFR 20.1406 in minimizing the contamination of plant facilities and the environment. Additional guidance supporting 10 CFR 20.1406 is presented in: 
The system should be operated in such a manner that radiation levels of airborne radioactive material and redioiodine buildup on the adsorber do not deleteriously affect the operation of the filter sys-tem or any component.
1. Regulatory Guide 1.143, which describes systems handling of radioactive materials in liquids, gaseous and solid collection systems that include construction of structures. Further, RG 4.21 gives guidance for design of facilities to minimize contamination of the facility and the environment, and the generation of waste.


2. NUREG-0800 gives NRC review criteria for nuclear power plants.
An atmosphere cleanup system installed in a nor-mal ventilation exhaust system consists of some or all of the following components:
heaters or cooling coils used in conjunction with heaters, prefilters, high-efficiency particulate air (HEPA) filters, iodine ad-sorption units, fans, and associated ductwork, dam-pers, and instrumentation.


3. Nuclear Energy Institute (NEI) techni cal report NEI 08-08A "Guidance for Life Cycle Minimization of Contamination" (Ref. 16), provides a method for licensees to describe operational policies and operational programs to meet the programmatic requirements of 10 CFR Part 20.1406(a) and (b) for life cycle minimization of contamination. Meeting these requirements is achieved, in part, by addressing the applicable regulatory position elements of RG 4.21.
Heaters are designed to heat the influent stream to reduce its relative humid-ity before it reaches the filters and adsorbers.


The main objective of the regulations and NRC guidance is to avoid unmonitored and uncontrolled releases of radioactive materials on the site and in uncontrolled areas, and provide information that can be used to assess potential radiological hazards.
HEPA filters are installed to remove particulate matter, which may be radioactive, and pass the air stream to the adsorber.


i. The adsorber section of the normal atmosphere cleanup system may contain any adsorbent material demonstrated to remove gaseous iodine (elemental iodine and organic iodides) from air with the required efficiency or better.
The adsorber removes gaseous iodine (elemental iodine and organic iodides) from the air stream. HEPA filters downstream of the adsorber units collect carbon fines and provide redundant pro-tection against particulate release in case of failure of the upstream HEPA filter bank. The fan is the final item in an atmosphere cleanup system. Consideration should be given to installing prefilters upstream of the HEPA filters to reduce the particulate load and extend their service life.The environmental history will affect the perform-ance of the atmosphere cleanup system. Industrial contaminants, pollutants, temperature, and relative humidity contribute to the aging and weathering of filters and adsorbers and reduce their capability to perform their intended functions.


(1) Each original or replacement batch or lot of impregnated activated carbon media used in an adsorber section should be pr epared, inspected, and tested consistent with Section FF of ASME AG-1b-2009.
Therefore, aging, weathering, and poisoning of these components, which may vary from site to site, need to be consid-ered during design and operation.


(2) If impregnated activated carbon media is used, the adsorber section design should provide for a minimum atmosphere residence time of 0.05 seconds per centimeter (0.125 seconds per inch) of adsorbent media bed depth at rated flow.
Average temper-ature and relative humidity also vary from site to site, and the potential buildup of moisture in the adsorber warrants equal design consideration.


(3) Sections FD, FE, and FH of ASME AG-1b-2009 should be used to determine residence time.
The effects of these factors on the atmosphere cleanup system can be determined by scheduled testing during operation.


RG 1.140, Rev. 3, Page 11
All components of the atmosphere cleanup system installed in normal ventilation exhaust systems need to be designed for reliable performance under the ex-pected operating conditions.
(4) If sample (inservice test) canisters are used, their design should be consistent with Section FE of ASME AG-1b-2009 or Appendix I to ASME N509-2002.


j. Ductwork should be designed, constructed, and tested consistent with Section SA of ASME AG-1b-2009.
Initial testing and proper maintenance are primary factors in ensuring the relia-bility of the system. Careful attention during the de-sign phase to problems of system maintenance can contribute significantly to the reliability of the system by increasing the ease of such maintenance.


k. Duct and housing layout designs should minimize ledges, protrusions, and crevices that could collect dust and moisture and impede personnel work performance or create avoidable industrial safety hazards. Turning vanes or other airflow distribution devices should be installed where needed to achieve acceptably uniform flow profiles and support representative airflow measurements.
Of par-ticular importance in the design is a layout that pro-vides accessibility and sufficient working space so that the required functions can be performed safely.Periodic testing during operation to verify the effi-ciency of the components is another important means of ensuring reliability.


l. Dampers should be designed, constructed, and tested consistent with Section DA of ASME AG-1b-2009.
Built-in features that will facilitate convenient in-place testing are important in system design.Standards for the design and testing of atmosphere cleanup systems include ANSI /ASME N509-1976,"Nuclear Power Plant Air Cleaning Units and Com-ponents" (Ref. 1), and ANSI N510-1975, "Testing of Nuclear Air Cleaning Systems" (Ref. 2).Other standards are available for the construction and testing of certain components of systems. Where such standards are acceptable to the NRC staff, they are referenced in this guide. Where no suitable stand-ard exists, acceptable approaches are presented in this guide. ERDA 76-21, "Nuclear Air Cleaning Handbook" (Ref. 3), provides a comprehensive re-view of air filtration systems. It is not ! standard but a guide that discusses a number of acceptable design alternatives.


m. Fan/blower and motor, mounting, and ductwork connections should be designed, constructed, and tested consistent with Section BA for fans/blowers and Section SA of ASME AG-1b-2009 for ducts.
Not all of the documents mentioned in ANSI N509-1976 (Ref. 1), ANSI N510-1975 (Ref. 2), or other standards referenced in this guide have been the subject of an evaluation by the NRC staff as to their applicability or acceptability.


n. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above component design criteria and qualification testing are deemed applicable, but should be evaluated and applied taking into consideration the system's specific design features. 5. Maintainability Criteria  Cleanup system design should incorporate provisions for maintenance consistent with Section HA of ASME AG-1b-2009 as modified and supplemented by the following:
It should be noted that ANSI N509-1976 and ANSI N510-1975 refer to ORNL-NSIC-65, "Design, Construction and Testing of High-Efficiency Air Filtration Systems for Nuclear Application" (Ref. 4), which has been replaced by ERDA 76-21 (Ref. 3).C. REGULATORY
a. System design should support accessibility for inspection and maintenance. Filtration unit enclosures should provide a minimum of 0.92 meters (3 feet) from mounting frame to mounting frame between banks of components. Where components within a bank are designed for replacement, the spacing between banks should be the length of the component plus at least 0.92 meters (3 feet).  
POSITION Section 2 of ANSI N509-1976 (Ref. 1) and Sec-tion 2 of ANSI N510-1975 (Ref. 2) list additional documents referred to in these standards.
b. Cleanup system components (i.e., HEPA filters, prefilters, and adsorbers) that are used during system construction should be replaced before the system is declared fully


functional.
The specific applicability or acceptability of these listed docu-ments, as well as documents listed in other standards referenced in this guide, has been or will be covered separately in other regulatory guides, where appro-priate.Where reference is made to ORNL-NSIC-65 (Ref.4) in ANSI N509-1976 and in ANSI N510-1975, it*~1.140-2 should be interpreted to mean the corresponding por-tion of ERDA 76-21 (Ref. 3).1. Environmental Design Criteria a. The design of each atmosphere cleanup sys-tem installed in a normal ventilation exhaust system should be based on the maximum anticipated operat-ing parameters of temperature, pressure, relative humidity, and radiation levels. The cleanup system should be designed based on continuous operation for the expected life of the plant or the maximum antici-pated service life of the cleanup system.b. If the atmosphere cleanup system is located in an area of high radiation during normal plant opera-tion, adequate shielding of components from the radiation source should be provided.c. The operation of any atmosphere cleanup sys-tem in a normal ventilation exhaust system should not deleteriously affect the expected operation of any engineered-safety-feature system that must operate after a design basis accident.d. The design of the atmosphere cleanup system should consider any significant contaminants such as dusts, chemicals, or other particulate matter that could deleteriously affect the cleanup system's opera-tion.2. System Design Criteria a. Atmosphere cleanup systems installed in normal ventilation exhaust systems need not be re-dundant nor designed to seismic Category I classifica- tion, but should consist of the following sequential components:
(1) HEPA filters before the adsorbers, (2) iodine adsorbers (impregnated activated carbon or equivalent adsorbent such as metal zeolites), (3)ducts and dampers, (4) fans, and (5) related in-strumentation.


c. Duct access for inspection and maintenance should be provided consistent with the guidance of Section 4.3.4 of National Fire Protection Association (NFPA) 90A, "Standard for the Installation of Air Conditioning and Ventilation Systems" (Ref. 17).
If it is desired to reduce the particulate load on the HEPA filters and extend their service life, the installation of prefilters upstream of the initial HEPA bank is suggested.
d. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above maintainability criteria are deemed applicable, but should be evaluated and applied taking into consideration the system's specific design features.


RG 1.140, Rev. 3, Page 12
Consideration should also be given to the installation of a HEPA filter bank downstream of carbon adsorbers to retain carbon fines. Heaters or cooling coils used in conjunction with heaters should be used when the humidity is to be controlled before filtration.
6. In-Place Testing Criteria  Initial in-place testing of normal atmosphere cleanup systems should be performed consistent with Section TA of ASME AG-1b-2009. Periodic in-place testing of the cleanup systems and components should be performed consistent with ASME N511-2007 as modified and supplemented by the following:
a. A visual inspection of the normal atmosphere cleanup system and all associated components should be performed consistent with Appendix I to ASME N511-2007.


b. In-place aerosol leak tests for HEPA filters upstream from the carbon adsorbers should be performed (1) consistent with and at the frequency intervals shown in Section 5.7 and Appendix III to ASME N511-2007 , (2) after each partial or complete replacement of a HEPA filter bank, (3) following detection of, or evidence of, penetration or intrusion of water or other material into any portion of a cleanup system that may have an adverse effect on the functional capability of the filters, and (4) following painting, fire, or chemical release in any ventilation zone communicating with the system that may have an adverse effect on the functional capability of the system. The leak test should confirm a combined penetration and leakage (or bypass) of the normal atmosphere cleanup system of less than 0.05 percent of the challenge aerosol at a system-rated flow +/-10 percent to warrant a 99-percent removal efficiency for particulates.
b. The volumetric air flow rate of a single cleanup train should be limited to approximately
30,000 ft 3/min. If a total system air flow in excess of this rate is required, multiple trains should be used. For ease of maintenance, a filter layout that is three HEPA filters high and ten wide is preferred.


c. HEPA filter sections that fail to satisfy appropriate leak test criteria should be examined to determine location and cause of leaks. Ad justments, such as alignment of filter cases and tightening of filter hold-down fasteners, may be made. Defective, damaged, or torn filter media should not be repaired by patching and caulking; filters should be replaced and not repaired. After adjustments or filter replacement, the cleanup system should be retested.
c. Each atmosphere cleanup system should be locally instrumented to monitor and alarm pertinent pressure drops and flow rates in accordance with the recommendations of Section 5.6 of ERDA 76-21 (Ref. 3).d. To maintain the radiation exposure to operat-ing personnel as low as is reasonably achievable dur-ing plant maintenance, atmosphere cleanup systems should be designed to control leakage and facilitate maintenance in accordance with the guidelines of Regulatory Guide 8.8, "Information Relevant to En-suring that Occupational Radiation Exposures at Nu-clear Power Stations Will Be As Low As Is Rea-sonably Achievable" (Ref. 5).e. Outdoor air intake openings should be equipped with louvers, grills, screens, or similar pro-tective devices to minimize the effects of high winds, rain, snow, ice, trash, and other contaminants on the operation of the system. If the atmosphere surround-ing the plant could contain significant environmental contaminants, such as dusts and residues from smoke cleanup systems from adjacent coal burning power plants or industry, the design of the system should consider these contaminants and prevent them from affecting the operation of any atmosphere cleanup system.f. Atmosphere cleanup system housings and ductwork should be designed to exhibit on test a maximum total leakage rate as defined in Section 4.12 of ANSI N509-1976 (Ref. 1). Duct and housing leak tests should be performed in accordance with the provisions of Section 6 of ANSI N510-1975 (Ref. 2).3. Component Design Criteria and Qualification Testing a. Adsorption units functon efficiently at a rela-tive humidity of 70% or less. If the relative humidity of the incoming atmosphere is expected to be greater than 70% during normal reactor operation, heaters or cooling coils used in conjunction with heaters should be designed to reduce the relative humidity of the in-coming atmosphere to 70%. Heaters should be de-signed, constructed, and tested in accordance with the requirements of Section 5.5 of ANSI N509-1976 (Ref. 1) exclusive of sizing criteria.b. The HEPA filters should be designed, con-structed, and tested in accordance with the require-ments of Section 5.1 of ANSI N509-1976 (Ref. 1).Each HEPA filter should be tested for penetration of dioctyl phthalate (DOP) in accordance with the provi-sions of MIL,-F-51068 (Ref. 6) and MIL.-STD-282 (Ref. 7).e. Filter and adsorber mounting frames should be designed and constructed in accordance with the provisions of Section 5.6.3 of ANSI N509-1976 (Ref. 1).d. Filter and adsorber banks should be arranged in accordance with the recommendations of Section 4.4 of ERDA 76-21 (Ref. 3).e. System filter housings, including floors and doors, and electrical conduits, drains, and piping in-stalled inside filter housings should be designed and constructed in accordance with the provisions of Sec-tion 5.6 of ANSI N509-1976 (Ref. 1).f. Ductwork associated with the atmosphere cleanup system should be designed, constructed, and 1,140-3-_MMMý
I tested in accordance with the provisions of Section 5.10 of ANSI N509-1976 (Ref. 1).g. The adsorber section of the atmosphere cleanup system may contain any adsorbent material demonstrated to remove gaseous iodine (elemental iodine and organic iodides) from air at the required efficiency.


d. Cleanup system adsorbers should be in-place leak tested (1) consistent with and at the frequency intervals shown in Section 5.8 and Appendix IV to ASME N511-2007, (2) following removal of an adsorber sample for laboratory testing if the integrity of the adsorber section is affected, (3) after each partial or complete replacement of carbon adsorber in an adsorber section, (4) following detection of, or evidence of, penetration or intrusion of water or other material into any portion of a normal atmosphere cleanup system that may have an adverse effect on the functional capability of the adsorbers, and (5) following painting, fire, or chemical release in any ventilation zone communicating with the system that may have an adverse effect on the functional capability of the system. The leak test should confirm a combined penetration and leakage (or bypass) of the adsorber section of 0.05 percent or less of the challenge gas at a system-rated flow +/-10 percent.
Since impregnated activated carbon is commonly used, only this adsorbent is discussed in this guide. Each original or replacement batch of im-pregnated activated carbon used in the adsorber sec-tion should meet the qualification and batch test re-sults summarized in Table I of this guide.* If an adsorbent other than impregnated activated carbon is proposed or if the mesh size distribution is different from the specifications in Table 1, the pro-posed adsorbent should have demonstrated the capa-* bility to perform as well L- or better than activated carbon in satisfying the specifications in Table I. If impregnated activated carbon is used as the adsor-bent, the adsorber system should be designed for an average atmosphere residence time of 0.25 sec per two inches of adsorbent bed.h. Adsorber cells should be designed, con-structed, and tested in accordance with the require-ments of Section 5.2 of ANSI N509-1976 (Ref. 1).i. The system fan and motors, mounting, and ductwork connections should be designed, con-structed, and tested in accordance with the require-ments of Sections 5.7 and 5.8 of ANSI N509-1976 (Ref. I).j. The fan or blower used in the atmosphere cleanup system should be capable of operating under the environmental conditions postulated.


e. Adsorber sections that fail to satisfy the appropriate leak test conditions should be examined to determine the location and cause of leaks. Adjustments, such as alignment of adsorber cells, tightening of adsorber cell hold-down fasteners, or tightening of test canister fixtures, may be made. Defective or damaged adsorber cells, mounting frames, or housings should not be temporarily repaired with patching material or caulking. After adjustments or adsorber cell replacement, the cleanup system should be retested.
k. Ducts and housings should be laid out with a minimum of ledges, protrusions, and crevices that could collect dust and moisture and that could impede personnel or create a hazard to them in the perform-ance of their work. Straightening vanes should be in-stalled where required to ensure representative air flow measurement and uniform flow distribution through cleanup components., 1. Dampers should be designed, constructed, and tested in accordance with the provisions of Section 5.9 of ANSI N509-1976 (Ref. 1).4. Maintenance a. Accessibility of components and maintenance should be considered in the design of atmosphere cleanup systems in accordance with the provisions of Section 2.3.8 of ERDA 76-21 (Ref. 3) and Section 4.7 of ANSI N509-1976 (Ref. 1).b. For ease of maintenance, the system design should provide for a minimum of three feet from..mounting frame to mounting frame between banks of components.


f. Painting, fire, or chemical release is "not communicating" with the HEPA filter or adsorber if the cleanup system is not in operation, the isolation dampers are closed, and there is no pressure differential across the filter housing. This provides reasonable RG 1.140, Rev. 3, Page 13 assurance that air is not passing through the filters and adsorbers. Conservative, well-documented administrative controls should be implemented that define the terms "painting," "fire," and "chemical release" with respect to the potential for degrading cleanup system HEPA filters and adsorbers.
If components are to be replaced, the dimensions to be provided should be the maximum length of the component plus a minimum of three feet.c. The system design should provide for perma-nent test probes with external connections in accord-ance with the provisions of Section 4.11 of ANSI N509-1976 (Ref. 1).d. The cleanup components (e.p., HEPA filters and adsorbers)
should be installed after construction is completed.


g. If welding repairs are performed on, within, or adjacent to the cleanup system ducts, housing, or mounting frames, the HEPA filte rs and adsorbers should first be removed from the housing (or otherwise protected). When repairs are completed and filters and adsorbers reinstalled, the cleanup system should be visually inspected and leak tested as described in Regulatory Positions 6.a, 6.b, and 6.d of this guide.
5. In-Place Testing Criteria a. A visual inspection of the atmosphere cleanup system and all associated components should be made before each in-place airflow distribution test, DOP test, or activated carbon adsorber section leak test in accordance with the provisions of Section 5 of ANSI N510-1975 (Ref. 2).b. The airflow distribution to the HEPA filters and iodine adsorbers should be tested inplace for uniformity initially and after maintenance affecting the flow distribution.


h. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above in place testing criteria are deemed applicable, but shoul d be evaluated and applied taking into consideration the system's specific design features. 7. Laboratory Testing Criteria for Activated Carbon a. Activated carbon adsorber sections of the cleanup system should be assigned the decontamination efficiencies given in Table 1 for radioiodine if the following conditions are met: (1) The adsorber section meets the conditions given in Regulatory Position 6.d of this guide.
The distribution should be within +/- 20% of the average flow per unit when tested in accordance with the provisions of Section 9 of "Industrial Ventilation" (Ref. 8) and Section 8 of ANSI N510-1975 (Ref. 2).c. The in-place DOP test for HEPA filters should conform to Section 10 of ANSI N510-1975 (Ref. 2).HEPA filter sections should be tested in place ini-tially and at a frequency not to exceed 18 months thereafter (during a scheduled reactor shutdown is ac-ceptable).
The HEPA filter bank upstream of the ad-sorber section should also be tested following paint-ing, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the HEPA filters could become contaminated from the fumes, chemicals, or foreign materials.


(2) New activated carbon meets the physical property specifications given in Regulatory Position 4.i of this guide.
DOP penetration tests of all HEPA filter banks should con-firm a penetration of less than 0.05% at rated flow. A filtration system satisfying this condition can be con-sidered to warrant a 99% removal efficiency for par-ticulates.


(3) Representative samples of used activated carbon pass the laboratory tests given in Table 1 of this guide.
HEPA filters that fail to satisfy the in-place test criteria should be replaced with filters qualified pursuant to regulatory position C.3.b of this guide. If the HEPA filter bank is entirely or only partially re-placed, an in-place DOP test should be conducted.


b. Efficiency of an activated carbon adsorber section should be determined by laboratory testing of representative samples of the activated carbon experiencing the same service conditions and the same exposure to all contam inants as the entire adsorber section. Each representative sample should be 5.1 centimeters (2 inches) or more in both length and diameter, and each sample should have the same qualification and batch test characteristics as the system adsorbent. A sufficient number of representative samples should be located in parallel with the adsorber section to allow periodic determination of system adsorbent penetration throughout its service life. Where system activated carbon adsorber is greater than 5.1 centimeters (2 inches) deep, each representative sampling should consist of an equivalent depth. Once representative samples are removed for laboratory testing, the positions they occupied should be blocked off to maintain adsorber section capability.
If any welding repairs are necessary on, within, or adjacent to the ducts, housing, or mounting frames, the filters and adsorbers should be removed from the housing during such repairs. These repairs should be completed prior to periodic testing, filter inspection, and in-place testing. The use of silicone sealants or any other temporary patching material on filters, housing, mounting frames, or ducts should not be allowed.d. The activated carbon adsorber section should be leak-tested with a gaseous halogenated hydrocarbon refrigerant in accordance with Section 12 of ANSI N510-1975 (Ref. 2) to ensure that bypass leakage through the adsorber section is less than 0.05%. After the test is completed, air flow through the unit should be maintained until the residual refrigerant gas in the effluent is less than 0.01 ppm. Adsorber leak testing 1.140-4 should be conducted
(1) initially, (2) at a frequency not to exceed 18 months thereafter (during a sched-uled reactor shutdown is acceptable), (3) following removal of an adsorber sample for laboratory testing if the integrity of the adsorber section is affected, and (4) following painting, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the charcoal adsorbers could become contaminated from the funs, chemicals, or foreign materials.


c. Sampling and analysis of adsorbent should be performed (1) consistent with and at the frequency intervals shown in Sections 7 and 5.9 of ASME N511-2007, (2) following painting, fire, or chemical release in any ventilation zone communicating with the system that may have an adverse effect on the functional capability of the carbon media, and (3) following detection of, or evidence of, penetration or intrusion of water or other material into any portion of a normal atmosphere cleanup system that may have an adverse effect on the functional capability of the adsorber media.
6. Laboratory Testing Criteria for Activated Carbon a. The activated carbon adsorber section of the atmosphere cleanup system should be assigned the decontamination efficiencies given in Table 2 for radioiodine if the following conditions are met: (1) The adsorber section meets the conditions given in regulatory position C.5.d of this gvi'i_., (2) New activated carbon meets the physical property specifications given in Table 1, and (3) Representative samples of used activated carbon pass the laboratory tests given in Table 2.If the activated carbon fails to meet any of the above conditions, it should not be used in adsorption units.b. The efficiency of the activated carbon ad-sorber section should be determined by laboratory testing of representative samples of the activated car-bon exposed simultaneously to the same service con-ditions as the adsorber section. Each representative sample should be not less than two inches in both length and diameter, and each sample should have the same qualification and batch test characteristics as the system adsorbent.


RG 1.140, Rev. 3, Page 14 d. Laboratory tests of representative samples of adsorbent should be conducted as indicated in Table 1 of this guide, with the test gas flow in the same direction as normal cleanup system flow unless using bulk sample extraction methods from deep bed adsorbers. Similar laboratory tests should be performed on a sample before loading media into the adsorber section to establish a baseline for comparison with future sample test results.
There should be a sufficient number of representative samples located in parallel with the adsorber section to estimate the amount of penetration of the system adsorbent throughout its service life. The design of the samplers should be in accordance with the provisions of Appendix A of ANSI N509-1976 (Ref. 1). Where the system acti-vated carbon is greater than two inches deep, each representative sampling station should consist of enough two-inch samples in series to equal thc thick-ness of the system adsorbent.


The contents of an activated carbon adsorber section should be replaced with new, unused activated carbon adsorbent meeting the physical properties identified in Regulatory Position 4.i of this guide if (1) testing in accordance with Table 1 of this guide results in a representative sample failing an acceptance criterion or (2) no representative sample is available for testing.
Once reprcsentative samples are removed for laboratory test their posi-tions in the sampling array should be blocked off.Laboratory tests of representative samples should be conducted, as indicated in Table 2 of this guide, with the test gas flow in the same direction as the flow during service conditions.


e. For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the above laboratory testing criteria for activated carbon are deemed applicable, but should be evaluated and applied taking into consideration the system's specific design features. Table 1. Inservice Adsorber Laboratory Tests for Activated Carbon Activated Carbon Total Bed Depth Maximum Assigned Activated Carbon Decontamination Efficiencies Methyl Iodide Penetration Acceptance Criterion for Representative Sample
Similar laboratory tests should be performed on an adsorbent sample be-fore loading into the adsorbers to establish an initial point for comparison of future test results. The acti-vated carbon adsorber section should be replaced with new unused activated carbon meeting the physi-cal property specifications of Table I if (1) testing in accordance with the frequency specified in Footnote c of Table 2 results in a representative sample failing to pass the applicable test in Table 2 or (2) no represen-tative sample is available for testing.
  2 inches  Elemental iodine
 
Organic iodide 95% 
95% Penetration 5% when tested in accordance with ASTM D3803-1991
4 inches or greater (in-series beds are treated as a single bed of aggregate depth)
Elemental iodine Organic iodide 99%  99% Penetration 1% when tested in accordance with ASTM D3803-1991  Activated carbon in delay tanks or beds  Elemental iodine
 
Organic iodide 99% 
99% Penetration 1% when tested in  accordance with ASTM D3803-1991 
 
Table 1 Notes:
(1) See Appendix I to ASME N509-2002 for the definition of a representative sample. (2) Credited decontamination efficiencies (a portion of which includes bypass leakage) are based on a 0.25-second residence time per 5.1 centimeter (2-inch bed depth). (3) The activated carbon, when new, should meet the specifications of Regulatory Position 4.i of this guide. Table 1 provides acceptable decontamination efficiencies and methyl iodide test penetrations of used activated carbon samples for laboratory testing. Testing should be performed at the frequencies specified in Regulatory Position 7.c of this guide. Testi ng should be performed in accordance with American Society for Testing and Materials (ASTM) D3803-1991 (Reaffirmed 2014, "Standard Test Methods for Nuclear-Grade Activated Carbon" (Ref. 18), with an entering air temperature of 30 degrees Celsius (86 degrees Fahrenheit) and a relative humidity of 95 percent (or 70 percent with humidity control). Humidity control can be provided by heaters, cooling coils, or an analysis that demonstrates that the air entering the installed adsorber section would be maintained less than or equal to a 70-percent relative humidity level.
 
RG 1.140, Rev. 3, Page 15
(4) Organic iodide and elemental iodine are the forms of iodine that are expected to be absorbed by activated carbon. Organic iodide is more difficult for activated carbon to adsorb than elemental iodine. Therefore, the laboratory test to determine the performance of the activated carbon adsorber is based on organic iodide. Methyl iodide is the organic form of iodine that is used in the laboratory test.
 
(5) For power cycle waste offgas systems relying on activated carbon delay tanks or beds, the inservice adsorber laboratory tests should confirm that the proper types of activated carbon (nuclear grade and defined mesh size) are tested for representative batches of activated carbon over the entire design inventory of the waste offgas treatment system, given the design capacity and number of delay tanks or beds.
 
RG 1.140, Rev. 3, Page 16


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide information on how applicants and licensees
The purpose of this section is to provide informa-tion to applicants and licensees 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 or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein is being and will continue to be used in the evaluation of submittals for operating license or con-struction permit applications until this guide is re-vised as a result of suggestions from the public or additional staff review.I 1.140-5 I,  
1 may use this guide and information regarding the NRC's plans for using this regulatory guide. In addition, it describes how the NRC staff complies with 10 CFR 50.109, "Backfitting" and any applicable finality provisions in 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants."  Use by Applicants and Licensees Applicants and licensees may voluntarily
TABLE 1 PHYSICAL PROPERTIES
2 use the guidance in this document to demonstrate compliance with the underlying NRC regulations. Methods or solutions that differ from those described in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations. Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged
OF NEW ACTIVATED
. Licensees may use the information in this regulatory guide for actions which do not require NRC review and approval such as changes to a facility design under 10 CFR 50.59, "Changes, Tests, and Experiments." Licensees may use the information in this regulatory guide or applicable parts to resolve regulatory or inspection issues.  Use by NRC Staff  The NRC staff does not intend or approve any imposition or backfitting of the guidance in this regulatory guide. The NRC staff does not expect a ny existing licensee to use or commit to using the guidance in this regulatory guide, unless the licensee makes a change to its licensing basis. The NRC staff does not expect or plan to request licensees to voluntarily adopt this regulatory guide to resolve a generic regulatory issue. The NRC staff does not expect or plan to initiate NRC regulatory action which would require the use of this regulatory guide. Examples of such unplanned NRC regulatory actions include issuance of an order requiring the use of the regulatory guide, requests for information under 10 CFR 50.54(f) as to whether a licensee intends to commit to use of this regulatory guide, generic communication, or promulgation of a rule requiring the use of this regulatory guide without further
CARBON BATCH TESTS" TO BE PERFORMED
 
ON FINISHED ADSORBENT Test 1. Particle size distribution
backfit consideration. During regulatory discussions on plant specific operational issues, the staff may discuss with licensees various actions consistent with staff positions in this regulatory guide, as one acceptable means of meeting the underlying NRC regulatory requirement. Such discussions would not ordinarily be considered backfitting even if prior versions of this regulatory guide are part of the licensing basis of the facility. However, unless this regulatory guide is part of the licensing basis for a facility, the staff may not represent to the licensee that the licensee's failure to comply with the positions in this regulatory guide constitutes a violation. If an existing licensee voluntarily seeks a license amendment or change and (1) the NRC staff's consideration of the request involves a regulatory issue directly relevant to this new or revised regulatory guide and (2) the specific subject matter of this regulatory guide is an essential consideration in the staff's                                           
2. Hardness number 3. Ignition te-aperature
1  In this section, "licensees" refers to licensees of nuclear power plants under 10 CFR Parts 50 and 52; and the term "applicants," refers to applicants for licenses and permits for (or relating to) nuclear power plants under 10 CFR Parts 50 and 52, and applicants for standard design approvals and standard design certifications under 10 CFR Part 52.
4. CCI 4 Activity'5. Radioiodine removal efficiency a. Elemental iodine, 25°C and 95% relative humidity b. Methyl iodide, 25*C and 95% relative humidity 6. Bulk density 7. Impregnant content Acceptable Test Method ASTM D2862 (Ref. 9)RDT M16-IT, Appendix C (Ref. 10)RDT M16-IT, Appendix C (Ref. 10)CCI 4 Activity, RDT M16-IT, Appendix C (Ref. 10)RDT M 16-IT (Ref. 10)para. 4.5.1, except 95% relative humidity air is required RDT MI6-IT (Ref. 10)para. 4.5.3, except 95% relative humidity air is required ASTM D2854 (Ref. 11)State procedure Acceptable Results Retained on #6 ASTM El 1 b Sieve: 0.0%Retained on #8 ASTM El ! Sieve: 5.0% max.Through #8, rctained on #12 Sieve: 40% to 60%Through # 12, retained on # 16 Sieve: 40% to 60%Through # 16 ASTM Elib Sieve: 5.0% max.Through #18 ASTM ElIb Sieve: 1.0% max.95 minimum 330"C minimum at 100 fpm 60 minimum 99.5%95%0.38 g/ml minimum State type (not to exceed 5% by weight)a A "batch test" is a test made on a production batch of a product to establish suitability for a specific application.
 
2  In this section, "voluntary" and "voluntarily" means that the licensee is seeking the action of its own accord, without the force of a legally binding requirement or an NRC representation of further licensing or enforcement action.
 
RG 1.140, Rev. 3, Page 17 determination of the acceptability of the licensee's request, then the staff may request that the licensee either follow the guidance in this regulatory guide or provide an eq uivalent alternative process that demonstrates compliance with the underlying NRC regulatory requirements. This is not considered backfitting as defined in 10 CFR 50.109(a)(1) or a violation of any of the issue finality provisions in 10 CFR Part 52. Additionally, an existing applicant may be required to comply to new rules, orders, or guidance if 10 CFR 50.109(a)(3) applies.  If a licensee believes that the NRC is either using this regulatory guide or requesting or requiring the licensee to implement the methods or processes in this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfit appeal with the NRC in accordance with the guidance in NRC Management Directive 8.4, "Management of Facility-Specific Backfitting and Information Collection" (Ref. 19)  
and NUREG-1409, "Backfitting Guidelines," (Ref. 20).
 
RG 1.140, Rev. 3, Page 18 REFERENCES
3 1. U.S. Code of Federal Regulations (CFR) "Domestic Licensing of Production and Utilization Facilities," Part 50, Chapter 1, Title 10, "Energy," Washington, DC.
 
2. CFR, "Licenses, Certifications, and Approvals for Nuclear Power Plants," Part 52, Chapter 1, Title 10, "Energy," Washington, DC.
 
3. CFR, 10 CFR 20.1406, "Minimization of contamination," U.S. Nuclear Regulatory Commission, Washington DC.
 
4. Nuclear Regulatory Commission (NRC), Regulatory Guide 1.52, "Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants,"
Washington, DC.
 
5. NRC, Regulatory Guide 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Reactor Power Plants," Washington, DC.
 
6. NRC, Regulatory Guide 4.21, "Minimization of Contamination and Radioactive Waste Generation: Life Cycle Planning," Washington, DC.
 
7. NRC, NUREG-0800 "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" 
8. American Society of Mechanical Engineers (ASME) AG-1b-2009, "Code on Nuclear Air and Gas Treatment," 2009, including 2010 Addenda 1a and 2011 Addenda 1b, American Society of Mechanical Engineers, New York, NY.


4 9. ASME N509-2002 (Reaffirmed 2008), "Nuclear Power Plant Air-Cleaning Units and Components," American Society of Mechanical Engineers, New York, NY.
A "batch of activated carbon" is a quantity of material of the same grade, type, and series that has been homogenized to exhibit, within reason-able tolerance, the same performance and physical characteristics and for which the manufacturer can demonstrate by acceptable tests and quality control practices such uniformity.


10. ASME N510-2007, "Testing of Nuclear Air-Treatment Systems," American Society of Mechanical Engineers, New York, NY.
All material in the same batch should be activated, impregnated, and otherwise treated under the same process conditions and procedures in the same process equipment and should be produced under the same manufactur- ing release and instructions.


11. ASME N511-2007, Standard N511, "Inservice Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems," American Society of Mechanical Engineers, New York, NY.
Material produced in the same charge of batch equipment constitutes a batch; material produced in different charges of the same batch equipment should be included in the same batch only if it can be homogenized as above. The maximum batch size should be 350 ftW of activated carbo


3  Publicly available documents from the U.S. Nuclear Regulatory Commission (NRC) are available electronically  through the NRC Library on the NRC's public Web site at http://www.nrc.gov
====n. b See Reference ====
/reading-rm/doc-collections/. The documents can also be viewed on-line for free or printed for a fee in the NRC's Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301) 415 3548; and e-mail pdr.resource@nrc.gov.  4  Copies of American Society of Mechanical Engineers (ASME) standards may be purchased from ASME, Two Park Avenue, New York, New York 10016-5990; telephone (800) 843-2763. Purchase information is available through the ASME Web-based store at http://www.asme.org/Codes/Publications/. 
12.C This test should be performed on base material.1.140-6 TABLE 2 LABORATORY
RG 1.140, Rev. 3, Page 19
TESTS FOR ACTIVATED
12. International Atomic Energy Agency (IAEA), NS-G-1.10, "Design of Reactor Containment Systems of Nuclear Power Plants," Vienna, Austria.
CARBON Activated Carbon" Bed Depth b 2 inches. Air filtration system designed to operate inside primary containment.


5 13. IAEA, NS-G-2.7, "Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants," Vienna, Austria.
2 inches. Air filtration system designed to operate outside the primary contain-ment, and relative humidity is controlled to 70%4 inches. Air filtration system designed to operate outside the primary contain-ment, and relative humdity is controlled to 70%.6 inches. Air filtration system designed to operate outside the primary contain-ment, and relativr;
humidity is controlled to 7G%.Assigned Activated Carbon Decontamination Efficiencies For Radioiodine
90%70%Laxboratory Tests for a Representativc SampleC Per Test 5.b in Table I for a methyl iodide pene-tration of less than 10%.Per Test 5.b in Table I at a rclative humidity of 70% for a methyl iodide penetration of less than 10%.Per Test 5.b in Table 1 at a relative humidity of 70%for a methyl iodide pene-tration of less than 10%.Per Test 5.b in Table I at a relative humidity of 70%for a methyl iodide penetra-tion of less than 1%.90%99%* The activated carbon, when new, should meet the specifications of regulatory position C.3.g of this guide.b Multiple beds. e.g., two 2-inch beds in series, should be treated as a single bed of aggregate depth.See regulatory position C.6.b for definition of representative sample. Testing should be performed
(1) initially, (2) at a frequency not to exceed 18 months (during a scheduled reactor shutdown is acceptable), and (3) following painting, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the charcoal adsorbers could become contaminated from the fumes, chemicals, or foreign materials.


14. IAEA, SSR-2/1, "Safety of Nuclear Power Plants:  Design," Vienna, Austria.
REFERENCES
1. American National Standard ANSI/ASME
N509-1976, "Nuclear Power Plant Air Cleaning Units and Components." Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.2. American National Standard ANSI N510-1975,"Testing of Nuclear Air Cleaning Systems,''
American Society of Mechanical Engineers.


15. NRC, Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Washington, DC.
3. ERDA 76-21, "Nuclear Air Cleaning Hand-book," Oak Ridge National Laboratory, C. A.Burchsted, J. E. Kahn, and A. B. Fuller, March 31, 1976. Copies may be obtained from the Na-tional Technical Information Service, Springfield, Va. 22161.4. ORNL-NSIC-65, "Design, Construction, and Testing of High Efficiency Air Filtration Systems for Nuclear Application," Oak Ridge National Laboratory, C. A. Burchsted and A. B. Fuller, January 1970. Copies may be obtained from the National Technical Information Service.5. Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Office of Standards Development, U.S. Nuclear Regulatory Commis-sion.6. MIL-F-51068, "Filter, Particulate.


16. Nuclear Energy Institute (NEI) technical report NEI 08-08A "Guidance for Life Cycle Minimization of Contamination," (ADAMS Accession Number ML093220530, ML092720253)  
High-Efficiency, Fire-Resistant" (latest edition), Mili-tary Specification.
17. National Fire Protection Association, (NFPA) 90A, "Standard for the Installation of Air Conditioning and Ventilation Systems," National Fire Codes, 2002, Quincy, MA.


6 18. American Society for Testing and Materials (ASTM) D3803-1991 (Reaffirmed 2014), "Standard Test Methods for Nuclear-Grade Ac tivated Carbon," ASTM International, West Conshohocken, PA.
Copies may be obtained from the Naval Publications and Forms Center, 5801 Tabor Ave., Philadelphia, Penn. 19120.7. MIL-STD-282, "Filter Units, Protective Cloth-ing, Gas-Mask Components and Related Products: Performance-Test Methods," Military Standard, 28 May 1956. Copies may be obtained from the address given in Reference
6.8. American Conference of Governmental Industrial Hygienists, "Industrial Ventilation," 14th Edi-tion, 1976, Committee on Industrial Ventilation, P.O. Box 453, Lansing, Mich. 48902.9. ASTM D2862-70, "Test for Particle Size Distribu-tion of Granulated Activated Carbon." Copies 1.140-7 a .a may be obtained from the American Society for Testing and Materials, 1916 Race Street, Philadelphia, Penn. 19103.10. RDT Standard M16-IT, "Gas-Phase Adsorbents for Trapping Radioactive Iodine and Iodine Com-pounds." USAEC Division of Reactor Research and Development.


7 19. NRC, Management Directive 8.4, "Management of Facility-specific Backfitting and Information Collection," Washington DC.
October 1973, Oak Ridge, Tenn.37830.UNITEO STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, 0. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, S300 11. ASTM D2854-70, "Test for Apparent Density of Activated Carbon," American Society for Test-ing and Materials.


20. NRC, NUREG-1409, "Backfitting Guidelines," Washington DC.
12. ASTM El 1-70, "Specifications for Wire Cloth Sieves for Testing Purposes," American Society for Testing and Materials.


5  Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site:  www.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org
POSTAGE AND FEES PAID U.S. NUCLEAR REGULATOR
  6  Copies of the National Fire Protection Association (NFPA) may be purchased from the NFPA, 1 Batterymarch Park, Quincy, Massachusetts; telephone (800) 344-3555. Purchase information is available through the NFPA Web-based store at http://www.nfpa.org/Catalog/. 7  Copies of American Society for Testing and Materials (ASTM) standards may be purchased from ASTM, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, Pennsylvania 19428-2959; telephone (610) 832-9585. Purchase information is available through the ASTM Web site at http://www.astm.org.}}
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Revision as of 19:54, 12 October 2018

Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants
ML13350A263
Person / Time
Issue date: 03/31/1978
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.140
Download: ML13350A263 (8)
v • d • e


U.S. NUCLEAR REGULATORY

COMMISSION

March 1978)REGULATORY

GUIDE OFFICE OF STANDARDS

DEVELOPMENT

REGULATORY

GUIDE 1.140 DESIGN, TESTING, AND MAINTENANCE

CRITERIA FOR NORMAL VENTILATION

EXHAUST SYSTEM AIR FILTRATION

AND ADSORPTION

UNITS OF LIGHT-WATER-COOLED

NUCLEAR POWER PLANTS

A. INTRODUCTION

General Design Criteria 60 and 61 of Appendix A,"General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," require that filtering systems be included in the nuclear power unit design to control suitably the release of radioactive materials in gase-ous effluents during normal reactor operation, includ-ing anticipated operational occurrences and fuel stor-age and handling operations.

In addition, §§50.34a,"Design objectives for equipment to control releases of radioactive material in effluents-nuclear power reactors," and 50.36a, "Technical specifications on effluents from nuclear power reactors," of 10 CFR Part 50 require that means be employed to ensure that release of radioactive material to unrestricted are, during normal reactor. operation, including operational occurrences, is kept as low as i sea: sonably achievable.

Appendix I, "Numerical Guides for C Ob tives and Limiting Conditions for Oper .on tol eet the Criterion

'As Low As Is Reasonabl le'for Radioactive Material in Light-Water-Coo ed Nu-clear Power Reactor Effluents," to 10 CFR Part 50 provides guidance and n al values for design objectives to help appl t and holders of, licenses for nuclear we ant feet the require-ments of §§50.34 .Appendix I requires that each light- er-co d nuclear power reactor unit not exce an ua ose design objective of 15 mrem to a n ny individual in an unre-stricted area all exposure pathways from airborne radioactive io and particulate releases.

Appendix I also requires that additional radwaste equipment be provided if the equipment has reasonably demon-strated technology and the cost-benefit ratio is favor-able.This guide presents methods ac j able to the NRC staff for implementing the Conxizition's regulations in 10 CFR Part 50 and in nl 'ndi $.A and I to 10 CFR Part 50 with regard to'b, desi,' testing, and maintenance criteria fo and adsorption units installed in thvqiOe, vation exhaust sys-tems of light-watepoo ed ch 5 lear power plants. This guide applies onlf-4.iCIosphere cleanup systems de-signed to co r dioactive materials during normal plant ptioi -'including anticipated opera-tional r d and addresses the atmosphere cleanup , including the various components a in the normal operating environment., e does not apply to postaccident

4e -dsafety-feature atmosphere cleanup sys-' at are designed to mitigate the consequences postulated accidents.

Regulatory Guide 1.52, Oh ". esign, Testing, and Maintenance Criteria for Post-.accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants," pro-vides guidance for these systems.

B. DISCUSSION

Particulate filtration and radioiodine adsorption units are included in the design of the ventilation exhaust systems of light-water-coolc I nuclear power plants to reduce the quantities of raCractive mate-rials in gaseous effluents released fron. building or containment atmospheres during normal operation.

including anticipated operational occurrences.

All such cleanup systems should be designed to operate continuously under normal environmental conditions.

In this guide, cleanup systems that should operate to meet the "as low as is reasonably achievable" guidelines of Appendix I to 10 CFR Part 50 inside the primary containment (recirculating units) are desig-USNRC REGULATORY

GUIDES Comments should be sent to the Secretary of the Comm muon.US.Nucl.ae Rq.u Regulatory Guides we Issued to desculbe and Make Mvailalit to the public methods latore Commitsion.

Washinto,.

O.C. 20?655. Attention Oocketng And somptablit to the NRC staff of implementing specifi t pant of the Commision's Barnch.rtelatlint.

to used by the staff In evaluating sp"tific Problems The guides we issued in the following ten broad dowsont Or postulated aicidents, or to provide it. epplieants.

Regulatory Guides are not sibstilutes for rsguilaions.

and compliance with them is not required.

I. Power Reactors 6. Products Methods end tOlutions different from thaw set out In the guitde will be Accept, 2. Researh and Test Reactors 7. Tranivootaton able if they provide a bash for the flndings requilte to the istuance or continuance

3. Fuels and Malrial Facilities

8. Occupational Health of a permit or Wiants@ b the CoenmIthlon.

4. Envirorinelnwtal and Sltilfg 9. Antitrust Reviyn, 5. Materiatls"d Plant Proteclion t0. General Commrents nd ugguestions for in thee guides ame encouraged it all timaes and guides will be revised, as appropriate, to accommodate commenti enfd Reouitsi for single copties of isstue guies iwhitch may :)e reuoducied or for tulace.to reflect new Informationt or eaperience.

Holwever, comnments On this guideif ment on an didtitiuon Ist tor ,sngie cosmse of tulqge quide in sspecific ,ohniesd within about t!wo monhst after Its Issuance.

will be iParticularly useful in divisiont be madIe in writing to the US. Nuclear Regutaooiy Commission, evetuetlne the need for an teialy revition.

Washington, D.C. 2055. Attention.

Oirector. of Oocument Cunt,ot nated as "primary systems." Primary systems gener-ally include a containment cleanup system (kidney filtration system). Systems that operate outside pri-mary containment are designated as "secondary sys-tems." Secondary systems generally include cleanup systems installed in the ventilation exhaust systems for the reactor building, turbine building, radwaste building, auxiliary building, mechanical vacuum pump, main condenser air ejector, and any other re-lease points that may contain particulates and gaseous radioiodine species. In some instances, filtration equipment installed in a postaccident hydrogen purge exhaust system may be designed to the recom-mendations of this guide, e.g., where a removal effi-ciency of 90% or less for radioiodine species is suffi-cient for the hydrogen purge exhaust system when the sum of the calculated loss-of-coolant accident (LOCA) dose and the post-LOCA

hydrogen purge dose is less than the guideline values of 10 CFR Part 100.Normal environmental conditions that these atmos-phere cleanup systems should withstand are inlet concentrations of radioactive iodine in the range of l0-6 to 10-13 j-Ci/cm 3 , relative humidity of the in-fluent stream up to 100%, temperatures of the in-fluent stream up to 125*F (52'C), and atmospheric pressure.

The system should be operated in such a manner that radiation levels of airborne radioactive material and redioiodine buildup on the adsorber do not deleteriously affect the operation of the filter sys-tem or any component.

An atmosphere cleanup system installed in a nor-mal ventilation exhaust system consists of some or all of the following components:

heaters or cooling coils used in conjunction with heaters, prefilters, high-efficiency particulate air (HEPA) filters, iodine ad-sorption units, fans, and associated ductwork, dam-pers, and instrumentation.

Heaters are designed to heat the influent stream to reduce its relative humid-ity before it reaches the filters and adsorbers.

HEPA filters are installed to remove particulate matter, which may be radioactive, and pass the air stream to the adsorber.

The adsorber removes gaseous iodine (elemental iodine and organic iodides) from the air stream. HEPA filters downstream of the adsorber units collect carbon fines and provide redundant pro-tection against particulate release in case of failure of the upstream HEPA filter bank. The fan is the final item in an atmosphere cleanup system. Consideration should be given to installing prefilters upstream of the HEPA filters to reduce the particulate load and extend their service life.The environmental history will affect the perform-ance of the atmosphere cleanup system. Industrial contaminants, pollutants, temperature, and relative humidity contribute to the aging and weathering of filters and adsorbers and reduce their capability to perform their intended functions.

Therefore, aging, weathering, and poisoning of these components, which may vary from site to site, need to be consid-ered during design and operation.

Average temper-ature and relative humidity also vary from site to site, and the potential buildup of moisture in the adsorber warrants equal design consideration.

The effects of these factors on the atmosphere cleanup system can be determined by scheduled testing during operation.

All components of the atmosphere cleanup system installed in normal ventilation exhaust systems need to be designed for reliable performance under the ex-pected operating conditions.

Initial testing and proper maintenance are primary factors in ensuring the relia-bility of the system. Careful attention during the de-sign phase to problems of system maintenance can contribute significantly to the reliability of the system by increasing the ease of such maintenance.

Of par-ticular importance in the design is a layout that pro-vides accessibility and sufficient working space so that the required functions can be performed safely.Periodic testing during operation to verify the effi-ciency of the components is another important means of ensuring reliability.

Built-in features that will facilitate convenient in-place testing are important in system design.Standards for the design and testing of atmosphere cleanup systems include ANSI /ASME N509-1976,"Nuclear Power Plant Air Cleaning Units and Com-ponents" (Ref. 1), and ANSI N510-1975, "Testing of Nuclear Air Cleaning Systems" (Ref. 2).Other standards are available for the construction and testing of certain components of systems. Where such standards are acceptable to the NRC staff, they are referenced in this guide. Where no suitable stand-ard exists, acceptable approaches are presented in this guide. ERDA 76-21, "Nuclear Air Cleaning Handbook" (Ref. 3), provides a comprehensive re-view of air filtration systems. It is not ! standard but a guide that discusses a number of acceptable design alternatives.

Not all of the documents mentioned in ANSI N509-1976 (Ref. 1), ANSI N510-1975 (Ref. 2), or other standards referenced in this guide have been the subject of an evaluation by the NRC staff as to their applicability or acceptability.

It should be noted that ANSI N509-1976 and ANSI N510-1975 refer to ORNL-NSIC-65, "Design, Construction and Testing of High-Efficiency Air Filtration Systems for Nuclear Application" (Ref. 4), which has been replaced by ERDA 76-21 (Ref. 3).C. REGULATORY

POSITION Section 2 of ANSI N509-1976 (Ref. 1) and Sec-tion 2 of ANSI N510-1975 (Ref. 2) list additional documents referred to in these standards.

The specific applicability or acceptability of these listed docu-ments, as well as documents listed in other standards referenced in this guide, has been or will be covered separately in other regulatory guides, where appro-priate.Where reference is made to ORNL-NSIC-65 (Ref.4) in ANSI N509-1976 and in ANSI N510-1975, it*~1.140-2 should be interpreted to mean the corresponding por-tion of ERDA 76-21 (Ref. 3).1. Environmental Design Criteria a. The design of each atmosphere cleanup sys-tem installed in a normal ventilation exhaust system should be based on the maximum anticipated operat-ing parameters of temperature, pressure, relative humidity, and radiation levels. The cleanup system should be designed based on continuous operation for the expected life of the plant or the maximum antici-pated service life of the cleanup system.b. If the atmosphere cleanup system is located in an area of high radiation during normal plant opera-tion, adequate shielding of components from the radiation source should be provided.c. The operation of any atmosphere cleanup sys-tem in a normal ventilation exhaust system should not deleteriously affect the expected operation of any engineered-safety-feature system that must operate after a design basis accident.d. The design of the atmosphere cleanup system should consider any significant contaminants such as dusts, chemicals, or other particulate matter that could deleteriously affect the cleanup system's opera-tion.2. System Design Criteria a. Atmosphere cleanup systems installed in normal ventilation exhaust systems need not be re-dundant nor designed to seismic Category I classifica- tion, but should consist of the following sequential components:

(1) HEPA filters before the adsorbers, (2) iodine adsorbers (impregnated activated carbon or equivalent adsorbent such as metal zeolites), (3)ducts and dampers, (4) fans, and (5) related in-strumentation.

If it is desired to reduce the particulate load on the HEPA filters and extend their service life, the installation of prefilters upstream of the initial HEPA bank is suggested.

Consideration should also be given to the installation of a HEPA filter bank downstream of carbon adsorbers to retain carbon fines. Heaters or cooling coils used in conjunction with heaters should be used when the humidity is to be controlled before filtration.

b. The volumetric air flow rate of a single cleanup train should be limited to approximately

30,000 ft 3/min. If a total system air flow in excess of this rate is required, multiple trains should be used. For ease of maintenance, a filter layout that is three HEPA filters high and ten wide is preferred.

c. Each atmosphere cleanup system should be locally instrumented to monitor and alarm pertinent pressure drops and flow rates in accordance with the recommendations of Section 5.6 of ERDA 76-21 (Ref. 3).d. To maintain the radiation exposure to operat-ing personnel as low as is reasonably achievable dur-ing plant maintenance, atmosphere cleanup systems should be designed to control leakage and facilitate maintenance in accordance with the guidelines of Regulatory Guide 8.8, "Information Relevant to En-suring that Occupational Radiation Exposures at Nu-clear Power Stations Will Be As Low As Is Rea-sonably Achievable" (Ref. 5).e. Outdoor air intake openings should be equipped with louvers, grills, screens, or similar pro-tective devices to minimize the effects of high winds, rain, snow, ice, trash, and other contaminants on the operation of the system. If the atmosphere surround-ing the plant could contain significant environmental contaminants, such as dusts and residues from smoke cleanup systems from adjacent coal burning power plants or industry, the design of the system should consider these contaminants and prevent them from affecting the operation of any atmosphere cleanup system.f. Atmosphere cleanup system housings and ductwork should be designed to exhibit on test a maximum total leakage rate as defined in Section 4.12 of ANSI N509-1976 (Ref. 1). Duct and housing leak tests should be performed in accordance with the provisions of Section 6 of ANSI N510-1975 (Ref. 2).3. Component Design Criteria and Qualification Testing a. Adsorption units functon efficiently at a rela-tive humidity of 70% or less. If the relative humidity of the incoming atmosphere is expected to be greater than 70% during normal reactor operation, heaters or cooling coils used in conjunction with heaters should be designed to reduce the relative humidity of the in-coming atmosphere to 70%. Heaters should be de-signed, constructed, and tested in accordance with the requirements of Section 5.5 of ANSI N509-1976 (Ref. 1) exclusive of sizing criteria.b. The HEPA filters should be designed, con-structed, and tested in accordance with the require-ments of Section 5.1 of ANSI N509-1976 (Ref. 1).Each HEPA filter should be tested for penetration of dioctyl phthalate (DOP) in accordance with the provi-sions of MIL,-F-51068 (Ref. 6) and MIL.-STD-282 (Ref. 7).e. Filter and adsorber mounting frames should be designed and constructed in accordance with the provisions of Section 5.6.3 of ANSI N509-1976 (Ref. 1).d. Filter and adsorber banks should be arranged in accordance with the recommendations of Section 4.4 of ERDA 76-21 (Ref. 3).e. System filter housings, including floors and doors, and electrical conduits, drains, and piping in-stalled inside filter housings should be designed and constructed in accordance with the provisions of Sec-tion 5.6 of ANSI N509-1976 (Ref. 1).f. Ductwork associated with the atmosphere cleanup system should be designed, constructed, and 1,140-3-_MMMý

I tested in accordance with the provisions of Section 5.10 of ANSI N509-1976 (Ref. 1).g. The adsorber section of the atmosphere cleanup system may contain any adsorbent material demonstrated to remove gaseous iodine (elemental iodine and organic iodides) from air at the required efficiency.

Since impregnated activated carbon is commonly used, only this adsorbent is discussed in this guide. Each original or replacement batch of im-pregnated activated carbon used in the adsorber sec-tion should meet the qualification and batch test re-sults summarized in Table I of this guide.* If an adsorbent other than impregnated activated carbon is proposed or if the mesh size distribution is different from the specifications in Table 1, the pro-posed adsorbent should have demonstrated the capa-* bility to perform as well L- or better than activated carbon in satisfying the specifications in Table I. If impregnated activated carbon is used as the adsor-bent, the adsorber system should be designed for an average atmosphere residence time of 0.25 sec per two inches of adsorbent bed.h. Adsorber cells should be designed, con-structed, and tested in accordance with the require-ments of Section 5.2 of ANSI N509-1976 (Ref. 1).i. The system fan and motors, mounting, and ductwork connections should be designed, con-structed, and tested in accordance with the require-ments of Sections 5.7 and 5.8 of ANSI N509-1976 (Ref. I).j. The fan or blower used in the atmosphere cleanup system should be capable of operating under the environmental conditions postulated.

k. Ducts and housings should be laid out with a minimum of ledges, protrusions, and crevices that could collect dust and moisture and that could impede personnel or create a hazard to them in the perform-ance of their work. Straightening vanes should be in-stalled where required to ensure representative air flow measurement and uniform flow distribution through cleanup components., 1. Dampers should be designed, constructed, and tested in accordance with the provisions of Section 5.9 of ANSI N509-1976 (Ref. 1).4. Maintenance a. Accessibility of components and maintenance should be considered in the design of atmosphere cleanup systems in accordance with the provisions of Section 2.3.8 of ERDA 76-21 (Ref. 3) and Section 4.7 of ANSI N509-1976 (Ref. 1).b. For ease of maintenance, the system design should provide for a minimum of three feet from..mounting frame to mounting frame between banks of components.

If components are to be replaced, the dimensions to be provided should be the maximum length of the component plus a minimum of three feet.c. The system design should provide for perma-nent test probes with external connections in accord-ance with the provisions of Section 4.11 of ANSI N509-1976 (Ref. 1).d. The cleanup components (e.p., HEPA filters and adsorbers)

should be installed after construction is completed.

5. In-Place Testing Criteria a. A visual inspection of the atmosphere cleanup system and all associated components should be made before each in-place airflow distribution test, DOP test, or activated carbon adsorber section leak test in accordance with the provisions of Section 5 of ANSI N510-1975 (Ref. 2).b. The airflow distribution to the HEPA filters and iodine adsorbers should be tested inplace for uniformity initially and after maintenance affecting the flow distribution.

The distribution should be within +/- 20% of the average flow per unit when tested in accordance with the provisions of Section 9 of "Industrial Ventilation" (Ref. 8) and Section 8 of ANSI N510-1975 (Ref. 2).c. The in-place DOP test for HEPA filters should conform to Section 10 of ANSI N510-1975 (Ref. 2).HEPA filter sections should be tested in place ini-tially and at a frequency not to exceed 18 months thereafter (during a scheduled reactor shutdown is ac-ceptable).

The HEPA filter bank upstream of the ad-sorber section should also be tested following paint-ing, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the HEPA filters could become contaminated from the fumes, chemicals, or foreign materials.

DOP penetration tests of all HEPA filter banks should con-firm a penetration of less than 0.05% at rated flow. A filtration system satisfying this condition can be con-sidered to warrant a 99% removal efficiency for par-ticulates.

HEPA filters that fail to satisfy the in-place test criteria should be replaced with filters qualified pursuant to regulatory position C.3.b of this guide. If the HEPA filter bank is entirely or only partially re-placed, an in-place DOP test should be conducted.

If any welding repairs are necessary on, within, or adjacent to the ducts, housing, or mounting frames, the filters and adsorbers should be removed from the housing during such repairs. These repairs should be completed prior to periodic testing, filter inspection, and in-place testing. The use of silicone sealants or any other temporary patching material on filters, housing, mounting frames, or ducts should not be allowed.d. The activated carbon adsorber section should be leak-tested with a gaseous halogenated hydrocarbon refrigerant in accordance with Section 12 of ANSI N510-1975 (Ref. 2) to ensure that bypass leakage through the adsorber section is less than 0.05%. After the test is completed, air flow through the unit should be maintained until the residual refrigerant gas in the effluent is less than 0.01 ppm. Adsorber leak testing 1.140-4 should be conducted

(1) initially, (2) at a frequency not to exceed 18 months thereafter (during a sched-uled reactor shutdown is acceptable), (3) following removal of an adsorber sample for laboratory testing if the integrity of the adsorber section is affected, and (4) following painting, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the charcoal adsorbers could become contaminated from the funs, chemicals, or foreign materials.

6. Laboratory Testing Criteria for Activated Carbon a. The activated carbon adsorber section of the atmosphere cleanup system should be assigned the decontamination efficiencies given in Table 2 for radioiodine if the following conditions are met: (1) The adsorber section meets the conditions given in regulatory position C.5.d of this gvi'i_., (2) New activated carbon meets the physical property specifications given in Table 1, and (3) Representative samples of used activated carbon pass the laboratory tests given in Table 2.If the activated carbon fails to meet any of the above conditions, it should not be used in adsorption units.b. The efficiency of the activated carbon ad-sorber section should be determined by laboratory testing of representative samples of the activated car-bon exposed simultaneously to the same service con-ditions as the adsorber section. Each representative sample should be not less than two inches in both length and diameter, and each sample should have the same qualification and batch test characteristics as the system adsorbent.

There should be a sufficient number of representative samples located in parallel with the adsorber section to estimate the amount of penetration of the system adsorbent throughout its service life. The design of the samplers should be in accordance with the provisions of Appendix A of ANSI N509-1976 (Ref. 1). Where the system acti-vated carbon is greater than two inches deep, each representative sampling station should consist of enough two-inch samples in series to equal thc thick-ness of the system adsorbent.

Once reprcsentative samples are removed for laboratory test their posi-tions in the sampling array should be blocked off.Laboratory tests of representative samples should be conducted, as indicated in Table 2 of this guide, with the test gas flow in the same direction as the flow during service conditions.

Similar laboratory tests should be performed on an adsorbent sample be-fore loading into the adsorbers to establish an initial point for comparison of future test results. The acti-vated carbon adsorber section should be replaced with new unused activated carbon meeting the physi-cal property specifications of Table I if (1) testing in accordance with the frequency specified in Footnote c of Table 2 results in a representative sample failing to pass the applicable test in Table 2 or (2) no represen-tative sample is available for testing.

D. IMPLEMENTATION

The purpose of this section is to provide informa-tion to applicants and licensees 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 or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein is being and will continue to be used in the evaluation of submittals for operating license or con-struction permit applications until this guide is re-vised as a result of suggestions from the public or additional staff review.I 1.140-5 I,

TABLE 1 PHYSICAL PROPERTIES

OF NEW ACTIVATED

CARBON BATCH TESTS" TO BE PERFORMED

ON FINISHED ADSORBENT Test 1. Particle size distribution

2. Hardness number 3. Ignition te-aperature

4. CCI 4 Activity'5. Radioiodine removal efficiency a. Elemental iodine, 25°C and 95% relative humidity b. Methyl iodide, 25*C and 95% relative humidity 6. Bulk density 7. Impregnant content Acceptable Test Method ASTM D2862 (Ref. 9)RDT M16-IT, Appendix C (Ref. 10)RDT M16-IT, Appendix C (Ref. 10)CCI 4 Activity, RDT M16-IT, Appendix C (Ref. 10)RDT M 16-IT (Ref. 10)para. 4.5.1, except 95% relative humidity air is required RDT MI6-IT (Ref. 10)para. 4.5.3, except 95% relative humidity air is required ASTM D2854 (Ref. 11)State procedure Acceptable Results Retained on #6 ASTM El 1 b Sieve: 0.0%Retained on #8 ASTM El ! Sieve: 5.0% max.Through #8, rctained on #12 Sieve: 40% to 60%Through # 12, retained on # 16 Sieve: 40% to 60%Through # 16 ASTM Elib Sieve: 5.0% max.Through #18 ASTM ElIb Sieve: 1.0% max.95 minimum 330"C minimum at 100 fpm 60 minimum 99.5%95%0.38 g/ml minimum State type (not to exceed 5% by weight)a A "batch test" is a test made on a production batch of a product to establish suitability for a specific application.

A "batch of activated carbon" is a quantity of material of the same grade, type, and series that has been homogenized to exhibit, within reason-able tolerance, the same performance and physical characteristics and for which the manufacturer can demonstrate by acceptable tests and quality control practices such uniformity.

All material in the same batch should be activated, impregnated, and otherwise treated under the same process conditions and procedures in the same process equipment and should be produced under the same manufactur- ing release and instructions.

Material produced in the same charge of batch equipment constitutes a batch; material produced in different charges of the same batch equipment should be included in the same batch only if it can be homogenized as above. The maximum batch size should be 350 ftW of activated carbo

n. b See Reference

12.C This test should be performed on base material.1.140-6 TABLE 2 LABORATORY

TESTS FOR ACTIVATED

CARBON Activated Carbon" Bed Depth b 2 inches. Air filtration system designed to operate inside primary containment.

2 inches. Air filtration system designed to operate outside the primary contain-ment, and relative humidity is controlled to 70%4 inches. Air filtration system designed to operate outside the primary contain-ment, and relative humdity is controlled to 70%.6 inches. Air filtration system designed to operate outside the primary contain-ment, and relativr;

humidity is controlled to 7G%.Assigned Activated Carbon Decontamination Efficiencies For Radioiodine

90%70%Laxboratory Tests for a Representativc SampleC Per Test 5.b in Table I for a methyl iodide pene-tration of less than 10%.Per Test 5.b in Table I at a rclative humidity of 70% for a methyl iodide penetration of less than 10%.Per Test 5.b in Table 1 at a relative humidity of 70%for a methyl iodide pene-tration of less than 10%.Per Test 5.b in Table I at a relative humidity of 70%for a methyl iodide penetra-tion of less than 1%.90%99%* The activated carbon, when new, should meet the specifications of regulatory position C.3.g of this guide.b Multiple beds. e.g., two 2-inch beds in series, should be treated as a single bed of aggregate depth.See regulatory position C.6.b for definition of representative sample. Testing should be performed

(1) initially, (2) at a frequency not to exceed 18 months (during a scheduled reactor shutdown is acceptable), and (3) following painting, fire, or chemical release in any ventilation zone communicating with the system in such a manner that the charcoal adsorbers could become contaminated from the fumes, chemicals, or foreign materials.

REFERENCES

1. American National Standard ANSI/ASME

N509-1976, "Nuclear Power Plant Air Cleaning Units and Components." Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.2. American National Standard ANSI N510-1975,"Testing of Nuclear Air Cleaning Systems,

American Society of Mechanical Engineers.

3. ERDA 76-21, "Nuclear Air Cleaning Hand-book," Oak Ridge National Laboratory, C. A.Burchsted, J. E. Kahn, and A. B. Fuller, March 31, 1976. Copies may be obtained from the Na-tional Technical Information Service, Springfield, Va. 22161.4. ORNL-NSIC-65, "Design, Construction, and Testing of High Efficiency Air Filtration Systems for Nuclear Application," Oak Ridge National Laboratory, C. A. Burchsted and A. B. Fuller, January 1970. Copies may be obtained from the National Technical Information Service.5. Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable," Office of Standards Development, U.S. Nuclear Regulatory Commis-sion.6. MIL-F-51068, "Filter, Particulate.

High-Efficiency, Fire-Resistant" (latest edition), Mili-tary Specification.

Copies may be obtained from the Naval Publications and Forms Center, 5801 Tabor Ave., Philadelphia, Penn. 19120.7. MIL-STD-282, "Filter Units, Protective Cloth-ing, Gas-Mask Components and Related Products: Performance-Test Methods," Military Standard, 28 May 1956. Copies may be obtained from the address given in Reference

6.8. American Conference of Governmental Industrial Hygienists, "Industrial Ventilation," 14th Edi-tion, 1976, Committee on Industrial Ventilation, P.O. Box 453, Lansing, Mich. 48902.9. ASTM D2862-70, "Test for Particle Size Distribu-tion of Granulated Activated Carbon." Copies 1.140-7 a .a may be obtained from the American Society for Testing and Materials, 1916 Race Street, Philadelphia, Penn. 19103.10. RDT Standard M16-IT, "Gas-Phase Adsorbents for Trapping Radioactive Iodine and Iodine Com-pounds." USAEC Division of Reactor Research and Development.

October 1973, Oak Ridge, Tenn.37830.UNITEO STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON, 0. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, S300 11. ASTM D2854-70, "Test for Apparent Density of Activated Carbon," American Society for Test-ing and Materials.

12. ASTM El 1-70, "Specifications for Wire Cloth Sieves for Testing Purposes," American Society for Testing and Materials.

POSTAGE AND FEES PAID U.S. NUCLEAR REGULATOR

I, COMMISSION

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